ENTRY 11153 20180319 14391115300000001 SUBENT 11153001 20180319 14391115300100001 BIB 14 41 1115300100002 TITLE Elastic and inelastic scattering of fast neutrons from 1115300100003 6Li and 7Li 1115300100004 AUTHOR (J.C.Hopkins, D.M.Drake, H.Conde) 1115300100005 REFERENCE (J,NP/A,107,139,1968) 1115300100006 #doi:10.1016/0375-9474(68)90731-8 1115300100007 (R,LA-3765,1967) NP/A article + numerical data tables 1115300100008 (C,66WASH,2,634,1966) part of final data tables given 1115300100009 REL-REF (I,,H.Conde+,C,66WASH,2,735,1966) Nai detector details 1115300100010 INSTITUTE (1USALAS,2SWDFOA) 1115300100011 FACILITY (VDG,1USALAS) 8 MV Van de Graaff 1115300100012 INC-SOURCE (P-T) En=3.35 and 4.83 MeV 1115300100013 (D-D) en=5.74 and 7.5 MeV 1115300100014 SAMPLE Separated Li isotopes (purity>99%, 2 cm diam, 2.54 cm 1115300100015 long) canned in thin Al containers. 1115300100016 Cylindrical polythene (0.51 cm diam, 1.9cm long) for 1115300100017 cross section normalization. 1115300100018 Empty can runs were done for background subtraction. 1115300100019 DETECTOR (SCIN) NE102A plastic scintillator (12.7 in diam., 1115300100020 2.5 cm thick) 1115300100021 (NAICR) 5.8 cm in diam, 15.2 cm in length, energy 1115300100022 resolution of about 9.5% for the 0.67 gamma-ray 1115300100023 METHOD (TOF) Flight path of 2.3 m 1115300100024 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 1115300100025 CORRECTION Corrected for flux attenuation and multiple 1115300100026 scattering by the MAGGIE code except for double 1115300100027 differential cross sections. 1115300100028 COMMENT By compiler (2016-09-22): Angular-integrated cross 1115300100029 sections in Appendix A of LA-3765 (1967) are slightly 1115300100030 different from those in Tables I+II of LA-3765 (1967) 1115300100031 and Tables 1+2 of Nucl.Phys.A107(1968)139. Values in 1115300100032 Appendix A are adopted in this EXFOR entry except for 1115300100033 005 and 015. 1115300100034 HISTORY (19760628T) Translated from SCISRS 1115300100035 (19800814A) converted to REACTION formalism 1115300100036 (19840207A) BIB update 1115300100037 (20160921A) On. 002 deleted. 003-020 recompiled, 021- 1115300100038 024 added. 1115300100039 (20180327A) BP: LANL-3765 data were added to 1115300100040 subentries 22,23 and a large number of new subentries 1115300100041 were created after optical character recognition 1115300100042 of PDF pages 12-42, added doi. 1115300100043 ENDBIB 41 0 1115300100044 NOCOMMON 0 0 1115300100045 ENDSUBENT 44 0 1115300199999 NOSUBENT 11153002 20160921 14221115300200001 SUBENT 11153003 20160921 14221115300300001 BIB 5 7 1115300300002 REACTION (3-LI-6(N,INL)3-LI-6,,SIG,,MSC,DERIV) continuum part 1115300300003 ANALYSIS Extrapolated below detector cut-off to zero energy 1115300300004 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115300300005 STATUS (TABLE) p15, p22, p34 of LANL-3765 1115300300006 (DEP,11153004) Angular diff. cross section given 1115300300007 HISTORY (19840207A) BIB corrected, COMMON added. 1115300300008 (20160921A) On. Recompiled. 1115300300009 ENDBIB 7 0 1115300300010 NOCOMMON 0 0 1115300300011 DATA 4 3 1115300300012 EN EN-RSL DATA DATA-ERR 1115300300013 MEV KEV MB MB 1115300300014 4.83 47. 461. 40. 1115300300015 5.74 230. 485. 48. 1115300300016 7.5 170. 569. 57. 1115300300017 ENDDATA 5 0 1115300300018 ENDSUBENT 17 0 1115300399999 SUBENT 11153004 20160921 14221115300400001 BIB 6 13 1115300400002 REACTION (3-LI-6(N,INL)3-LI-6,,DA,,MSC,DERIV) continuum part 1115300400003 ANALYSIS Extrapolated below detector cut-off to zero energy 1115300400004 ERR-ANALYS (DATA-ERR1) No information on source of uncertainty 1115300400005 (DATA-ERR2) Absolute standard deviation 1115300400006 STATUS (TABLE) p15, p22, p34 of LANL-3765 1115300400007 (SCSRS) Uncertainty at 4.83 MeV 1115300400008 (DEP,11153021) Data above the cut-off energy 1115300400009 COMMENT By compiler (2016-09-22): 1115300400010 The uncertainty at 4.83 MeV printed in a hard copy of 1115300400011 LANL-3765 owned by NDS is not readable, and therefore 1115300400012 the value converted from SCISRS is kept. 1115300400013 HISTORY (19840207A) COMMON added. 1115300400014 (20160921A) On. Recompiled. 1115300400015 ENDBIB 13 0 1115300400016 NOCOMMON 0 0 1115300400017 DATA 6 20 1115300400018 EN EN-RSL ANG DATA DATA-ERR1 DATA-ERR2 1115300400019 MEV KEV ADEG MB/SR MB/SR MB/SR 1115300400020 4.83 47. 40. 60.0 5.1 1115300400021 4.83 47. 55. 59.6 5.8 1115300400022 4.83 47. 72.5 52.0 6.1 1115300400023 4.83 47. 90. 39.0 5.4 1115300400024 4.83 47. 110. 19.7 7.0 1115300400025 4.83 47. 135. 12.9 6.7 1115300400026 5.74 230. 30. 72.7 7.2 1115300400027 5.74 230. 39. 57.2 6.0 1115300400028 5.74 230. 47. 62.7 6.2 1115300400029 5.74 230. 55. 51.1 5.0 1115300400030 5.74 230. 72.5 43.0 4.3 1115300400031 5.74 230. 90. 35.0 3.6 1115300400032 5.74 230. 110. 26.5 2.8 1115300400033 5.74 230. 134. 20.9 2.4 1115300400034 7.5 170. 39. 62.2 6.7 1115300400035 7.5 170. 55. 67.5 7.4 1115300400036 7.5 170. 72.5 56.3 7.1 1115300400037 7.5 170. 90. 40.1 5.6 1115300400038 7.5 170. 110. 33.2 4.4 1115300400039 7.5 170. 135. 26.6 3.0 1115300400040 ENDDATA 22 0 1115300400041 ENDSUBENT 40 0 1115300499999 SUBENT 11153005 20160921 14221115300500001 BIB 5 7 1115300500002 REACTION (3-LI-6(N,N+D)2-HE-4,,SIG) 1115300500003 ANALYSIS Inelastic to 2.18 MeV + continuum 1115300500004 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115300500005 STATUS (TABLE) Table I of LANL-3765 1115300500006 (DEP,11153003) Continuum part 1115300500007 (DEP,11153007) 2.18 MeV inelastic part 1115300500008 HISTORY (20160921A) On. Recompiled. 1115300500009 ENDBIB 7 0 1115300500010 NOCOMMON 0 0 1115300500011 DATA 4 3 1115300500012 EN EN-RSL DATA DATA-ERR 1115300500013 MEV KEV MB MB 1115300500014 4.83 47. 670. 42. 1115300500015 5.74 230. 650. 51. 1115300500016 7.5 170. 720. 59. 1115300500017 ENDDATA 5 0 1115300500018 ENDSUBENT 17 0 1115300599999 SUBENT 11153006 20160921 14221115300600001 BIB 4 6 1115300600002 REACTION (3-LI-6(N,EL)3-LI-6,,SIG) 1115300600003 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115300600004 STATUS (TABLE) p14, p21, p33 of LANL-3765 1115300600005 (DEP,11153008) Angular diff. cross section given 1115300600006 HISTORY (19820107U) BIB update 1115300600007 (20160921A) On. Recompiled. 1115300600008 ENDBIB 6 0 1115300600009 NOCOMMON 0 0 1115300600010 DATA 4 3 1115300600011 EN EN-RSL DATA DATA-ERR 1115300600012 MEV KEV MB MB 1115300600013 4.83 47. 1350. 60. 1115300600014 5.74 230. 1276. 51. 1115300600015 7.5 170. 1194. 48. 1115300600016 ENDDATA 5 0 1115300600017 ENDSUBENT 16 0 1115300699999 SUBENT 11153007 20160921 14221115300700001 BIB 4 6 1115300700002 REACTION (3-LI-6(N,INL)3-LI-6,PAR,SIG) 1115300700003 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115300700004 STATUS (TABLE) p14, p21, p33 of LANL-3765 1115300700005 (DEP,11153009) Angular diff. cross section given 1115300700006 HISTORY (19820107U) BIB update 1115300700007 (20160921A) On. Recompiled. 1115300700008 ENDBIB 6 0 1115300700009 COMMON 1 3 1115300700010 E-LVL 1115300700011 MEV 1115300700012 2.18 1115300700013 ENDCOMMON 3 0 1115300700014 DATA 4 3 1115300700015 EN EN-RSL DATA DATA-ERR 1115300700016 MEV KEV MB MB 1115300700017 4.83 47. 208. 13. 1115300700018 5.74 230. 170. 17. 1115300700019 7.5 170. 149. 15. 1115300700020 ENDDATA 5 0 1115300700021 ENDSUBENT 20 0 1115300799999 SUBENT 11153008 20160921 14221115300800001 BIB 4 5 1115300800002 REACTION (3-LI-6(N,EL)3-LI-6,,DA) 1115300800003 ERR-ANALYS (ERR-1) Relative standard deviation 1115300800004 (ERR-T) Absolute standard deviation 1115300800005 STATUS (TABLE) p14, p21, p33 of LANL-3765 1115300800006 HISTORY (20160921A) On. Recompiled. 1115300800007 ENDBIB 5 0 1115300800008 NOCOMMON 0 0 1115300800009 DATA 6 20 1115300800010 EN EN-RSL COS-CM DATA-CM ERR-1 ERR-T 1115300800011 MEV KEV NO-DIM MB/SR MB/SR MB/SR 1115300800012 4.83 47. 0.692 193.0 4.0 8.0 1115300800013 4.83 47. 0.456 105.0 2.5 5.0 1115300800014 4.83 47. 0.144 50.0 2.0 4.0 1115300800015 4.83 47. -0.168 43.0 1.5 3.0 1115300800016 4.83 47. -0.486 46.0 1.5 3.0 1115300800017 4.83 47. -0.786 58.0 1.5 3.0 1115300800018 5.74 230. 0.821 307.0 10.3 15.0 1115300800019 5.74 230. 0.706 204.0 7.0 10.0 1115300800020 5.74 230. 0.587 141.0 6.4 8.5 1115300800021 5.74 230. 0.456 89.3 4.3 5.4 1115300800022 5.74 230. 0.144 40.4 2.2 2.8 1115300800023 5.74 230. -0.168 33.8 1.9 2.4 1115300800024 5.74 230. -0.486 36.2 2.0 2.5 1115300800025 5.74 230. -0.776 38.9 2.2 2.7 1115300800026 7.5 170. 0.706 196.0 6.9 9.8 1115300800027 7.5 170. 0.456 74.1 3.3 4.4 1115300800028 7.5 170. 0.144 27.4 1.5 1.9 1115300800029 7.5 170. -0.168 24.8 1.4 1.7 1115300800030 7.5 170. -0.486 24.7 1.4 1.7 1115300800031 7.5 170. -0.786 26.4 1.4 1.8 1115300800032 ENDDATA 22 0 1115300800033 ENDSUBENT 32 0 1115300899999 SUBENT 11153009 20160921 14221115300900001 BIB 4 5 1115300900002 REACTION (3-LI-6(N,INL)3-LI-6,PAR,DA) 1115300900003 ERR-ANALYS (ERR-1) Relative standard deviation 1115300900004 (ERR-T) Absolute standard deviation 1115300900005 STATUS (TABLE) p14, p21, p33 of LANL-3765 1115300900006 HISTORY (20160921A) On. Recompiled. 1115300900007 ENDBIB 5 0 1115300900008 COMMON 1 3 1115300900009 E-LVL 1115300900010 MEV 1115300900011 2.18 1115300900012 ENDCOMMON 3 0 1115300900013 DATA 6 20 1115300900014 EN EN-RSL COS-CM DATA-CM ERR-1 ERR-T 1115300900015 MEV KEV NO-DIM MB/SR MB/SR MB/SR 1115300900016 4.83 47. 0.656 16.5 0.8 1.4 1115300900017 4.83 47. 0.399 19.8 0.8 1.4 1115300900018 4.83 47. 0.072 23.4 1.3 2.0 1115300900019 4.83 47. -0.244 17.1 1.0 1.5 1115300900020 4.83 47. -0.549 14.5 1.0 1.4 1115300900021 4.83 47. -0.818 10.6 1.1 1.3 1115300900022 5.74 230. 0.804 15.9 1.5 1.6 1115300900023 5.74 230. 0.680 15.9 1.5 1.6 1115300900024 5.74 230. 0.552 15.2 1.4 1.5 1115300900025 5.74 230. 0.413 17.1 1.6 1.7 1115300900026 5.74 230. 0.089 15.1 1.4 1.5 1115300900027 5.74 230. -0.225 12.7 1.2 1.3 1115300900028 5.74 230. -0.533 10.9 1.0 1.1 1115300900029 5.74 230. -0.802 9.6 0.9 1.0 1115300900030 7.5 170. 0.689 16.0 1.5 1.6 1115300900031 7.5 170. 0.427 14.4 1.3 1.4 1115300900032 7.5 170. 0.107 13.2 1.2 1.3 1115300900033 7.5 170. -0.206 11.4 1.0 1.1 1115300900034 7.5 170. -0.518 7.8 0.7 0.8 1115300900035 7.5 170. -0.803 7.4 0.6 0.7 1115300900036 ENDDATA 22 0 1115300900037 ENDSUBENT 36 0 1115300999999 SUBENT 11153010 20160921 14221115301000001 BIB 4 5 1115301000002 REACTION (3-LI-7(N,INL)3-LI-7,PAR,DA,,MSC) continuum part 1115301000003 ERR-ANALYS (ERR-1) Relative standard deviation 1115301000004 (ERR-T) Absolute standard deviation 1115301000005 STATUS (TABLE) p18, p28, p39 of LANL-3765 1115301000006 HISTORY (20160921A) On. Recompiled. 1115301000007 ENDBIB 5 0 1115301000008 NOCOMMON 0 0 1115301000009 DATA 7 20 1115301000010 EN EN-RSL ANG E-MIN DATA ERR-1 1115301000011 ERR-T 1115301000012 MEV KEV ADEG MEV MB/SR MB/SR 1115301000013 MB/SR 1115301000014 4.83 47. 40. 0.4 8.9 2.3 1115301000015 1115301000016 4.83 47. 55. 0.4 9.5 1.9 1115301000017 1115301000018 4.83 47. 72.5 0.4 7.9 1.7 1115301000019 1115301000020 4.83 47. 90. 0.4 4.6 1.7 1115301000021 1115301000022 4.83 47. 110. 0.4 4.3 1.5 1115301000023 1115301000024 4.83 47. 135. 0.4 4.1 1.6 1115301000025 1115301000026 5.74 230. 30. 0.5 38.2 1115301000027 6.6 1115301000028 5.74 230. 39. 0.5 27.7 1115301000029 5.6 1115301000030 5.74 230. 47. 0.4 26.8 1115301000031 5.0 1115301000032 5.74 230. 55. 0.4 28.3 1115301000033 4.4 1115301000034 5.74 230. 72.5 0.7 12.3 1115301000035 1.2 1115301000036 5.74 230. 90. 0.6 9.6 1115301000037 1.0 1115301000038 5.74 230. 110. 0.6 7.4 1115301000039 0.7 1115301000040 5.74 230. 134. 0.6 2.5 1115301000041 0.3 1115301000042 7.5 170. 39. 1.0 24.8 1115301000043 2.7 1115301000044 7.5 170. 55. 0.5 33.4 1115301000045 3.7 1115301000046 7.5 170. 72.5 0.5 21.5 1115301000047 2.4 1115301000048 7.5 170. 90. 0.5 17.3 1115301000049 1.9 1115301000050 7.5 170. 110. 0.4 16.3 1115301000051 1.8 1115301000052 7.5 170. 135. 0.4 13.6 1115301000053 1.5 1115301000054 ENDDATA 44 0 1115301000055 ENDSUBENT 54 0 1115301099999 SUBENT 11153011 20160921 14221115301100001 BIB 5 7 1115301100002 REACTION (3-LI-7(N,INL)3-LI-7,,SIG,,MSC,DERIV) continuum part 1115301100003 ANALYSIS Extrapolated below detector cut-off to zero energy 1115301100004 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115301100005 STATUS (TABLE) p18, p28, p39 of LANL-3765 1115301100006 (DEP,11153013) Angular diff. cross section given 1115301100007 HISTORY (19840207A) BIB corrected, COM MON added. 1115301100008 (20160921A) On. Recompiled. 1115301100009 ENDBIB 7 0 1115301100010 NOCOMMON 0 0 1115301100011 DATA 4 3 1115301100012 EN EN-RSL DATA DATA-ERR 1115301100013 MEV KEV MB MB 1115301100014 4.83 47. 97. 22. 1115301100015 5.74 230. 224. 34. 1115301100016 7.5 170. 311. 37. 1115301100017 ENDDATA 5 0 1115301100018 ENDSUBENT 17 0 1115301199999 SUBENT 11153012 20160921 14221115301200001 BIB 4 6 1115301200002 REACTION (3-LI-7(N,SCT)3-LI-7,PAR,SIG) 1115301200003 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115301200004 STATUS (TABLE) p27, p38 of LANL-3765 1115301200005 (DEP,11153014) Angular diff. cross section given 1115301200006 HISTORY (19820107U) BIB update 1115301200007 (20160921A) On. Recompiled. 1115301200008 ENDBIB 6 0 1115301200009 COMMON 1 3 1115301200010 E-LVL 1115301200011 MEV 1115301200012 0.478 1115301200013 ENDCOMMON 3 0 1115301200014 DATA 4 2 1115301200015 EN EN-RSL DATA DATA-ERR 1115301200016 MEV KEV MB MB 1115301200017 5.74 230. 1776. 71. 1115301200018 7.5 170. 1519. 61. 1115301200019 ENDDATA 4 0 1115301200020 ENDSUBENT 19 0 1115301299999 SUBENT 11153013 20160921 14221115301300001 BIB 5 8 1115301300002 REACTION (3-LI-7(N,INL)3-LI-7,,DA,,MSC,DERIV) continuum part 1115301300003 ANALYSIS Extrapolated below detector cut-off to zero energy 1115301300004 ERR-ANALYS (ERR-1) Relative standard deviation 1115301300005 (ERR-T) Absolute standard deviation 1115301300006 STATUS (TABLE) p18, p28, p39 of LANL-3765 1115301300007 (DEP,11153010) Data above the cut-off energy 1115301300008 HISTORY (19840207A) COMMON added. 1115301300009 (20160921A) On. Recompiled. 1115301300010 ENDBIB 8 0 1115301300011 NOCOMMON 0 0 1115301300012 DATA 6 20 1115301300013 EN EN-RSL ANG DATA ERR-1 ERR-T 1115301300014 MEV KEV ADEG MB/SR MB/SR MB/SR 1115301300015 4.83 47. 40. 9.8 2.4 1115301300016 4.83 47. 55. 10.8 2.0 1115301300017 4.83 47. 72.5 9.3 1.8 1115301300018 4.83 47. 90. 5.8 1.8 1115301300019 4.83 47. 110. 5.9 1.7 1115301300020 4.83 47. 135. 6.4 2.0 1115301300021 5.74 230. 30. 47.6 7.9 1115301300022 5.74 230. 39. 38.3 7.7 1115301300023 5.74 230. 47. 30.1 5.3 1115301300024 5.74 230. 55. 34.3 5.3 1115301300025 5.74 230. 72.5 18.3 3.2 1115301300026 5.74 230. 90. 13.4 2.1 1115301300027 5.74 230. 110. 9.9 1.5 1115301300028 5.74 230. 134. 4.0 1.8 1115301300029 7.5 170. 39. 33.6 5.2 1115301300030 7.5 170. 55. 37.5 4.3 1115301300031 7.5 170. 72.5 25.1 3.0 1115301300032 7.5 170. 90. 20.9 2.6 1115301300033 7.5 170. 110. 20.4 2.8 1115301300034 7.5 170. 135. 17.7 2.6 1115301300035 ENDDATA 22 0 1115301300036 ENDSUBENT 35 0 1115301399999 SUBENT 11153014 20160921 14221115301400001 BIB 4 5 1115301400002 REACTION (3-LI-7(N,SCT)3-LI-7,PAR,DA) 1115301400003 ERR-ANALYS (ERR-1) Relative standard deviation 1115301400004 (ERR-T) Absolute standard deviation 1115301400005 STATUS (TABLE) p27, p38 of LANL-3765 1115301400006 HISTORY (20160921A) On. Recompiled. 1115301400007 ENDBIB 5 0 1115301400008 COMMON 1 3 1115301400009 E-LVL 1115301400010 MEV 1115301400011 0.478 1115301400012 ENDCOMMON 3 0 1115301400013 DATA 6 14 1115301400014 EN EN-RSL COS-CM DATA-CM ERR-1 ERR-T 1115301400015 MEV KEV NO-DIM MB/SR MB/SR MB/SR 1115301400016 5.74 230. 0.828 379.0 13.0 19.0 1115301400017 5.74 230. 0.717 266.0 9.1 13.0 1115301400018 5.74 230. 0.601 182.0 8.3 11.0 1115301400019 5.74 230. 0.473 121.0 5.5 7.3 1115301400020 5.74 230. 0.167 64.0 3.6 4.5 1115301400021 5.74 230. -0.144 75.1 4.2 5.3 1115301400022 5.74 230. -0.466 85.3 4.8 6.0 1115301400023 5.74 230. -0.765 73.7 4.2 5.2 1115301400024 7.5 170. 0.717 249.0 8.8 12.5 1115301400025 7.5 170. 0.473 105.2 4.7 6.3 1115301400026 7.5 170. 0.167 51.0 2.9 3.6 1115301400027 7.5 170. -0.144 52.8 3.0 3.7 1115301400028 7.5 170. -0.466 54.7 3.0 3.8 1115301400029 7.5 170. -0.775 49.0 2.7 3.4 1115301400030 ENDDATA 16 0 1115301400031 ENDSUBENT 30 0 1115301499999 SUBENT 11153015 20160921 14221115301500001 BIB 4 6 1115301500002 REACTION (3-LI-7(N,N+T)2-HE-4,,SIG) 1115301500003 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115301500004 STATUS (TABLE) Table I of LANL-3765 1115301500005 (DEP,11153011) Continuum part 1115301500006 (DEP,11153017) 4.63 MeV inelastic part 1115301500007 HISTORY (20160921A) On. Recompiled. 1115301500008 ENDBIB 6 0 1115301500009 NOCOMMON 0 0 1115301500010 DATA 4 3 1115301500011 EN EN-RSL DATA DATA-ERR 1115301500012 MEV KEV MB MB 1115301500013 4.83 47. 100. 22. 1115301500014 5.74 230. 330. 38. 1115301500015 7.5 170. 430. 39. 1115301500016 ENDDATA 5 0 1115301500017 ENDSUBENT 16 0 1115301599999 SUBENT 11153016 20160921 14221115301600001 BIB 4 6 1115301600002 REACTION (3-LI-7(N,EL)3-LI-7,,SIG) 1115301600003 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115301600004 STATUS (TABLE) p13, p18 of LANL-3765 1115301600005 (DEP,11153018) Angular diff. cross section given 1115301600006 HISTORY (19820107U) BIB update 1115301600007 (20160921A) On. Recompiled. 1115301600008 ENDBIB 6 0 1115301600009 NOCOMMON 0 0 1115301600010 DATA 4 2 1115301600011 EN EN-RSL DATA DATA-ERR 1115301600012 MEV KEV MB MB 1115301600013 3.35 62. 1863. 52. 1115301600014 4.83 47. 2225. 89. 1115301600015 ENDDATA 4 0 1115301600016 ENDSUBENT 15 0 1115301699999 SUBENT 11153017 20160921 14221115301700001 BIB 5 8 1115301700002 REACTION (3-LI-7(N,INL)3-LI-7,PAR,SIG) 1115301700003 FLAG (1.) Assumed 6Li angular distribution shape 1115301700004 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115301700005 STATUS (TABLE) p13, p18, p27, p38 of LANL-3765 1115301700006 (DEP,11153019) Angular diff. cross section given 1115301700007 (DEP,11153020) Angular diff. cross section given 1115301700008 HISTORY (19820107U) BIB update 1115301700009 (20160921A) On. Recompiled. 1115301700010 ENDBIB 8 0 1115301700011 NOCOMMON 0 0 1115301700012 DATA 6 4 1115301700013 E-LVL EN EN-RSL DATA DATA-ERR FLAG 1115301700014 MEV MEV KEV MB MB NO-DIM 1115301700015 0.478 3.35 62. 242. 20. 1115301700016 0.478 4.83 47. 178. 27. 1115301700017 4.63 5.74 230. 114. 17. 1. 1115301700018 4.63 7.5 170. 122. 12. 1115301700019 ENDDATA 6 0 1115301700020 ENDSUBENT 19 0 1115301799999 SUBENT 11153018 20160921 14221115301800001 BIB 4 5 1115301800002 REACTION (3-LI-7(N,EL)3-LI-7,,DA) 1115301800003 ERR-ANALYS (ERR-1) Relative standard deviation 1115301800004 (ERR-T) Absolute standard deviation 1115301800005 STATUS (TABLE) p13, p18 of LANL-3765 1115301800006 HISTORY (20160921A) On. Recompiled. 1115301800007 ENDBIB 5 0 1115301800008 NOCOMMON 0 0 1115301800009 DATA 6 12 1115301800010 EN EN-RSL COS-CM DATA-CM ERR-1 ERR-T 1115301800011 MEV KEV NO-DIM MB/SR MB/SR MB/SR 1115301800012 3.35 62. 0.703 219.0 4.5 9.0 1115301800013 3.35 62. 0.473 150.0 3.0 6.0 1115301800014 3.35 62. 0.167 98.0 2.5 5.0 1115301800015 3.35 62. -0.144 80. 2.0 4.0 1115301800016 3.35 62. -0.466 87. 2.0 4.0 1115301800017 3.35 62. -0.775 154. 3.5 7.0 1115301800018 4.83 47. 0.703 267.0 6.5 13.0 1115301800019 4.83 47. 0.473 122.0 3.0 6.0 1115301800020 4.83 47. 0.167 79.0 2.5 5.0 1115301800021 4.83 47. -0.144 98.0 3.0 6.0 1115301800022 4.83 47. -0.466 128.0 4.0 8.0 1115301800023 4.83 47. -0.775 163.0 4.5 9.0 1115301800024 ENDDATA 14 0 1115301800025 ENDSUBENT 24 0 1115301899999 SUBENT 11153019 20160921 14221115301900001 BIB 4 5 1115301900002 REACTION (3-LI-7(N,INL)3-LI-7,PAR,DA) 1115301900003 ERR-ANALYS (ERR-1) Relative standard deviation 1115301900004 (ERR-T) Absolute standard deviation 1115301900005 STATUS (TABLE) p13, p18 of LANL-3765 1115301900006 HISTORY (20160921A) On. Recompiled. 1115301900007 ENDBIB 5 0 1115301900008 COMMON 1 3 1115301900009 E-LVL 1115301900010 MEV 1115301900011 0.478 1115301900012 ENDCOMMON 3 0 1115301900013 DATA 6 12 1115301900014 EN EN-RSL COS-CM DATA-CM ERR-1 ERR-T 1115301900015 MEV KEV NO-DIM MB/SR MB/SR MB/SR 1115301900016 3.35 62. 0.697 22.0 0.5 1.7 1115301900017 3.35 62. 0.463 17.2 0.4 1.3 1115301900018 3.35 62. 0.155 14.7 1.0 1.1 1115301900019 3.35 62. -0.156 16.8 0.4 1.3 1115301900020 3.35 62. -0.477 20.0 0.5 1.5 1115301900021 3.35 62. -0.782 21.5 0.4 1.6 1115301900022 4.83 47. 0.700 12.7 2.6 4.3 1115301900023 4.83 47. 0.466 15.4 0.9 1.5 1115301900024 4.83 47. 0.158 18.7 3.1 5.1 1115301900025 4.83 47. -0.156 14.1 1.3 2.1 1115301900026 4.83 47. -0.473 13.9 1.3 2.2 1115301900027 4.83 47. -0.779 8.5 2.0 3.3 1115301900028 ENDDATA 14 0 1115301900029 ENDSUBENT 28 0 1115301999999 SUBENT 11153020 20160921 14221115302000001 BIB 4 5 1115302000002 REACTION (3-LI-7(N,INL)3-LI-7,PAR,DA) 1115302000003 ERR-ANALYS (ERR-1) Relative standard deviation 1115302000004 (ERR-T) Absolute standard deviation 1115302000005 STATUS (TABLE) p27, p38 of LANL-3765 1115302000006 HISTORY (20160921A) On. Recompiled. 1115302000007 ENDBIB 5 0 1115302000008 COMMON 1 3 1115302000009 E-LVL 1115302000010 MEV 1115302000011 4.63 1115302000012 ENDCOMMON 3 0 1115302000013 DATA 6 10 1115302000014 EN EN-RSL COS-CM DATA-CM ERR-1 ERR-T 1115302000015 MEV KEV NO-DIM MB/SR MB/SR MB/SR 1115302000016 5.74 230. 0.707 11.3 1.7 1.7 1115302000017 5.74 230. 0.530 11.9 1.8 1.8 1115302000018 5.74 230. 0.355 10.7 1.6 1.6 1115302000019 5.74 230. 0.173 8.7 1.3 1.3 1115302000020 7.5 170. 0.661 10.7 1.0 1.1 1115302000021 7.5 170. 0.382 11.9 1.1 1.2 1115302000022 7.5 170. 0.050 14.2 1.3 1.4 1115302000023 7.5 170. -0.265 10.3 0.9 1.0 1115302000024 7.5 170. -0.565 6.9 0.6 0.7 1115302000025 7.5 170. -0.827 4.7 0.5 0.5 1115302000026 ENDDATA 12 0 1115302000027 ENDSUBENT 26 0 1115302099999 SUBENT 11153021 20160921 14221115302100001 BIB 4 5 1115302100002 REACTION (3-LI-6(N,INL)3-LI-6,PAR,DA,,MSC) continuum part 1115302100003 ERR-ANALYS (ERR-1) Relative standard deviation 1115302100004 (ERR-T) Absolute standard deviation 1115302100005 STATUS (TABLE) p15, p22, p34 of LANL-3765 1115302100006 HISTORY (20160921C) On 1115302100007 ENDBIB 5 0 1115302100008 NOCOMMON 0 0 1115302100009 DATA 7 20 1115302100010 EN EN-RSL ANG E-MIN DATA ERR-1 1115302100011 ERR-T 1115302100012 MEV KEV ADEG MEV MB/SR MB/SR 1115302100013 MB/SR 1115302100014 4.83 47. 40. 0.4 49.8 1.9 1115302100015 1115302100016 4.83 47. 55. 0.4 48.3 2.9 1115302100017 1115302100018 4.83 47. 72.5 0.4 39.4 3.0 1115302100019 1115302100020 4.83 47. 90. 0.4 29.6 2.9 1115302100021 1115302100022 4.83 47. 110. 0.4 16.7 5.0 1115302100023 1115302100024 4.83 47. 135. 0.4 10.8 5.6 1115302100025 1115302100026 5.74 230. 30. 0.5 68.7 1115302100027 6.9 1115302100028 5.74 230. 39. 0.6 50.8 1115302100029 5.1 1115302100030 5.74 230. 47. 0.4 59.2 1115302100031 6.0 1115302100032 5.74 230. 55. 0.4 48.1 1115302100033 4.8 1115302100034 5.74 230. 72.5 0.4 40.0 1115302100035 4.0 1115302100036 5.74 230. 90. 0.4 31.8 1115302100037 3.2 1115302100038 5.74 230. 110. 0.4 23.5 1115302100039 2.4 1115302100040 5.74 230. 134. 0.4 17.7 1115302100041 1.8 1115302100042 7.5 170. 39. 0.5 57.4 1115302100043 6.3 1115302100044 7.5 170. 55. 0.4 62.0 1115302100045 6.8 1115302100046 7.5 170. 72.5 0.5 46.3 1115302100047 5.1 1115302100048 7.5 170. 90. 0.6 31.3 1115302100049 3.4 1115302100050 7.5 170. 110. 0.5 26.6 1115302100051 2.9 1115302100052 7.5 170. 135. 0.4 23.6 1115302100053 2.6 1115302100054 ENDDATA 44 0 1115302100055 ENDSUBENT 54 0 1115302199999 SUBENT 11153022 20180327 14391115302200001 BIB 5 11 1115302200002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115302200003 CORRECTION The energy spectra are intended only to show the 1115302200004 continuum neutrons. The cross sections for the 1115302200005 discrete peaks given in the energy spectra have not 1115302200006 been corrected for multiple scattering and 1115302200007 attenuation. The cross sections for discrete peaks are 1115302200008 given separately and have been corrected properly. 1115302200009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115302200010 STATUS (TABLE) page 15 of LANL-3765. 1115302200011 HISTORY (20160921C) On 1115302200012 (20180327A) BP: Added numerical data. 1115302200013 ENDBIB 11 0 1115302200014 COMMON 2 3 1115302200015 EN ANG 1115302200016 MEV ADEG 1115302200017 4.83 40.0 1115302200018 ENDCOMMON 3 0 1115302200019 DATA 3 28 1115302200020 E DATA DATA-ERR 1115302200021 MEV MB/SR/MEV MB/SR/MEV 1115302200022 0.425 48.0 1.0 1115302200023 0.500 31.1 6.0 1115302200024 0.600 26.3 9.0 1115302200025 0.701 23.5 1.0 1115302200026 0.805 28.2 3.0 1115302200027 0.908 28.2 1.0 1115302200028 1.008 29.2 10.0 1115302200029 1.009 26.3 4.0 1115302200030 1.212 24.5 3.0 1115302200031 1.315 24.5 1.0 1115302200032 1.416 26.3 3.0 1115302200033 1.519 22.6 1.0 1115302200034 1.624 22.6 1.0 1115302200035 1.719 35.4 7.0 1115302200036 1.822 20.7 2.0 1115302200037 1.934 24.5 1.0 1115302200038 2.029 29.2 1.0 1115302200039 2.131 46.5 6.0 1115302200040 2.240 96.9 18.0 1115302200041 2.342 69.6 8.0 1115302200042 2.431 19.6 7.0 1115302200043 2.576 11.3 1.0 1115302200044 2.647 7.5 1.0 1115302200045 2.755 6.6 1.0 1115302200046 2.846 7.5 1.0 1115302200047 2.942 8.5 1.0 1115302200048 3.042 7.5 1.0 1115302200049 3.148 8.5 1.0 1115302200050 ENDDATA 30 0 1115302200051 ENDSUBENT 50 0 1115302299999 SUBENT 11153023 20180327 14391115302300001 BIB 5 11 1115302300002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115302300003 CORRECTION The energy spectra are intended only to show the 1115302300004 continuum neutrons. The cross sections for the 1115302300005 discrete peaks given in the energy spectra have not 1115302300006 been corrected for multiple scattering and 1115302300007 attenuation. The cross sections for discrete peaks are 1115302300008 given separately and have been corrected properly. 1115302300009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115302300010 STATUS (TABLE) page 19 of LANL-3765. 1115302300011 HISTORY (20160921C) On 1115302300012 (20180327A) BP: Added numerical data. 1115302300013 ENDBIB 11 0 1115302300014 COMMON 2 3 1115302300015 EN ANG 1115302300016 MEV ADEG 1115302300017 4.83 40.0 1115302300018 ENDCOMMON 3 0 1115302300019 DATA 3 16 1115302300020 E DATA DATA-ERR 1115302300021 MEV MB/SR/MEV MB/SR/MEV 1115302300022 0.42 4.0 9.2 1115302300023 0.50 -1.9 4.7 1115302300024 0.60 8.1 3.7 1115302300025 0.70 10.4 3.0 1115302300026 0.80 6.7 2.6 1115302300027 0.90 7.5 2.5 1115302300028 1.00 7.7 2.3 1115302300029 1.11 6.9 2.1 1115302300030 1.21 8.1 2.2 1115302300031 1.31 5.1 1.9 1115302300032 1.41 5.6 2.1 1115302300033 1.51 8.1 1.9 1115302300034 1.62 1.4 1.9 1115302300035 1.73 2.3 2.0 1115302300036 1.82 -0.4 2.0 1115302300037 1.92 -0.3 1.9 1115302300038 ENDDATA 18 0 1115302300039 ENDSUBENT 38 0 1115302399999 SUBENT 11153024 20160921 14221115302400001 BIB 5 14 1115302400002 REACTION (3-LI-7(N,INL)3-LI-7,PAR,SIG,G) 1115302400003 CORRECTION Corrected for 1115302400004 a.Attenuation of the incoming neutron beam including 1115302400005 the effects of multiple scattering of the neutrons 1115302400006 and a l/r2 factor, where r is the distance between 1115302400007 the neutron source and the scattering sample, 1115302400008 differs for different parts of the scattering 1115302400009 sample. 1115302400010 b.Attenuation of outgoing gamma rays. 1115302400011 c.Gamma rays caused by Compton scattering within the 1115302400012 sample. 1115302400013 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1115302400014 STATUS (TABLE) Text (p7) of LANL-3765 1115302400015 HISTORY (20160921C) On 1115302400016 ENDBIB 14 0 1115302400017 COMMON 1 3 1115302400018 E 1115302400019 MEV 1115302400020 0.478 1115302400021 ENDCOMMON 3 0 1115302400022 DATA 4 2 1115302400023 EN EN-RSL DATA DATA-ERR 1115302400024 MEV KEV MB MB 1115302400025 5.74 230. 230. 20. 1115302400026 7.5 170. 320. 24. 1115302400027 ENDDATA 4 0 1115302400028 ENDSUBENT 27 0 1115302499999 SUBENT 11153025 20180327 14391115302500001 BIB 5 10 1115302500002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115302500003 CORRECTION The energy spectra are intended only to show the 1115302500004 continuum neutrons. The cross sections for the 1115302500005 discrete peaks given in the energy spectra have not 1115302500006 been corrected for multiple scattering and 1115302500007 attenuation. The cross sections for discrete peaks are 1115302500008 given separately and have been corrected properly. 1115302500009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115302500010 STATUS (TABLE) page 16 of LANL-3765. 1115302500011 HISTORY (20180327C) BP 1115302500012 ENDBIB 10 0 1115302500013 COMMON 2 3 1115302500014 EN ANG 1115302500015 MEV ADEG 1115302500016 4.83 55.0 1115302500017 ENDCOMMON 3 0 1115302500018 DATA 3 25 1115302500019 E DATA DATA-ERR 1115302500020 MEV MB/SR/MEV MB/SR/MEV 1115302500021 0.425 22.6 6.0 1115302500022 0.500 27.3 5.0 1115302500023 0.600 29.2 3.0 1115302500024 0.701 28.2 1.0 1115302500025 0.805 27.3 1.0 1115302500026 0.908 28.2 2.0 1115302500027 1.008 27.3 1.0 1115302500028 1.109 29.2 2.0 1115302500029 1.212 30.1 1.0 1115302500030 1.315 28.2 1.0 1115302500031 1.416 30.1 2.0 1115302500032 1.519 26.3 1.0 1115302500033 1.624 25.4 1.0 1115302500034 1.719 25.4 1.0 1115302500035 1.822 32.9 2.0 1115302500036 1.934 64.0 1.0 1115302500037 2.029 102.6 2.0 1115302500038 2.131 73.4 2.0 1115302500039 2.240 16.0 1.0 1115302500040 2.342 6.6 1.0 1115302500041 2.431 4.7 1.0 1115302500042 2.526 5.6 1.0 1115302500043 2.647 5.6 1.0 1115302500044 2.755 5.0 1.0 1115302500045 2.846 5.0 1.0 1115302500046 ENDDATA 27 0 1115302500047 ENDSUBENT 46 0 1115302599999 SUBENT 11153026 20180327 14391115302600001 BIB 5 10 1115302600002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115302600003 CORRECTION The energy spectra are intended only to show the 1115302600004 continuum neutrons. The cross sections for the 1115302600005 discrete peaks given in the energy spectra have not 1115302600006 been corrected for multiple scattering and 1115302600007 attenuation. The cross sections for discrete peaks are 1115302600008 given separately and have been corrected properly. 1115302600009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115302600010 STATUS (TABLE) page 16 of LANL-3765. 1115302600011 HISTORY (20180327C) BP 1115302600012 ENDBIB 10 0 1115302600013 COMMON 2 3 1115302600014 EN ANG 1115302600015 MEV ADEG 1115302600016 4.83 72.5 1115302600017 ENDCOMMON 3 0 1115302600018 DATA 3 22 1115302600019 E DATA DATA-ERR 1115302600020 MEV MB/SR/MEV MB/SR/MEV 1115302600021 0.425 46.1 6.0 1115302600022 0.500 40.5 1.0 1115302600023 0.600 82.0 1.0 1115302600024 0.700 82.0 2.0 1115302600025 0.804 30.1 6.0 1115302600026 0.904 32.0 1.0 1115302600027 1.002 30.1 3.0 1115302600028 1.106 32.0 3.0 1115302600029 1.208 23.5 3.0 1115302600030 1.312 22.6 5.0 1115302600031 1.414 20.7 5.0 1115302600032 1.511 20.7 3.0 1115302600033 1.618 39.5 4.0 1115302600034 1.727 66.8 3.0 1115302600035 1.824 68.5 11.0 1115302600036 1.918 28.2 1.0 1115302600037 2.020 5.6 1.0 1115302600038 2.129 3.8 2.0 1115302600039 2.232 0.6 1.0 1115302600040 2.327 2.8 1.0 1115302600041 2.428 1.9 2.0 1115302600042 2.535 0.0 2.0 1115302600043 ENDDATA 24 0 1115302600044 ENDSUBENT 43 0 1115302699999 SUBENT 11153027 20180327 14391115302700001 BIB 5 10 1115302700002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115302700003 CORRECTION The energy spectra are intended only to show the 1115302700004 continuum neutrons. The cross sections for the 1115302700005 discrete peaks given in the energy spectra have not 1115302700006 been corrected for multiple scattering and 1115302700007 attenuation. The cross sections for discrete peaks are 1115302700008 given separately and have been corrected properly. 1115302700009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115302700010 STATUS (TABLE) page 17 of LANL-3765. 1115302700011 HISTORY (20180327C) BP 1115302700012 ENDBIB 10 0 1115302700013 COMMON 2 3 1115302700014 EN ANG 1115302700015 MEV ADEG 1115302700016 4.83 90.0 1115302700017 ENDCOMMON 3 0 1115302700018 DATA 3 20 1115302700019 E DATA DATA-ERR 1115302700020 MEV MB/SR/MEV MB/SR/MEV 1115302700021 0.425 22.2 12.8 1115302700022 0.500 15.0 6.6 1115302700023 0.600 23.1 5.0 1115302700024 0.701 25.6 4.3 1115302700025 0.805 29.2 3.6 1115302700026 0.908 22.4 3.4 1115302700027 1.008 19.9 3.2 1115302700028 1.109 21.0 3.0 1115302700029 1.212 25.6 2.9 1115302700030 1.315 22.0 2.9 1115302700031 1.416 44.6 3.3 1115302700032 1.519 77.0 3.6 1115302700033 1.624 41.1 3.1 1115302700034 1.719 10.0 2.7 1115302700035 1.822 4.3 2.1 1115302700036 1.934 4.6 2.1 1115302700037 2.029 2.9 2.4 1115302700038 2.131 3.7 2.1 1115302700039 2.240 5.2 2.3 1115302700040 2.342 4.4 2.3 1115302700041 ENDDATA 22 0 1115302700042 ENDSUBENT 41 0 1115302799999 SUBENT 11153028 20180327 14391115302800001 BIB 5 10 1115302800002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115302800003 CORRECTION The energy spectra are intended only to show the 1115302800004 continuum neutrons. The cross sections for the 1115302800005 discrete peaks given in the energy spectra have not 1115302800006 been corrected for multiple scattering and 1115302800007 attenuation. The cross sections for discrete peaks are 1115302800008 given separately and have been corrected properly. 1115302800009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115302800010 STATUS (TABLE) page 17 of LANL-3765. 1115302800011 HISTORY (20180327C) BP 1115302800012 ENDBIB 10 0 1115302800013 COMMON 2 3 1115302800014 EN ANG 1115302800015 MEV ADEG 1115302800016 4.83 110.0 1115302800017 ENDCOMMON 3 0 1115302800018 DATA 3 18 1115302800019 E DATA DATA-ERR 1115302800020 MEV MB/SR/MEV MB/SR/MEV 1115302800021 0.425 13.4 12.9 1115302800022 0.500 12.6 6.7 1115302800023 0.600 20.8 5.2 1115302800024 0.701 16.6 4.3 1115302800025 0.805 20.5 3.6 1115302800026 0.906 18.1 3.3 1115302800027 1.008 10.4 3.1 1115302800028 1.109 21.6 2.9 1115302800029 1.212 45.7 3.2 1115302800030 1.315 55.4 3.4 1115302800031 1.416 13.6 3.0 1115302800032 1.519 5.4 2.7 1115302800033 1.624 3.2 2.5 1115302800034 1.719 1.2 2.7 1115302800035 1.822 -0.2 2.2 1115302800036 1.934 4.9 2.4 1115302800037 2.029 1.8 2.8 1115302800038 2.131 5.9 2.5 1115302800039 ENDDATA 20 0 1115302800040 ENDSUBENT 39 0 1115302899999 SUBENT 11153029 20180327 14391115302900001 BIB 5 10 1115302900002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115302900003 CORRECTION The energy spectra are intended only to show the 1115302900004 continuum neutrons. The cross sections for the 1115302900005 discrete peaks given in the energy spectra have not 1115302900006 been corrected for multiple scattering and 1115302900007 attenuation. The cross sections for discrete peaks are 1115302900008 given separately and have been corrected properly. 1115302900009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115302900010 STATUS (TABLE) page 17 of LANL-3765. 1115302900011 HISTORY (20180327C) BP 1115302900012 ENDBIB 10 0 1115302900013 COMMON 2 3 1115302900014 EN ANG 1115302900015 MEV ADEG 1115302900016 4.83 135.0 1115302900017 ENDCOMMON 3 0 1115302900018 DATA 3 13 1115302900019 E DATA DATA-ERR 1115302900020 MEV MB/SR/MEV MB/SR/MEV 1115302900021 0.425 -0.9 3.0 1115302900022 0.500 9.4 13.0 1115302900023 0.600 15.1 7.0 1115302900024 0.701 12.2 6.0 1115302900025 0.809 11.3 1.0 1115302900026 0.908 14.1 10.0 1115302900027 1.008 28.2 1.0 1115302900028 1.109 33.9 4.0 1115302900029 1.212 1.9 6.0 1115302900030 1.315 0.9 1.0 1115302900031 1.416 -12.2 7.0 1115302900032 1.519 -3.8 8.0 1115302900033 1.624 -2.8 2.0 1115302900034 ENDDATA 15 0 1115302900035 ENDSUBENT 34 0 1115302999999 SUBENT 11153030 20180327 14391115303000001 BIB 5 10 1115303000002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115303000003 CORRECTION The energy spectra are intended only to show the 1115303000004 continuum neutrons. The cross sections for the 1115303000005 discrete peaks given in the energy spectra have not 1115303000006 been corrected for multiple scattering and 1115303000007 attenuation. The cross sections for discrete peaks are 1115303000008 given separately and have been corrected properly. 1115303000009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115303000010 STATUS (TABLE) page 19 of LANL-3765. 1115303000011 HISTORY (20180327C) BP 1115303000012 ENDBIB 10 0 1115303000013 COMMON 2 3 1115303000014 EN ANG 1115303000015 MEV ADEG 1115303000016 4.83 55.0 1115303000017 ENDCOMMON 3 0 1115303000018 DATA 3 14 1115303000019 E DATA DATA-ERR 1115303000020 MEV MB/SR/MEV MB/SR/MEV 1115303000021 0.42 5.1 5.3 1115303000022 0.50 9.0 2.7 1115303000023 0.60 7.1 2.1 1115303000024 0.70 11.7 1.8 1115303000025 0.80 10.1 1.6 1115303000026 0.90 6.8 1.6 1115303000027 1.00 11.9 1.4 1115303000028 1.11 9.1 1.3 1115303000029 1.21 6.5 1.3 1115303000030 1.31 4.2 1.2 1115303000031 1.41 6.4 1.2 1115303000032 1.51 4.8 1.2 1115303000033 1.62 1.8 1.2 1115303000034 1.72 3.5 1.2 1115303000035 ENDDATA 16 0 1115303000036 ENDSUBENT 35 0 1115303099999 SUBENT 11153031 20180327 14391115303100001 BIB 5 10 1115303100002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115303100003 CORRECTION The energy spectra are intended only to show the 1115303100004 continuum neutrons. The cross sections for the 1115303100005 discrete peaks given in the energy spectra have not 1115303100006 been corrected for multiple scattering and 1115303100007 attenuation. The cross sections for discrete peaks are 1115303100008 given separately and have been corrected properly. 1115303100009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115303100010 STATUS (TABLE) page 19 of LANL-3765. 1115303100011 HISTORY (20180327C) BP 1115303100012 ENDBIB 10 0 1115303100013 COMMON 2 3 1115303100014 EN ANG 1115303100015 MEV ADEG 1115303100016 4.83 72.5 1115303100017 ENDCOMMON 3 0 1115303100018 DATA 3 12 1115303100019 E DATA DATA-ERR 1115303100020 MEV MB/SR/MEV MB/SR/MEV 1115303100021 0.42 8.0 7.6 1115303100022 0.50 1.1 3.8 1115303100023 0.60 12.4 2.8 1115303100024 0.70 10.9 2.5 1115303100025 0.80 10.3 2.1 1115303100026 0.90 11.4 2.0 1115303100027 1.00 5.6 1.9 1115303100028 1.11 7.0 1.7 1115303100029 1.21 3.9 1.7 1115303100030 1.31 4.2 1.6 1115303100031 1.41 4.7 1.7 1115303100032 1.51 -0.7 1.6 1115303100033 ENDDATA 14 0 1115303100034 ENDSUBENT 33 0 1115303199999 SUBENT 11153032 20180327 14391115303200001 BIB 5 10 1115303200002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115303200003 CORRECTION The energy spectra are intended only to show the 1115303200004 continuum neutrons. The cross sections for the 1115303200005 discrete peaks given in the energy spectra have not 1115303200006 been corrected for multiple scattering and 1115303200007 attenuation. The cross sections for discrete peaks are 1115303200008 given separately and have been corrected properly. 1115303200009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115303200010 STATUS (TABLE) page 20 of LANL-3765. 1115303200011 HISTORY (20180327C) BP 1115303200012 ENDBIB 10 0 1115303200013 COMMON 2 3 1115303200014 EN ANG 1115303200015 MEV ADEG 1115303200016 4.83 90.0 1115303200017 ENDCOMMON 3 0 1115303200018 DATA 3 10 1115303200019 E DATA DATA-ERR 1115303200020 MEV MB/SR/MEV MB/SR/MEV 1115303200021 0.42 9.7 7.8 1115303200022 0.50 1.3 3.9 1115303200023 0.60 10.0 2.9 1115303200024 0.70 12.0 2.4 1115303200025 0.80 4.2 2.1 1115303200026 0.90 0.2 1.9 1115303200027 1.00 4.7 1.7 1115303200028 1.11 0.1 1.6 1115303200029 1.21 0.8 1.5 1115303200030 1.31 -1.3 1.5 1115303200031 ENDDATA 12 0 1115303200032 ENDSUBENT 31 0 1115303299999 SUBENT 11153033 20180327 14391115303300001 BIB 5 10 1115303300002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115303300003 CORRECTION The energy spectra are intended only to show the 1115303300004 continuum neutrons. The cross sections for the 1115303300005 discrete peaks given in the energy spectra have not 1115303300006 been corrected for multiple scattering and 1115303300007 attenuation. The cross sections for discrete peaks are 1115303300008 given separately and have been corrected properly. 1115303300009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115303300010 STATUS (TABLE) page 20 of LANL-3765. 1115303300011 HISTORY (20180327C) BP 1115303300012 ENDBIB 10 0 1115303300013 COMMON 2 3 1115303300014 EN ANG 1115303300015 MEV ADEG 1115303300016 4.83 110.0 1115303300017 ENDCOMMON 3 0 1115303300018 DATA 3 7 1115303300019 E DATA DATA-ERR 1115303300020 MEV MB/SR/MEV MB/SR/MEV 1115303300021 0.50 15.2 4.3 1115303300022 0.60 7.7 3.4 1115303300023 0.70 9.8 2.7 1115303300024 0.80 6.5 2.2 1115303300025 0.90 5.0 2.0 1115303300026 1.00 2.9 1.9 1115303300027 1.11 0.8 1.7 1115303300028 ENDDATA 9 0 1115303300029 ENDSUBENT 28 0 1115303399999 SUBENT 11153034 20180327 14391115303400001 BIB 5 10 1115303400002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115303400003 CORRECTION The energy spectra are intended only to show the 1115303400004 continuum neutrons. The cross sections for the 1115303400005 discrete peaks given in the energy spectra have not 1115303400006 been corrected for multiple scattering and 1115303400007 attenuation. The cross sections for discrete peaks are 1115303400008 given separately and have been corrected properly. 1115303400009 ERR-ANALYS (DATA-ERR) Standard deviation from consistency of data.1115303400010 STATUS (TABLE) page 20 of LANL-3765. 1115303400011 HISTORY (20180327C) BP 1115303400012 ENDBIB 10 0 1115303400013 COMMON 2 3 1115303400014 EN ANG 1115303400015 MEV ADEG 1115303400016 4.83 135.0 1115303400017 ENDCOMMON 3 0 1115303400018 DATA 3 5 1115303400019 E DATA DATA-ERR 1115303400020 MEV MB/SR/MEV MB/SR/MEV 1115303400021 0.50 8.6 4.0 1115303400022 0.60 12.8 3.2 1115303400023 0.70 8.4 2.7 1115303400024 0.80 4.8 2.3 1115303400025 0.90 2.0 2.1 1115303400026 ENDDATA 7 0 1115303400027 ENDSUBENT 26 0 1115303499999 SUBENT 11153035 20180327 14391115303500001 BIB 5 12 1115303500002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115303500003 CORRECTION The energy spectra are intended only to show the 1115303500004 continuum neutrons. The cross sections for the 1115303500005 discrete peaks given in the energy spectra have not 1115303500006 been corrected for multiple scattering and 1115303500007 attenuation. The cross sections for discrete peaks are 1115303500008 given separately and have been corrected properly. 1115303500009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115303500010 spectra taken with the incident neutron energies of 1115303500011 5.74 and 7.5 MeV. 1115303500012 STATUS (TABLE) page 23 of LANL-3765. 1115303500013 HISTORY (20180327C) BP 1115303500014 ENDBIB 12 0 1115303500015 COMMON 2 3 1115303500016 EN ANG 1115303500017 MEV ADEG 1115303500018 5.74 30.0 1115303500019 ENDCOMMON 3 0 1115303500020 DATA 3 61 1115303500021 E DATA ERR-S 1115303500022 MEV MB/SR/MEV MB/SR/MEV 1115303500023 0.3969 -200.9000 7.2771 1115303500024 0.4990 12.6492 3.5056 1115303500025 0.6004 26.8275 3.3007 1115303500026 0.7017 22.0596 2.8178 1115303500027 0.8038 24.9562 2.5543 1115303500028 0.9075 28.0087 2.4405 1115303500029 1.0048 25.8602 2.2385 1115303500030 1.1068 28.2677 2.2536 1115303500031 1.2114 26.4793 2.0984 1115303500032 1.3153 25.3046 2.1868 1115303500033 1.4156 25.0623 2.0506 1115303500034 1.5179 26.0273 2.0836 1115303500035 1.6204 26.9578 2.0420 1115303500036 1.7227 24.3297 2.0990 1115303500037 1.8217 24.9865 2.0908 1115303500038 1.9294 26.8394 1.9994 1115303500039 2.0315 22.3458 2.1430 1115303500040 2.1257 22.2044 1.9762 1115303500041 2.2267 19.4834 1.8669 1115303500042 2.3351 20.7879 1.7860 1115303500043 2.4313 19.4190 2.0375 1115303500044 2.5341 19.4021 1.6772 1115303500045 2.6450 14.0043 1.9856 1115303500046 2.7355 18.2272 1.9242 1115303500047 2.8330 18.4916 1.8611 1115303500048 2.9357 24.8628 1.8657 1115303500049 3.0441 31.3264 1.8477 1115303500050 3.1587 54.0570 2.1061 1115303500051 3.2487 69.0215 3.1343 1115303500052 3.3430 64.2123 2.1817 1115303500053 3.4750 18.9097 1.8307 1115303500054 3.5790 16.3223 2.1266 1115303500055 3.6511 11.1967 1.9513 1115303500056 3.7636 17.6371 1.4196 1115303500057 3.8809 17.2760 2.0261 1115303500058 3.9622 18.3400 2.0864 1115303500059 4.0897 26.1212 1.5809 1115303500060 4.2226 26.5176 2.2807 1115303500061 4.3151 34.7489 2.3794 1115303500062 4.4107 2.0107 2.4752 1115303500063 4.5093 43.7686 2.6290 1115303500064 4.6116 54.6668 2.8186 1115303500065 4.7175 60.5175 3.0150 1115303500066 4.8266 72.9538 3.2321 1115303500067 4.9396 100.2206 3.5781 1115303500068 5.0570 139.3655 4.0279 1115303500069 5.1784 2213.5619 4.9179 1115303500070 5.3042 387.3607 6.2080 1115303500071 5.4147 601.6172 7.4746 1115303500072 5.5701 611.6811 7.6803 1115303500073 5.7106 384.3442 6.5661 1115303500074 5.8564 123.6265 4.4768 1115303500075 6.0079 12.2255 2.3461 1115303500076 6.1654 1.2938 1.0290 1115303500077 6.3292 0.7264 0.6578 1115303500078 6.4995 0.4605 0.5903 1115303500079 6.6769 -0.8359 0.5453 1115303500080 6.8616 -0.2488 0.4694 1115303500081 7.0540 0.6015 0.4541 1115303500082 7.2547 0.0793 0.4720 1115303500083 7.4641 -0.1307 0.4711 1115303500084 ENDDATA 63 0 1115303500085 ENDSUBENT 84 0 1115303599999 SUBENT 11153036 20180327 14391115303600001 BIB 5 12 1115303600002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115303600003 CORRECTION The energy spectra are intended only to show the 1115303600004 continuum neutrons. The cross sections for the 1115303600005 discrete peaks given in the energy spectra have not 1115303600006 been corrected for multiple scattering and 1115303600007 attenuation. The cross sections for discrete peaks are 1115303600008 given separately and have been corrected properly. 1115303600009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115303600010 spectra taken with the incident neutron energies of 1115303600011 5.74 and 7.5 MeV. 1115303600012 STATUS (TABLE) page 23 of LANL-3765. 1115303600013 HISTORY (20180327C) BP 1115303600014 ENDBIB 12 0 1115303600015 COMMON 2 3 1115303600016 EN ANG 1115303600017 MEV ADEG 1115303600018 5.74 39.0 1115303600019 ENDCOMMON 3 0 1115303600020 DATA 3 61 1115303600021 E DATA ERR-S 1115303600022 MEV MB/SR/MEV MB/SR/MEV 1115303600023 0.3969 -6.2864 7.0448 1115303600024 0.4990 11.7443 3.3815 1115303600025 0.6004 25.4363 2.0563 1115303600026 0.7017 25.7335 2.6595 1115303600027 0.8038 25.4496 2.4098 1115303600028 0.9025 21.8608 2.2649 1115303600029 1.0048 23.2851 2.1111 1115303600030 1.1068 25.4365 2.1397 1115303600031 1.2114 20.2412 1.9296 1115303600032 1.3153 21.9485 2.1471 1115303600033 1.4156 21.9016 1.6548 1115303600034 1.5179 20.9753 1.9813 1115303600035 1.6209 19.1914 1.8463 1115303600036 1.7227 20.9520 2.0207 1115303600037 1.8217 21.4904 1.9579 1115303600038 1.9294 17.5853 1.7608 1115303600039 2.0315 13.8638 1.9148 1115303600040 2.1257 17.9494 1.7690 1115303600041 2.2267 15.9102 1.6861 1115303600042 2.3351 15.3648 1.6114 1115303600043 2.4313 11.6280 1.9271 1115303600044 2.5341 15.4031 1.5450 1115303600045 2.6430 15.4584 1.8686 1115303600046 2.7355 16.5627 1.8631 1115303600047 2.8330 24.1269 1.8182 1115303600048 2.9357 35.1407 1.9046 1115303600049 3.0441 46.2768 2.0013 1115303600050 3.1587 59.2291 2.0930 1115303600051 3.2487 52.4934 2.6018 1115303600052 3.3430 36.9661 1.7763 1115303600053 3.4750 17.2220 1.4453 1115303600054 3.5790 11.1902 1.8624 1115303600055 3.6511 8.5399 1.7006 1115303600056 3.7636 10.3122 1.2335 1115303600057 3.8809 13.1507 1.8159 1115303600058 3.9623 15.2432 1.8276 1115303600059 4.0897 19.8024 1.7259 1115303600060 4.2226 23.6810 1.9988 1115303600061 4.3151 26.0617 2.0898 1115303600062 4.4107 30.4176 2.1259 1115303600063 4.5095 14.4521 2.2149 1115303600064 4.6116 42.1376 2.3670 1115303600065 4.7173 50.0294 2.5911 1115303600066 4.8266 67.1100 2.8534 1115303600067 4.9398 94.9827 3.2435 1115303600068 5.0570 156.7055 3.7708 1115303600069 5.1784 269.4847 4.0961 1115303600070 5.3042 380.1773 5.5042 1115303600071 5.4347 396.1493 5.6458 1115303600072 5.5701 263.6562 -1.4823 1115303600073 5.7106 96.8809 3.0967 1115303600074 5.8564 9.3659 2.6173 1115303600075 6.0079 -2.0134 1.5659 1115303600076 6.1654 0.5599 0.8265 1115303600077 6.3292 0.4764 0.6720 1115303600078 6.4995 -0.8152 0.5702 1115303600079 6.6769 0.3050 0.5852 1115303600080 6.8616 0.3400 0.5657 1115303600081 7.0540 -0.0012 0.4835 1115303600082 7.2547 0.0263 0.5452 1115303600083 7.4641 -0.8253 0.9051 1115303600084 ENDDATA 63 0 1115303600085 ENDSUBENT 84 0 1115303699999 SUBENT 11153037 20180327 14391115303700001 BIB 5 12 1115303700002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115303700003 CORRECTION The energy spectra are intended only to show the 1115303700004 continuum neutrons. The cross sections for the 1115303700005 discrete peaks given in the energy spectra have not 1115303700006 been corrected for multiple scattering and 1115303700007 attenuation. The cross sections for discrete peaks are 1115303700008 given separately and have been corrected properly. 1115303700009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115303700010 spectra taken with the incident neutron energies of 1115303700011 5.74 and 7.5 MeV. 1115303700012 STATUS (TABLE) page 24 of LANL-3765. 1115303700013 HISTORY (20180327C) BP 1115303700014 ENDBIB 12 0 1115303700015 COMMON 2 3 1115303700016 EN ANG 1115303700017 MEV ADEG 1115303700018 5.74 47.0 1115303700019 ENDCOMMON 3 0 1115303700020 DATA 3 61 1115303700021 E DATA ERR-S 1115303700022 MEV MB/SR/MEV MB/SR/MEV 1115303700023 0.3969 23.2838 3.9517 1115303700024 0.4990 28.9347 3.1794 1115303700025 0.6004 31.0682 2.8467 1115303700026 0.7017 29.3605 2.3060 1115303700027 0.8038 29.6218 2.1034 1115303700028 0.9025 23.6843 2.0216 1115303700029 1.0048 25.2979 1.8705 1115303700030 1.1068 25.0806 1.8961 1115303700031 1.2114 24.2300 1.7431 1115303700032 1.3153 22.4013 1.8181 1115303700033 1.4156 23.4109 1.7108 1115303700034 1.5179 25.0467 1.7929 1115303700035 1.6209 23.9165 1.7157 1115303700036 1.7227 24.8146 1.8161 1115303700037 1.8217 20.3787 1.7117 1115303700038 1.9294 16.0296 1.5763 1115303700039 2.0315 17.6629 1.7099 1115303700040 2.1257 15.9566 1.6509 1115303700041 2.2267 16.8395 1.5284 1115303700042 2.3351 17.2921 1.4667 1115303700043 2.4313 14.0834 1.8015 1115303700044 2.5341 17.8257 1.4863 1115303700045 2.6470 17.6510 1.7486 1115303700046 2.7355 24.4596 1.7661 1115303700047 2.8330 36.6597 1.8608 1115303700048 2.9357 48.6487 1.9633 1115303700049 3.0441 59.8724 2.0374 1115303700050 3.1587 47.2777 1.7878 1115303700051 3.2487 24.7338 2.0504 1115303700052 3.3430 12.9003 1.2966 1115303700053 3.4750 10.5953 1.1443 1115303700054 3.5790 9.1452 1.5839 1115303700055 3.6511 4.4953 1.4369 1115303700056 3.7636 10.5946 1.0654 1115303700057 3.8809 11.0353 1.5012 1115303700058 3.9623 13.0772 1.5581 1115303700059 4.0897 16.2465 1.1311 1115303700060 4.2226 17.7790 1.6644 1115303700061 4.3151 21.0660 1.7126 1115303700062 4.4107 26.0665 1.8742 1115303700063 4.5095 30.5178 1.9983 1115303700064 4.6116 41.4460 2.0943 1115303700065 4.7173 51.7374 2.3311 1115303700066 4.8266 81.4768 2.6836 1115303700067 4.9398 133.5351 3.2401 1115303700068 5.0570 221.4545 3.9665 1115303700069 5.1784 280.2684 4.4135 1115303700070 5.3042 251.5801 4.2770 1115303700071 5.4347 145.4912 3.5983 1115303700072 5.5701 44.5667 2.9126 1115303700073 5.7106 4.4758 2.3348 1115303700074 5.8564 1.5287 1.6493 1115303700075 6.0079 1.9427 0.9256 1115303700076 6.1654 -0.5088 0.6068 1115303700077 6.3292 -0.4503 0.4898 1115303700078 6.4995 -0.4836 0.4569 1115303700079 6.6769 0.1939 0.4261 1115303700080 6.8616 0.5870 0.4161 1115303700081 7.0540 0.2350 0.4329 1115303700082 7.2547 1.1935 0.3918 1115303700083 7.4641 -0.3965 0.4111 1115303700084 ENDDATA 63 0 1115303700085 ENDSUBENT 84 0 1115303799999 SUBENT 11153038 20180327 14391115303800001 BIB 5 12 1115303800002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115303800003 CORRECTION The energy spectra are intended only to show the 1115303800004 continuum neutrons. The cross sections for the 1115303800005 discrete peaks given in the energy spectra have not 1115303800006 been corrected for multiple scattering and 1115303800007 attenuation. The cross sections for discrete peaks are 1115303800008 given separately and have been corrected properly. 1115303800009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115303800010 spectra taken with the incident neutron energies of 1115303800011 5.74 and 7.5 MeV. 1115303800012 STATUS (TABLE) page 24 of LANL-3765. 1115303800013 HISTORY (20180327C) BP 1115303800014 ENDBIB 12 0 1115303800015 COMMON 2 3 1115303800016 EN ANG 1115303800017 MEV ADEG 1115303800018 5.74 55.0 1115303800019 ENDCOMMON 3 0 1115303800020 DATA 3 61 1115303800021 E DATA ERR-S 1115303800022 MEV MB/SR/MEV MB/SR/MEV 1115303800023 0.3969 17.3853 57.4440 1115303800024 0.4990 20.6008 3.0420 1115303800025 0.6004 27.5124 2.6953 1115303800026 0.7017 24.6291 2.2149 1115303800027 0.8038 25.1563 2.0509 1115303800028 0.9025 23.3160 1.9264 1115303800029 1.0048 22.5078 1.8083 1115303800030 1.1068 25.4422 1.8537 1115303800031 1.2114 27.2671 1.6562 1115303800032 1.3153 24.9469 1.7835 1115303800033 1.4156 23.6357 1.6099 1115303800034 1.5179 24.6868 1.7163 1115303800035 1.6209 21.8856 1.6172 1115303800036 1.7227 23.9619 1.7050 1115303800037 1.8217 21.4858 1.5944 1115303800038 1.9294 16.4962 1.4851 1115303800039 2.0315 17.4800 1.6289 1115303800040 2.1257 12.5188 1.5047 1115303800041 2.2267 12.2651 1.3927 1115303800042 2.3351 15.1551 1.3594 1115303800043 2.4313 14.8277 1.6978 1115303800044 2.5341 19.0403 1.4653 1115303800045 2.6430 25.7120 1.7946 1115303800046 2.7355 37.9252 1.9081 1115303800047 2.8330 50.1543 2.0363 1115303800048 2.9357 32.8061 1.9579 1115303800049 3.0441 33.7318 1.5927 1115303800050 3.1587 11.5507 1.2519 1115303800051 3.2487 5.7259 1.6236 1115303800052 3.3410 5.1214 1.1251 1115303800053 3.4750 6.3024 1.0311 1115303800054 3.5790 4.6904 1.3495 1115303800055 3.6511 5.8560 1.2131 1115303800056 3.7636 9.3553 0.9555 1115303800057 3.8809 8.5450 1.3705 1115303800058 3.9623 10.7323 1.3628 1115303800059 4.0897 16.7675 1.0502 1115303800060 4.2220 15.4595 1.5449 1115303800061 4.3151 16.9514 1.6463 1115303800062 4.4107 22.4428 1.7011 1115303800063 4.5095 30.3827 1.9114 1115303800064 4.6116 41.5946 2.1050 1115303800065 4.7173 66.0963 2.3737 1115303800066 4.8266 104.4420 2.9723 1115303800067 4.9398 149.2261 3.2730 1115303800068 5.0570 172.2333 3.4265 1115303800069 5.1784 143.3495 3.1949 1115303800070 5.3042 71.1124 2.5529 1115303800071 5.4347 17.9218 2.0893 1115303800072 5.5701 2.9242 1.9193 1115303800073 5.7106 -1.9072 1.6747 1115303800074 5.8564 -1.3164 1.2056 1115303800075 6.0079 -0.0143 0.7587 1115303800076 6.1654 -0.6597 0.4832 1115303800077 6.3292 0.3071 0.4384 1115303800078 6.4995 0.4570 0.4624 1115303800079 6.6769 -0.2817 0.4033 1115303800080 6.8616 0.0809 0.4012 1115303800081 7.0540 0.6032 0.4330 1115303800082 7.2547 -0.6758 0.4050 1115303800083 7.4641 0.0723 0.3566 1115303800084 ENDDATA 63 0 1115303800085 ENDSUBENT 84 0 1115303899999 SUBENT 11153039 20180327 14391115303900001 BIB 5 12 1115303900002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115303900003 CORRECTION The energy spectra are intended only to show the 1115303900004 continuum neutrons. The cross sections for the 1115303900005 discrete peaks given in the energy spectra have not 1115303900006 been corrected for multiple scattering and 1115303900007 attenuation. The cross sections for discrete peaks are 1115303900008 given separately and have been corrected properly. 1115303900009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115303900010 spectra taken with the incident neutron energies of 1115303900011 5.74 and 7.5 MeV. 1115303900012 STATUS (TABLE) page 25 of LANL-3765. 1115303900013 HISTORY (20180327C) BP 1115303900014 ENDBIB 12 0 1115303900015 COMMON 2 3 1115303900016 EN ANG 1115303900017 MEV ADEG 1115303900018 5.74 72.5 1115303900019 ENDCOMMON 3 0 1115303900020 DATA 3 61 1115303900021 E DATA ERR-S 1115303900022 MEV MB/SR/MEV MB/SR/MEV 1115303900023 0.3969 17.8963 4.0174 1115303900024 0.4990 27.6530 3.1424 1115303900025 0.6004 27.6294 2.7092 1115303900026 0.7017 23.2912 2.2420 1115303900027 0.8038 20.4740 2.0313 1115303900028 0.9025 25.6274 1.9308 1115303900029 1.0048 23.7251 1.7569 1115303900030 1.1068 22.1317 1.7365 1115303900031 1.2114 22.8375 1.5917 1115303900032 1.3153 22.0853 1.6988 1115303900033 1.4156 18.9520 1.5257 1115303900034 1.5179 16.4756 1.5920 1115303900035 1.6209 15.4302 1.4307 1115303900036 1.7277 14.4891 1.4963 1115303900037 1.8217 14.5522 1.4640 1115303900038 1.9294 14.8792 1.3553 1115303900039 2.0315 14.0209 1.4158 1115303900040 2.1257 11.7808 1.3820 1115303900041 2.2267 13.6636 1.3462 1115303900042 2.3351 21.7394 1.4080 1115303900043 2.4213 35.0443 2.0077 1115303900044 2.5341 46.7709 1.7391 1115303900045 2.6430 48.4007 1.0571 1115303900046 2.7355 27.9012 1.6399 1115303900047 2.8330 12.7538 1.3062 1115303900048 2.9357 3.3265 1.0896 1115303900049 3.0441 4.1043 0.9834 1115303900050 3.1587 1.0910 1.3122 1115303900051 3.2487 4.4779 1.4526 1115303900052 3.3430 2.6233 0.9989 1115303900053 3.4750 3.2867 0.9172 1115303900054 3.5790 3.4266 1.1967 1115303900055 3.6511 3.1822 1.1928 1115303900056 3.7636 5.5147 0.8309 1115303900057 3.8809 6.9593 1.2751 1115303900058 3.9623 7.6838 1.2179 1115303900059 4.0897 10.9526 0.9699 1115303900060 4.2226 16.9600 1.5621 1115303900061 4.3151 26.1026 1.7486 1115303900062 4.4107 42.7063 2.0427 1115303900063 4.5095 65.3506 2.3665 1115303900064 4.6116 78.2997 2.5433 1115303900065 4.7173 74.8055 2.4504 1115303900066 4.8266 52.8595 2.1379 1115303900067 4.9398 23.5248 1.5841 1115303900068 5.0570 6.1958 1.1786 1115303900069 5.1784 0.7172 1.1658 1115303900070 5.3042 1.5363 1.2194 1115303900071 5.4347 -0.9432 1.3097 1115303900072 5.5701 -2.6111 1.2115 1115303900073 5.7106 -1.0073 0.9762 1115303900074 5.8564 -0.0016 0.7480 1115303900075 6.0079 -0.0580 0.5941 1115303900076 6.1654 -0.7700 0.4726 1115303900077 6.3292 -0.7625 0.3996 1115303900078 6.4995 -0.0719 0.4056 1115303900079 6.6769 0.1532 0.4072 1115303900080 6.8616 -0.3759 0.3749 1115303900081 7.0540 -0.4505 0.3949 1115303900082 7.2470 0.3529 0.4146 1115303900083 7.4641 -0.1018 0.4195 1115303900084 ENDDATA 63 0 1115303900085 ENDSUBENT 84 0 1115303999999 SUBENT 11153040 20180327 14391115304000001 BIB 5 12 1115304000002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115304000003 CORRECTION The energy spectra are intended only to show the 1115304000004 continuum neutrons. The cross sections for the 1115304000005 discrete peaks given in the energy spectra have not 1115304000006 been corrected for multiple scattering and 1115304000007 attenuation. The cross sections for discrete peaks are 1115304000008 given separately and have been corrected properly. 1115304000009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304000010 spectra taken with the incident neutron energies of 1115304000011 5.74 and 7.5 MeV. 1115304000012 STATUS (TABLE) page 25 of LANL-3765. 1115304000013 HISTORY (20180327C) BP 1115304000014 ENDBIB 12 0 1115304000015 COMMON 2 3 1115304000016 EN ANG 1115304000017 MEV ADEG 1115304000018 5.74 90.0 1115304000019 ENDCOMMON 3 0 1115304000020 DATA 3 61 1115304000021 E DATA ERR-S 1115304000022 MEV MB/SR/MEV MB/SR/MEV 1115304000023 0.3969 21.2074 3.7152 1115304000024 0.4990 24.5040 2.9122 1115304000025 0.6004 27.4245 2.6016 1115304000026 0.7017 21.4336 2.1508 1115304000027 0.8038 22.6412 1.9527 1115304000028 0.9025 19.1111 1.8312 1115304000029 1.0048 22.4080 1.6961 1115304000030 1.1068 18.6494 1.6218 1115304000031 1.2114 20.0251 1.4747 1115304000032 1.3153 15.1521 1.4904 1115304000033 1.4156 14.0522 1.3972 1115304000034 1.5179 12.7110 1.4663 1115304000035 1.6209 12.2315 1.2215 1115304000036 1.7227 10.7258 1.3944 1115304000037 1.8217 13.1051 1.3656 1115304000038 1.9294 13.5194 1.2529 1115304000039 2.0315 22.3717 1.4567 1115304000040 2.1257 24.6670 1.6653 1115304000041 2.2267 44.2942 1.7491 1115304000042 2.3351 32.1325 1.5821 1115304000043 2.4313 10.4511 1.4694 1115304000044 2.5341 3.6446 1.0476 1115304000045 2.6420 3.4703 1.1242 1115304000046 2.7355 2.1226 1.0192 1115304000047 2.8330 0.8824 0.9731 1115304000048 2.9357 2.4154 0.9270 1115304000049 3.0441 2.1157 0.9920 1115304000050 3.1587 2.3495 0.9924 1115304000051 3.2487 7.3595 1.4238 1115304000052 3.3430 3.0244 0.9350 1115304000053 3.4750 4.2318 0.8661 1115304000054 3.5790 9.4517 1.3876 1115304000055 3.6511 9.3187 1.4375 1115304000056 3.7636 15.7545 1.1073 1115304000057 3.8809 30.1672 1.7974 1115304000058 3.9623 45.2894 2.1083 1115304000059 4.0897 65.6622 1.6808 1115304000060 4.2226 59.1389 2.2941 1115304000061 4.3151 37.3547 1.9324 1115304000062 4.4107 15.5348 1.4372 1115304000063 4.5095 5.9001 1.1436 1115304000064 4.6116 3.2656 1.0497 1115304000065 4.7173 1.2871 0.9173 1115304000066 4.8266 0.4948 0.9688 1115304000067 4.9396 1.9929 0.8310 1115304000068 5.0570 -1.0060 0.9642 1115304000069 5.1784 1.4283 1.0053 1115304000070 5.3042 -2.0684 1.1135 1115304000071 5.4347 -1.1245 1.0444 1115304000072 5.5701 -1.4393 0.6635 1115304000073 5.7106 -0.3670 0.6720 1115304000074 5.8564 0.4676 0.4619 1115304000075 6.0079 -0.4824 0.4205 1115304000076 6.1654 -0.1123 0.4131 1115304000077 6.3292 0.2291 0.3474 1115304000078 6.4995 0.5119 0.4225 1115304000079 6.6769 -0.4761 0.3706 1115304000080 6.8616 -0.5888 0.3917 1115304000081 7.0540 0.1441 0.2855 1115304000082 7.2547 -0.1933 0.3295 1115304000083 7.4641 -0.0655 0.3574 1115304000084 ENDDATA 63 0 1115304000085 ENDSUBENT 84 0 1115304099999 SUBENT 11153041 20180327 14391115304100001 BIB 5 12 1115304100002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115304100003 CORRECTION The energy spectra are intended only to show the 1115304100004 continuum neutrons. The cross sections for the 1115304100005 discrete peaks given in the energy spectra have not 1115304100006 been corrected for multiple scattering and 1115304100007 attenuation. The cross sections for discrete peaks are 1115304100008 given separately and have been corrected properly. 1115304100009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304100010 spectra taken with the incident neutron energies of 1115304100011 5.74 and 7.5 MeV. 1115304100012 STATUS (TABLE) page 26 of LANL-3765. 1115304100013 HISTORY (20180327C) BP 1115304100014 ENDBIB 12 0 1115304100015 COMMON 2 3 1115304100016 EN ANG 1115304100017 MEV ADEG 1115304100018 5.74 110.0 1115304100019 ENDCOMMON 3 0 1115304100020 DATA 3 61 1115304100021 E DATA ERR-S 1115304100022 MEV MB/SR/MEV MB/SR/MEV 1115304100023 0.3969 19.5368 3.8476 1115304100024 0.4990 23.8615 3.1858 1115304100025 0.6004 21.3285 2.7427 1115304100026 0.7017 15.6650 2.2453 1115304100027 0.8018 20.9582 2.0988 1115304100028 0.9025 19.9575 1.9469 1115304100029 1.0048 16.0674 1.7146 1115304100030 1.1063 15.4845 1.6625 1115304100031 1.2114 14.7052 1.4607 1115304100032 1.3153 10.6669 1.5132 1115304100033 1.4156 9.9165 1.3513 1115304100034 1.5179 9.9040 1.3680 1115304100035 1.6209 11.4157 1.3576 1115304100036 1.7227 15.5744 1.4267 1115304100037 1.8217 29.3860 1.5980 1115304100038 1.9294 36.2381 1.5837 1115304100039 2.0315 21.2545 1.5288 1115304100040 2.1257 6.6265 1.2364 1115304100041 2.2267 3.5578 1.1702 1115304100042 2.3351 1.6690 1.1711 1115304100043 2.4313 0.8600 1.2792 1115304100044 2.5341 3.6015 1.0940 1115304100045 2.6420 3.9697 1.1846 1115304100046 2.7355 5.0228 1.0909 1115304100047 2.8330 5.2043 1.1479 1115304100048 2.9357 5.3199 1.1815 1115304100049 3.0441 4.0176 1.2789 1115304100050 3.1587 5.3816 1.2377 1115304100051 3.2487 5.4180 1.7180 1115304100052 3.3410 13.4147 1.2578 1115304100053 3.4750 29.0634 1.3999 1115304100054 3.5790 50.2901 2.3701 1115304100055 3.6511 62.5270 2.4823 1115304100056 3.7636 62.9664 1.7180 1115304100057 3.8809 43.0690 2.0506 1115304100058 3.9623 22.4188 1.5930 1115304100059 4.0897 5.1001 0.8412 1115304100060 4.2226 2.6081 1.1010 1115304100061 4.3151 0.6698 1.0640 1115304100062 4.4107 1.9770 1.1198 1115304100063 4.5095 0.3839 1.0208 1115304100064 4.6116 2.8232 0.9971 1115304100065 4.7173 -0.0642 0.9631 1115304100066 4.8266 -0.1265 0.9140 1115304100067 4.9398 -0.0642 0.8999 1115304100068 5.0570 0.5701 0.8819 1115304100069 5.1784 -1.3305 1.0408 1115304100070 5.3042 0.0224 1.0453 1115304100071 5.4347 0.8146 0.9410 1115304100072 5.5701 -0.2664 0.8048 1115304100073 5.7106 -0.5916 0.6060 1115304100074 5.8564 -0.9231 0.5332 1115304100075 6.0079 -0.3939 0.4842 1115304100076 6.1654 -0.1586 0.4496 1115304100077 6.3292 0.0158 0.4205 1115304100078 6.4995 -0.2087 0.4391 1115304100079 6.6769 0.1549 0.4821 1115304100080 6.8616 0.2337 0.4205 1115304100081 7.0540 0.4810 0.3691 1115304100082 7.2547 0.8459 0.3729 1115304100083 7.4641 -0.3143 0.3504 1115304100084 ENDDATA 63 0 1115304100085 ENDSUBENT 84 0 1115304199999 SUBENT 11153042 20180327 14391115304200001 BIB 5 12 1115304200002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115304200003 CORRECTION The energy spectra are intended only to show the 1115304200004 continuum neutrons. The cross sections for the 1115304200005 discrete peaks given in the energy spectra have not 1115304200006 been corrected for multiple scattering and 1115304200007 attenuation. The cross sections for discrete peaks are 1115304200008 given separately and have been corrected properly. 1115304200009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304200010 spectra taken with the incident neutron energies of 1115304200011 5.74 and 7.5 MeV. 1115304200012 STATUS (TABLE) page 26 of LANL-3765. 1115304200013 HISTORY (20180327C) BP 1115304200014 ENDBIB 12 0 1115304200015 COMMON 2 3 1115304200016 EN ANG 1115304200017 MEV ADEG 1115304200018 5.74 134.0 1115304200019 ENDCOMMON 3 0 1115304200020 DATA 3 61 1115304200021 E DATA ERR-S 1115304200022 MEV MB/SR/MEV MB/SR/MEV 1115304200023 0.3969 21.2569 3.5871 1115304200024 0.4990 26.2234 2.9769 1115304200025 0.6004 23.4147 2.5675 1115304200026 0.7017 21.7946 2.1935 1115304200027 0.8038 17.1447 1.9574 1115304200028 0.9025 12.7491 1.7609 1115304200029 1.0048 12.5714 1.5629 1115304200030 1.1068 7.0072 1.5078 1115304200031 1.2114 10.8385 1.3995 1115304200032 1.3153 7.0094 1.4699 1115304200033 1.4156 9.1134 1.3891 1115304200034 1.5179 19.2530 1.5773 1115304200035 1.6209 29.6234 1.6345 1115304200036 1.7227 16.6161 1.5590 1115304200037 1.8217 2.4217 1.3094 1115304200038 1.9294 0.5016 1.2733 1115304200039 2.0315 3.8291 1.5524 1115304200040 2.1257 2.9571 1.6806 1115304200041 2.2267 1.1537 1.9017 1115304200042 2.3351 3.2069 1.6702 1115304200043 2.4313 3.4252 1.7463 1115304200044 2.5341 2.3047 1.1619 1115304200045 2.6430 3.7849 1.2218 1115304200046 2.7355 4.8683 1.1338 1115304200047 2.8330 8.6670 1.1456 1115304200048 2.9357 11.6332 1.2027 1115304200049 3.0441 19.7624 1.3679 1115304200050 3.1587 47.4267 1.7388 1115304200051 3.2487 75.1362 2.8286 1115304200052 3.3410 73.6884 1.9495 1115304200053 3.4750 28.5588 1.2739 1115304200054 3.5790 5.0417 1.1740 1115304200055 3.6511 2.8427 1.0532 1115304200056 3.7636 1.3226 0.7166 1115304200057 3.8809 1.2541 1.0636 1115304200058 3.9623 0.1338 1.0329 1115304200059 4.0897 -0.8869 0.7615 1115304200060 4.2226 3.2206 1.1001 1115304200061 4.3151 0.1355 1.0566 1115304200062 4.4107 0.3238 0.9924 1115304200063 4.5095 1.3370 0.9408 1115304200064 4.6116 0.3068 0.9242 1115304200065 4.7173 -1.1621 0.9639 1115304200066 4.8266 0.7770 0.9136 1115304200067 4.9398 -1.2270 0.9528 1115304200068 5.0570 -2.4419 1.0755 1115304200069 5.1784 -1.1415 1.1292 1115304200070 5.3042 0.6688 0.9492 1115304200071 5.4347 0.1036 0.8054 1115304200072 5.5701 -0.1724 0.6731 1115304200073 5.7106 -0.7440 0.5750 1115304200074 5.8564 -0.0297 0.4680 1115304200075 6.0079 0.1534 0.3970 1115304200076 6.1654 -0.5532 0.4238 1115304200077 6.3292 -0.7650 0.3510 1115304200078 6.4995 -0.2549 0.3758 1115304200079 6.6769 0.3743 0.3910 1115304200080 6.8616 -0.0281 0.3814 1115304200081 7.0540 0.1841 0.3605 1115304200082 7.2547 -0.6900 0.3826 1115304200083 7.4641 0.0560 0.3702 1115304200084 ENDDATA 63 0 1115304200085 ENDSUBENT 84 0 1115304299999 SUBENT 11153043 20180327 14391115304300001 BIB 5 12 1115304300002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115304300003 CORRECTION The energy spectra are intended only to show the 1115304300004 continuum neutrons. The cross sections for the 1115304300005 discrete peaks given in the energy spectra have not 1115304300006 been corrected for multiple scattering and 1115304300007 attenuation. The cross sections for discrete peaks are 1115304300008 given separately and have been corrected properly. 1115304300009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304300010 spectra taken with the incident neutron energies of 1115304300011 5.74 and 7.5 MeV. 1115304300012 STATUS (TABLE) page 29 of LANL-3765. 1115304300013 HISTORY (20180327C) BP 1115304300014 ENDBIB 12 0 1115304300015 COMMON 2 3 1115304300016 EN ANG 1115304300017 MEV ADEG 1115304300018 5.74 30.0 1115304300019 ENDCOMMON 3 0 1115304300020 DATA 3 61 1115304300021 E DATA ERR-S 1115304300022 MEV MB/SR/MEV MB/SR/MEV 1115304300023 0.3969 -9.5463 7.6242 1115304300024 0.4990 42.5285 3.5009 1115304300025 0.6004 95.5343 3.6147 1115304300026 0.7017 99.0539 3.2178 1115304300027 0.8038 78.4479 2.8518 1115304300028 0.9025 38.2086 2.3962 1115304300029 1.0046 21.3567 2.0706 1115304300030 1.1068 24.4124 2.0910 1115304300031 1.2114 15.8305 1.8762 1115304300032 1.3153 18.2077 1.9859 1115304300033 1.4156 20.5497 1.8702 1115304300034 1.5179 17.6302 1.8712 1115304300035 1.6209 15.6524 1.8026 1115304300036 1.7227 15.2677 1.8701 1115304300037 1.8217 12.9244 1.8330 1115304300038 1.9294 12.1003 1.7173 1115304300039 2.0315 11.2782 1.8756 1115304300040 2.1257 11.3566 1.7180 1115304300041 2.2267 7.5733 1.5962 1115304300042 2.3351 8.3509 1.5177 1115304300043 2.4313 8.5381 1.7382 1115304300044 2.5341 9.7220 1.4571 1115304300045 2.6430 4.3855 1.7182 1115304300046 2.7355 8.9869 1.6710 1115304300047 2.8330 9.0118 1.6101 1115304300048 2.9357 8.7865 1.5193 1115304300049 3.0441 9.6352 1.4228 1115304300050 3.1587 9.6092 1.3972 1115304300051 3.2487 10.8972 1.9217 1115304300052 3.3430 11.0504 1.4127 1115304300053 3.4750 12.7723 1.3904 1115304300054 3.5790 14.2488 1.9712 1115304300055 3.6511 16.8576 1.9636 1115304300056 3.7660 17.0367 1.3377 1115304300057 3.8809 18.7915 1.9499 1115304300058 3.9623 21.5234 2.0356 1115304300059 4.0897 27.7277 1.5207 1115304300060 4.2226 36.5492 2.3198 1115304300061 4.3151 40.7937 2.3526 1115304300062 4.4107 44.1030 2.5134 1115304300063 4.5095 50.4019 2.5852 1115304300064 4.6116 64.9522 2.8043 1115304300065 4.7173 73.0433 3.0005 1115304300066 4.8266 96.9117 3.3040 1115304300067 4.9398 136.6291 3.7141 1115304300068 5.0570 155.1244 4.1861 1115304300069 5.1784 239.9166 4.7794 1115304300070 5.3042 397.5619 5.9852 1115304300071 5.4347 649.3107 7.3345 1115304300072 5.5701 751.0245 7.8296 1115304300073 5.7106 534.4164 6.8549 1115304300074 5.8564 224.9333 4.8037 1115304300075 6.0079 36.4992 2.4476 1115304300076 6.1654 1.5801 1.0258 1115304300077 6.3292 1.5036 0.6446 1115304300078 6.4995 0.2293 0.5444 1115304300079 6.6769 -0.8080 0.5092 1115304300080 6.8616 0.4873 0.4741 1115304300081 7.0540 0.3216 0.4130 1115304300082 7.2547 -0.3710 0.4202 1115304300083 7.4641 -0.2285 0.4360 1115304300084 ENDDATA 63 0 1115304300085 ENDSUBENT 84 0 1115304399999 SUBENT 11153044 20180327 14391115304400001 BIB 5 12 1115304400002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115304400003 CORRECTION The energy spectra are intended only to show the 1115304400004 continuum neutrons. The cross sections for the 1115304400005 discrete peaks given in the energy spectra have not 1115304400006 been corrected for multiple scattering and 1115304400007 attenuation. The cross sections for discrete peaks are 1115304400008 given separately and have been corrected properly. 1115304400009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304400010 spectra taken with the incident neutron energies of 1115304400011 5.74 and 7.5 MeV. 1115304400012 STATUS (TABLE) page 29 of LANL-3765. 1115304400013 HISTORY (20180327C) BP 1115304400014 ENDBIB 12 0 1115304400015 COMMON 2 3 1115304400016 EN ANG 1115304400017 MEV ADEG 1115304400018 5.74 39.0 1115304400019 ENDCOMMON 3 0 1115304400020 DATA 3 61 1115304400021 E DATA ERR-S 1115304400022 MEV MB/SR/MEV MB/SR/MEV 1115304400023 0.3969 -19.9901 6.4543 1115304400024 0.4990 53.3037 3.4054 1115304400025 0.6004 99.6267 3.4084 1115304400026 0.7017 85.0753 2.9383 1115304400027 0.8038 47.3436 2.4402 1115304400028 0.9025 22.4889 2.1125 1115304400029 1.0048 15.3566 1.8898 1115304400030 1.1068 17.4169 1.9116 1115304400031 1.2114 12.9449 1.7214 1115304400032 1.3153 14.3523 1.8212 1115304400033 1.4156 16.0269 1.6640 1115304400034 1.5179 14.1804 1.7699 1115304400035 1.6209 11.8378 1.6368 1115304400036 1.7227 10.2740 1.7534 1115304400037 1.8217 11.0449 1.7041 1115304400038 1.9294 11.1000 1.5837 1115304400039 2.0315 7.5087 1.6959 1115304400040 2.1257 11.4540 1.5800 1115304400041 2.2267 8.0801 1.4603 1115304400042 2.3351 7.7679 1.3947 1115304400043 2.4313 5.7227 1.6970 1115304400044 2.5341 6.0723 1.3151 1115304400045 2.6430 5.3410 1.5729 1115304400046 2.7355 4.0942 1.5439 1115304400047 2.8330 7.3807 1.4381 1115304400048 2.9357 6.5697 1.3508 1115304400049 3.0441 6.4072 1.3025 1115304400050 3.1587 7.2859 1.2595 1115304400051 3.2487 8.9217 1.7975 1115304400052 3.3430 9.5732 1.2858 1115304400053 3.4750 12.6348 1.2900 1115304400054 3.5790 9.5762 1.7113 1115304400055 3.6511 14.8843 1.7432 1115304400056 3.7636 11.2191 1.1726 1115304400057 3.8809 18.7279 1.8251 1115304400058 3.9623 20.2025 1.8236 1115304400059 4.0897 25.4127 1.3299 1115304400060 4.2226 32.9545 2.0517 1115304400061 4.3151 36.2402 2.1428 1115304400062 4.4107 41.2389 2.1838 1115304400063 4.5095 51.9253 2.3515 1115304400064 4.6116 60.1769 2.4863 1115304400065 4.7173 78.8885 2.7877 1115304400066 4.8266 105.0223 3.1034 1115304400067 4.9398 123.0944 3.3481 1115304400068 5.0570 172.4743 3.7345 1115304400069 5.1784 251.7921 4.4000 1115304400070 5.3042 374.8718 5.2600 1115304400071 5.4347 464.0567 5.7407 1115304400072 5.5701 368.9050 5.3027 1115304400073 5.7106 186.5026 4.2654 1115304400074 5.8564 46.3797 2.7993 1115304400075 6.0079 2.2721 1.5243 1115304400076 6.1654 0.9175 0.7767 1115304400077 6.3292 0.1323 0.6094 1115304400078 6.4995 -0.2148 0.5439 1115304400079 6.6769 -0.1837 0.5159 1115304400080 6.8616 0.7230 0.5343 1115304400081 7.0540 0.7662 0.4745 1115304400082 7.2547 0.5344 0.5197 1115304400083 7.4641 0.0839 0.4970 1115304400084 ENDDATA 63 0 1115304400085 ENDSUBENT 84 0 1115304499999 SUBENT 11153045 20180327 14391115304500001 BIB 5 12 1115304500002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115304500003 CORRECTION The energy spectra are intended only to show the 1115304500004 continuum neutrons. The cross sections for the 1115304500005 discrete peaks given in the energy spectra have not 1115304500006 been corrected for multiple scattering and 1115304500007 attenuation. The cross sections for discrete peaks are 1115304500008 given separately and have been corrected properly. 1115304500009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304500010 spectra taken with the incident neutron energies of 1115304500011 5.74 and 7.5 MeV. 1115304500012 STATUS (TABLE) page 30 of LANL-3765. 1115304500013 HISTORY (20180327C) BP 1115304500014 ENDBIB 12 0 1115304500015 COMMON 2 3 1115304500016 EN ANG 1115304500017 MEV ADEG 1115304500018 5.74 47.0 1115304500019 ENDCOMMON 3 0 1115304500020 DATA 3 61 1115304500021 E DATA ERR-S 1115304500022 MEV MB/SR/MEV MB/SR/MEV 1115304500023 0.3969 22.2893 3.6893 1115304500024 0.4990 76.6115 3.3460 1115304500025 0.6004 91.6256 3.1768 1115304500026 0.7017 59.0944 2.4510 1115304500027 0.8038 27.4434 1.9652 1115304500028 0.9025 17.7692 1.8452 1115304500029 1.0048 15.5615 1.6604 1115304500030 1.1068 16.5768 1.6905 1115304500031 1.2114 14.0938 1.5304 1115304500032 1.3153 13.1661 1.5955 1115304500033 1.4156 13.7537 1.4941 1115304500034 1.5179 12.6027 1.5279 1115304500035 1.6209 10.9255 1.4529 1115304500036 1.7227 11.0125 1.5191 1115304500037 1.8217 8.5143 1.4486 1115304500038 1.9294 7.1014 1.3589 1115304500039 2.0315 7.1530 1.4406 1115304500040 2.1257 6.6371 1.4070 1115304500041 2.2267 6.2352 1.2673 1115304500042 2.3351 4.5111 1.1738 1115304500043 2.4313 4.3525 1.5138 1115304500044 2.5341 5.1201 1.2163 1115304500045 2.6430 5.1452 1.4278 1115304500046 2.7355 5.7104 1.3446 1115304500047 2.8330 4.1096 1.2157 1115304500048 2.9357 5.7242 1.1870 1115304500049 3.0441 4.5550 1.0920 1115304500050 3.1587 7.6424 1.0633 1115304500051 3.2487 8.9718 1.5586 1115304500052 3.3430 6.0837 1.1016 1115304500053 3.4750 10.4558 1.0795 1115304500054 3.5790 7.6809 1.4570 1115304500055 3.6511 9.0393 1.4747 1115304500056 3.7636 12.8865 1.0495 1115304500057 3.8809 11.8938 1.4428 1115304500058 3.9623 13.2760 1.4813 1115304500059 4.0897 19.6011 1.1263 1115304500060 4.2226 22.6276 1.6783 1115304500061 4.3151 30.0940 1.7984 1115304500062 4.4107 32.9503 1.9001 1115304500063 4.5095 48.5965 2.1743 1115304500064 4.6116 63.8078 2.3120 1115304500065 4.7173 78.6141 2.5563 1115304500066 4.8266 100.8612 2.7785 1115304500067 4.9398 124.3953 3.0242 1115304500068 5.0570 180.7090 3.5251 1115304500069 5.1784 271.7117 4.1883 1115304500070 5.3042 316.1207 4.5004 1115304500071 5.4347 233.6005 4.0430 1115304500072 5.5701 100.0542 3.2178 1115304500073 5.7106 16.8993 2.3222 1115304500074 5.8564 1.2850 1.5391 1115304500075 6.0079 1.9040 0.8672 1115304500076 6.1654 -1.1122 0.5427 1115304500077 6.3292 -0.0033 0.4764 1115304500078 6.4995 0.6325 0.4789 1115304500079 6.6769 0.5274 0.4166 1115304500080 6.8616 0.6745 0.3956 1115304500081 7.0540 0.0966 0.3982 1115304500082 7.2547 0.8748 0.3527 1115304500083 7.4641 -0.0300 0.3999 1115304500084 ENDDATA 63 0 1115304500085 ENDSUBENT 84 0 1115304599999 SUBENT 11153046 20180327 14391115304600001 BIB 5 12 1115304600002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115304600003 CORRECTION The energy spectra are intended only to show the 1115304600004 continuum neutrons. The cross sections for the 1115304600005 discrete peaks given in the energy spectra have not 1115304600006 been corrected for multiple scattering and 1115304600007 attenuation. The cross sections for discrete peaks are 1115304600008 given separately and have been corrected properly. 1115304600009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304600010 spectra taken with the incident neutron energies of 1115304600011 5.74 and 7.5 MeV. 1115304600012 STATUS (TABLE) page 30 of LANL-3765. 1115304600013 HISTORY (20180327C) BP 1115304600014 ENDBIB 12 0 1115304600015 COMMON 2 3 1115304600016 EN ANG 1115304600017 MEV ADEG 1115304600018 5.74 55.0 1115304600019 ENDCOMMON 3 0 1115304600020 DATA 3 61 1115304600021 E DATA ERR-S 1115304600022 MEV MB/SR/MEV MB/SR/MEV 1115304600023 0.3969 38.2191 5.4614 1115304600024 0.4990 80.5959 3.3218 1115304600025 0.6004 75.6858 2.9637 1115304600026 0.7017 33.9934 2.1793 1115304600027 0.8038 21.8038 1.8998 1115304600028 0.9025 16.3640 1.7398 1115304600029 1.0048 11.8736 1.5860 1115304600030 1.1068 15.8032 1.6369 1115304600031 1.2114 16.3358 1.4364 1115304600032 1.3153 14.0554 1.5418 1115304600033 1.4156 13.2159 1.3838 1115304600034 1.5179 13.2822 1.4057 1115304600035 1.6209 9.2518 1.3555 1115304600036 1.7227 9.1768 1.3861 1115304600037 1.8217 11.0203 1.3511 1115304600038 1.9294 9.5034 1.2980 1115304600039 2.0315 8.8104 1.3918 1115304600040 2.1257 4.4108 1.2758 1115304600041 2.2267 5.4522 1.1926 1115304600042 2.3351 5.6309 1.1188 1115304600043 2.4313 4.0001 1.3848 1115304600044 2.5341 3.8268 1.1562 1115304600045 2.6430 4.1326 1.3099 1115304600046 2.7355 5.9574 1.2723 1115304600047 2.8330 2.6130 1.1715 1115304600048 2.9357 3.5518 1.0532 1115304600049 3.0441 6.1496 1.0114 1115304600050 3.1587 5.0012 1.0518 1115304600051 3.2487 3.5237 1.4640 1115304600052 3.3430 5.2425 1.0604 1115304600053 3.4750 8.5243 1.0175 1115304600054 3.5790 8.6608 1.3873 1115304600055 3.6511 8.4396 1.3158 1115304600056 3.7636 11.5824 0.9507 1115304600057 3.8809 12.1144 1.3908 1115304600058 3.9623 15.1853 1.4075 1115304600059 4.0897 20.5482 1.0618 1115304600060 4.2226 24.0686 1.6475 1115304600061 4.3151 32.5542 1.8540 1115304600062 4.4107 39.9323 1.9272 1115304600063 4.5095 52.9932 2.1671 1115304600064 4.6116 73.2274 2.4344 1115304600065 4.7173 85.4241 2.5111 1115304600066 4.8266 95.5964 2.6627 1115304600067 4.9398 123.6923 2.9106 1115304600068 5.0570 108.0503 3.2622 1115304600069 5.1784 180.6511 3.3790 1115304600070 5.3042 136.5575 3.0592 1115304600071 5.4347 57.0297 2.4231 1115304600072 5.5701 13.6743 1.9401 1115304600073 5.7106 0.4812 1.6003 1115304600074 5.8564 -0.4712 1.1425 1115304600075 6.0079 0.8195 0.7343 1115304600076 6.1654 0.1403 0.4855 1115304600077 6.3292 -0.4575 0.3702 1115304600078 6.4995 0.0403 0.4125 1115304600079 6.6769 0.5512 0.4207 1115304600080 6.8616 -0.1738 0.3009 1115304600081 7.0540 0.3200 0.3923 1115304600082 7.2547 -0.3535 0.3928 1115304600083 7.4641 0.5727 0.3615 1115304600084 ENDDATA 63 0 1115304600085 ENDSUBENT 84 0 1115304699999 SUBENT 11153047 20180327 14391115304700001 BIB 5 12 1115304700002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115304700003 CORRECTION The energy spectra are intended only to show the 1115304700004 continuum neutrons. The cross sections for the 1115304700005 discrete peaks given in the energy spectra have not 1115304700006 been corrected for multiple scattering and 1115304700007 attenuation. The cross sections for discrete peaks are 1115304700008 given separately and have been corrected properly. 1115304700009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304700010 spectra taken with the incident neutron energies of 1115304700011 5.74 and 7.5 MeV. 1115304700012 STATUS (TABLE) page 31 of LANL-3765. 1115304700013 HISTORY (20180327C) BP 1115304700014 ENDBIB 12 0 1115304700015 COMMON 2 3 1115304700016 EN ANG 1115304700017 MEV ADEG 1115304700018 5.74 72.5 1115304700019 ENDCOMMON 3 0 1115304700020 DATA 3 61 1115304700021 E DATA ERR-S 1115304700022 MEV MB/SR/MEV MB/SR/MEV 1115304700023 0.3969 45.9276 3.8677 1115304700024 0.4990 47.1434 3.0487 1115304700025 0.6004 18.2238 2.4051 1115304700026 0.7017 13.4808 1.9714 1115304700027 0.8038 8.8129 1.7475 1115304700028 0.9025 10.9442 1.6301 1115304700029 1.0048 14.4748 1.5296 1115304700030 1.1068 12.9426 1.5006 1115304700031 1.2114 11.9000 1.3478 1115304700032 1.3153 6.4108 1.3581 1115304700033 1.4156 9.4075 1.2862 1115304700034 1.5179 6.9088 1.3390 1115304700035 1.6209 6.0127 1.1857 1115304700036 1.7227 4.1284 1.2131 1115304700037 1.8217 3.4434 1.1805 1115304700038 1.9294 4.5913 1.0930 1115304700039 2.0315 3.5007 1.1070 1115304700040 2.1257 2.7655 1.1123 1115304700041 2.2267 3.4758 1.0606 1115304700042 2.3310 6.1152 1.0500 1115304700043 2.4313 5.0737 1.3491 1115304700044 2.5341 3.6447 1.0457 1115304700045 2.6430 3.6454 1.1834 1115304700046 2.7355 3.3020 1.0617 1115304700047 2.8330 5.4902 1.0655 1115304700048 2.9357 2.4506 0.9872 1115304700049 3.0441 4.7319 0.9272 1115304700050 3.1587 4.3381 1.0084 1115304700051 3.2497 5.9126 1.3948 1115304700052 3.3430 5.3291 0.9847 1115304700053 3.4750 6.6940 0.9268 1115304700054 3.5790 9.1977 1.2939 1115304700055 3.6511 7.4014 1.1830 1115304700056 3.7636 11.1478 0.8959 1115304700057 3.8809 15.9715 1.4328 1115304700058 3.9623 22.4790 1.5215 1115304700059 4.0897 37.8541 1.3132 1115304700060 4.2226 57.7814 2.1921 1115304700061 4.3151 59.6844 2.2066 1115304700062 4.4107 62.8831 2.2438 1115304700063 4.5095 62.2868 2.2230 1115304700064 4.6116 73.8904 2.3811 1115304700065 4.7173 85.3568 2.4725 1115304700066 4.8266 68.0834 2.2419 1115304700067 4.9398 41.8077 1.8074 1115304700068 5.0570 17.3481 1.3486 1115304700069 5.1784 5.6899 1.1977 1115304700070 5.3042 5.0480 1.2108 1115304700071 5.4347 -0.8219 1.2188 1115304700072 5.5701 -2.0378 1.1343 1115304700073 5.7106 -1.6103 0.8862 1115304700074 5.8564 -1.3932 0.6404 1115304700075 6.0079 -0.6932 0.5188 1115304700076 6.1654 -1.4152 0.3946 1115304700077 6.3292 -0.0134 0.3971 1115304700078 6.4995 0.5747 0.3997 1115304700079 6.6769 0.6148 0.3920 1115304700080 6.8616 0.4332 0.3801 1115304700081 7.0540 -0.2538 0.3647 1115304700082 7.2547 -0.1319 0.3502 1115304700083 7.4641 -0.4704 0.3610 1115304700084 ENDDATA 63 0 1115304700085 ENDSUBENT 84 0 1115304799999 SUBENT 11153048 20180327 14391115304800001 BIB 5 12 1115304800002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115304800003 CORRECTION The energy spectra are intended only to show the 1115304800004 continuum neutrons. The cross sections for the 1115304800005 discrete peaks given in the energy spectra have not 1115304800006 been corrected for multiple scattering and 1115304800007 attenuation. The cross sections for discrete peaks are 1115304800008 given separately and have been corrected properly. 1115304800009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304800010 spectra taken with the incident neutron energies of 1115304800011 5.74 and 7.5 MeV. 1115304800012 STATUS (TABLE) page 31 of LANL-3765. 1115304800013 HISTORY (20180327C) BP 1115304800014 ENDBIB 12 0 1115304800015 COMMON 2 3 1115304800016 EN ANG 1115304800017 MEV ADEG 1115304800018 5.74 90.0 1115304800019 ENDCOMMON 3 0 1115304800020 DATA 3 61 1115304800021 E DATA ERR-S 1115304800022 MEV MB/SR/MEV MB/SR/MEV 1115304800023 0.3969 25.7469 3.5871 1115304800024 0.4990 17.9202 2.7239 1115304800025 0.6004 15.9589 2.3770 1115304800026 0.7017 13.5469 1.9709 1115304800027 0.8038 11.6201 1.7429 1115304800028 0.9025 10.6056 1.6517 1115304800029 1.0048 10.5891 1.4811 1115304800030 1.1068 6.0619 1.4397 1115304800031 1.2114 7.8498 1.2471 1115304800032 1.3153 6.5218 1.2881 1115304800033 1.4156 6.6391 1.2213 1115304800034 1.5179 3.1954 1.2440 1115304800035 1.6209 2.4519 1.1083 1115304800036 1.7227 0.6471 1.1435 1115304800037 1.8217 0.8324 1.0827 1115304800038 1.9294 2.5262 0.9996 1115304800039 2.0315 3.8442 1.0576 1115304800040 2.1257 2.6593 1.0286 1115304800041 2.2267 4.9514 1.0401 1115304800042 2.3351 2.8171 1.0333 1115304800043 2.4313 5.7705 1.2942 1115304800044 2.5341 4.0087 0.9993 1115304800045 2.6430 4.5199 1.0943 1115304800046 2.7355 5.3538 1.0514 1115304800047 2.8330 5.1617 1.0320 1115304800048 2.9357 4.6970 0.9419 1115304800049 3.0441 4.1652 0.9848 1115304800050 3.1587 6.1804 1.0264 1115304800051 3.2487 9.3676 1.4199 1115304800052 3.3430 9.9428 1.0358 1115304800053 3.4750 13.3539 1.0354 1115304800054 3.5790 16.8238 1.5235 1115304800055 3.6511 23.0202 1.7034 1115304800056 3.7636 36.6473 1.3695 1115304800057 3.8809 56.9294 2.2053 1115304800058 3.9623 62.0358 2.2947 1115304800059 4.0897 70.6006 1.6711 1115304800060 4.2226 85.3817 2.5629 1115304800061 4.3151 94.5542 2.6539 1115304800062 4.4107 94.3489 2.5950 1115304800063 4.5095 68.3261 2.2219 1115304800064 4.6116 33.2394 1.6594 1115304800065 4.7173 13.9170 1.2168 1115304800066 4.8266 3.5048 1.0024 1115304800067 4.9398 2.8523 0.8634 1115304800068 5.0570 -0.1871 0.9300 1115304800069 5.1784 1.6070 0.9537 1115304800070 5.3042 -1.8692 1.0480 1115304800071 5.4347 -0.8399 0.9873 1115304800072 5.5701 0.9591 0.8793 1115304800073 5.7106 0.3207 0.6603 1115304800074 5.8564 1.0234 0.4685 1115304800075 6.0079 -0.2994 0.4190 1115304800076 6.1654 -0.3723 0.3803 1115304800077 6.3292 0.1529 0.3306 1115304800078 6.4995 0.0799 0.3822 1115304800079 6.6769 -0.0040 0.3812 1115304800080 6.8616 -0.2851 0.3889 1115304800081 7.0540 -0.3631 0.3407 1115304800082 7.2547 0.1502 0.3447 1115304800083 7.4641 -0.0036 0.3455 1115304800084 ENDDATA 63 0 1115304800085 ENDSUBENT 84 0 1115304899999 SUBENT 11153049 20180327 14391115304900001 BIB 5 12 1115304900002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115304900003 CORRECTION The energy spectra are intended only to show the 1115304900004 continuum neutrons. The cross sections for the 1115304900005 discrete peaks given in the energy spectra have not 1115304900006 been corrected for multiple scattering and 1115304900007 attenuation. The cross sections for discrete peaks are 1115304900008 given separately and have been corrected properly. 1115304900009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115304900010 spectra taken with the incident neutron energies of 1115304900011 5.74 and 7.5 MeV. 1115304900012 STATUS (TABLE) page 32 of LANL-3765. 1115304900013 HISTORY (20180327C) BP 1115304900014 ENDBIB 12 0 1115304900015 COMMON 2 3 1115304900016 EN ANG 1115304900017 MEV ADEG 1115304900018 5.74 110.0 1115304900019 ENDCOMMON 3 0 1115304900020 DATA 3 61 1115304900021 E DATA ERR-S 1115304900022 MEV MB/SR/MEV MB/SR/MEV 1115304900023 0.3969 20.0254 3.5607 1115304900024 0.4990 18.9731 2.9115 1115304900025 0.6004 10.3808 2.4418 1115304900026 0.7017 10.2027 2.0304 1115304900027 0.8038 11.6835 1.8601 1115304900028 0.9025 9.4518 1.7038 1115304900029 1.0048 6.5542 1.4903 1115304900030 1.1068 6.3971 1.4325 1115304900031 1.2114 5.6861 1.2414 1115304900032 1.3153 2.3318 1.2792 1115304900033 1.4156 3.0739 1.1506 1115304900034 1.5179 3.9638 1.1737 1115304900035 1.6209 0.4920 1.0871 1115304900036 1.7227 4.8662 1.1423 1115304900037 1.8217 2.1913 1.0632 1115304900038 1.9294 3.5912 0.9813 1115304900039 2.0315 2.8651 1.0804 1115304900040 2.1257 2.6902 1.0702 1115304900041 2.2267 2.7047 1.0720 1115304900042 2.3351 2.8512 1.1110 1115304900043 2.4313 5.0881 1.2891 1115304900044 2.5341 3.5465 1.0187 1115304900045 2.6430 7.0106 1.1773 1115304900046 2.7355 8.2578 1.0985 1115304900047 2.8330 7.3344 1.1214 1115304900048 2.9357 10.3008 1.2086 1115304900049 3.0441 10.5102 1.3137 1115304900050 3.1587 14.2469 1.3162 1115304900051 3.2487 16.9016 1.8887 1115304900052 3.3430 27.5287 1.4108 1115304900053 3.4750 48.6230 1.5979 1115304900054 3.5790 56.5281 2.3701 1115304900055 3.6511 65.1156 2.4214 1115304900056 3.7636 78.4817 1.8096 1115304900057 3.8809 114.2984 2.9736 1115304900058 3.9623 126.8733 3.0759 1115304900059 4.0897 85.4683 1.8167 1115304900060 4.2226 28.0198 1.6408 1115304900061 4.3151 10.0307 1.2523 1115304900062 4.4107 1.4958 1.0301 1115304900063 4.5095 1.8208 0.9931 1115304900064 4.6116 1.8896 0.9016 1115304900065 4.7173 0.2445 0.9037 1115304900066 4.8266 0.1799 0.8579 1115304900067 4.9398 0.6180 0.8571 1115304900068 5.0570 1.3576 0.8451 1115304900069 5.1784 -0.8065 0.9798 1115304900070 5.3042 -0.9423 0.9465 1115304900071 5.4347 -0.1297 0.8486 1115304900072 5.5701 -0.6282 0.7343 1115304900073 5.7106 -0.1034 0.5786 1115304900074 5.8564 -1.0827 0.4805 1115304900075 6.0079 0.1617 0.4706 1115304900076 6.1654 0.8150 0.4591 1115304900077 6.3292 -0.1771 0.3757 1115304900078 6.4995 -0.0562 0.4104 1115304900079 6.6769 -0.5180 0.4114 1115304900080 6.8616 -0.2607 0.3596 1115304900081 7.0540 0.9404 0.3652 1115304900082 7.2547 0.4500 0.3211 1115304900083 7.4641 0.4435 0.3614 1115304900084 ENDDATA 63 0 1115304900085 ENDSUBENT 84 0 1115304999999 SUBENT 11153050 20180327 14391115305000001 BIB 5 12 1115305000002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115305000003 CORRECTION The energy spectra are intended only to show the 1115305000004 continuum neutrons. The cross sections for the 1115305000005 discrete peaks given in the energy spectra have not 1115305000006 been corrected for multiple scattering and 1115305000007 attenuation. The cross sections for discrete peaks are 1115305000008 given separately and have been corrected properly. 1115305000009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305000010 spectra taken with the incident neutron energies of 1115305000011 5.74 and 7.5 MeV. 1115305000012 STATUS (TABLE) page 32 of LANL-3765. 1115305000013 HISTORY (20180327C) BP 1115305000014 ENDBIB 12 0 1115305000015 COMMON 2 3 1115305000016 EN ANG 1115305000017 MEV ADEG 1115305000018 5.74 134.0 1115305000019 ENDCOMMON 3 0 1115305000020 DATA 3 61 1115305000021 E DATA ERR-S 1115305000022 MEV MB/SR/MEV MB/SR/MEV 1115305000023 0.3969 4.0464 3.1848 1115305000024 0.4990 6.2912 2.5973 1115305000025 0.6004 8.0034 2.2386 1115305000026 0.7017 2.6488 1.8508 1115305000027 0.8038 4.8188 1.6917 1115305000028 0.9025 4.2715 1.5408 1115305000029 1.0048 4.0061 1.3518 1115305000030 1.1068 0.9182 1.3179 1115305000031 1.2114 0.2866 1.1572 1115305000032 1.3153 0.0637 1.2593 1115305000033 1.4156 1.2602 1.1775 1115305000034 1.5179 -0.7555 1.1654 1115305000035 1.6209 -0.3847 1.1008 1115305000036 1.7227 -0.0806 1.1782 1115305000037 1.8217 -0.0402 1.1747 1115305000038 1.9294 0.6838 1.1868 1115305000039 2.0315 1.1255 1.4020 1115305000040 2.1257 4.3272 1.5887 1115305000041 2.2267 2.2481 1.7878 1115305000042 2.3351 1.9095 1.5419 1115305000043 2.4313 4.1681 1.6446 1115305000044 2.5341 5.0418 1.1304 1115305000045 2.6430 6.5103 1.2044 1115305000046 2.7355 7.3418 1.1200 1115305000047 2.8330 10.7410 1.1252 1115305000048 2.9357 16.2294 1.2283 1115305000049 3.0441 26.3980 1.4091 1115305000050 3.1587 43.0854 1.6053 1115305000051 3.2487 45.2228 2.1971 1115305000052 3.3430 55.9044 1.6626 1115305000053 3.4750 113.9084 2.1986 1115305000054 3.5790 128.8723 3.2644 1115305000055 3.6511 91.8501 2.7556 1115305000056 3.7636 32.8569 1.2601 1115305000057 3.8809 4.0701 1.0857 1115305000058 3.9623 2.6224 1.0448 1115305000059 4.0897 0.6058 0.7410 1115305000060 4.2226 1.3131 0.9688 1115305000061 4.3151 -0.3384 0.9679 1115305000062 4.4107 1.0126 0.9460 1115305000063 4.5095 1.0458 0.8675 1115305000064 4.6116 0.4400 0.8644 1115305000065 4.7173 -2.0248 0.8662 1115305000066 4.8266 1.2076 0.8652 1115305000067 4.9398 -0.3462 0.9109 1115305000068 5.0570 -0.8607 1.0390 1115305000069 5.1784 -1.3614 1.0446 1115305000070 5.3042 0.3428 0.8753 1115305000071 5.4347 -1.2728 0.7016 1115305000072 5.5701 -1.0552 0.5888 1115305000073 5.7106 -0.8502 0.5258 1115305000074 5.8564 0.1491 0.4416 1115305000075 6.0079 0.1788 0.3680 1115305000076 6.1654 -0.3597 0.3998 1115305000077 6.3292 -0.4369 0.3399 1115305000078 6.4995 0.0916 0.3655 1115305000079 6.6769 -0.1191 0.3320 1115305000080 6.8616 0.2108 0.3651 1115305000081 7.0540 0.8804 0.3720 1115305000082 7.2547 -0.8452 0.3420 1115305000083 7.4641 -0.7528 0.2935 1115305000084 ENDDATA 63 0 1115305000085 ENDSUBENT 84 0 1115305099999 SUBENT 11153051 20180327 14391115305100001 BIB 5 12 1115305100002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115305100003 CORRECTION The energy spectra are intended only to show the 1115305100004 continuum neutrons. The cross sections for the 1115305100005 discrete peaks given in the energy spectra have not 1115305100006 been corrected for multiple scattering and 1115305100007 attenuation. The cross sections for discrete peaks are 1115305100008 given separately and have been corrected properly. 1115305100009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305100010 spectra taken with the incident neutron energies of 1115305100011 5.74 and 7.5 MeV. 1115305100012 STATUS (TABLE) page 35 of LANL-3765. 1115305100013 HISTORY (20180327C) BP 1115305100014 ENDBIB 12 0 1115305100015 COMMON 2 3 1115305100016 EN ANG 1115305100017 MEV ADEG 1115305100018 7.5 39.0 1115305100019 ENDCOMMON 3 0 1115305100020 DATA 3 63 1115305100021 E DATA ERR-S 1115305100022 MEV MB/SR/MEV MB/SR/MEV 1115305100023 0.3961 149.1517 5.5646 1115305100024 0.4981 15.8366 2.0410 1115305100025 0.5997 18.0420 1.5298 1115305100026 0.7002 16.0689 1.3220 1115305100027 0.8031 16.9865 1.1231 1115305100028 0.9084 16.8942 1.0482 1115305100029 1.0105 16.8432 1.0014 1115305100030 1.1073 17.2125 1.0297 1115305100031 1.2059 16.1853 0.9549 1115305100032 1.3105 16.6273 0.9333 1115305100033 1.4127 13.6792 0.9425 1115305100034 1.5181 14.3466 0.8624 1115305100035 1.6253 14.0348 0.8973 1115305100036 1.7216 14.5801 0.9753 1115305100037 1.8148 14.6171 0.9690 1115305100038 1.9158 12.8163 0.9207 1115305100039 2.0254 11.8914 0.8644 1115305100040 2.1290 13.1995 0.9607 1115305100041 2.2245 11.5361 0.9223 1115305100042 2.3265 12.2225 0.8930 1115305100043 2.4357 10.5711 0.8489 1115305100044 2.5325 12.5805 0.9815 1115305100045 2.6356 11.3368 0.7536 1115305100046 2.7447 11.9260 0.9027 1115305100047 2.8371 10.6789 0.8663 1115305100048 2.9342 12.5616 0.8140 1115305100049 3.0365 12.5781 0.7503 1115305100050 3.1441 12.4038 0.7037 1115305100051 3.2576 13.3925 0.6836 1115305100052 3.3774 12.6372 0.6627 1115305100053 3.4714 12.1330 0.9213 1115305100054 3.5698 13.0682 0.6190 1115305100055 3.6720 12.6106 0.8444 1115305100056 3.7791 11.2377 0.5768 1115305100057 3.8905 12.6536 0.8107 1115305100058 3.9676 13.0738 0.8171 1115305100059 4.0881 15.8592 0.5892 1115305100060 4.2135 18.3607 0.8676 1115305100061 4.3005 19.9741 0.8809 1115305100062 4.3903 22.2707 0.9157 1115305100063 4.4829 26.8193 0.9424 1115305100064 4.5785 35.5364 0.9948 1115305100065 4.6771 42.8392 1.0199 1115305100066 4.7790 46.4026 1.0296 1115305100067 4.8843 40.2455 0.9638 1115305100068 4.9930 24.8369 0.8402 1115305100069 5.1055 15.5754 0.7698 1115305100070 5.2217 12.1623 0.7127 1115305100071 5.3420 11.3089 0.6886 1115305100072 5.4665 12.2936 0.6673 1115305100073 5.5955 13.3515 0.6726 1115305100074 5.7290 16.5028 0.7042 1115305100075 5.8673 20.7361 0.7331 1115305100076 6.0108 23.3921 0.7336 1115305100077 6.1595 32.7217 0.7980 1115305100078 6.3139 50.6730 0.9296 1115305100079 6.4741 108.1926 1.2783 1115305100080 6.6405 230.9159 1.7667 1115305100081 6.8134 357.6194 2.1579 1115305100082 6.9931 284.6084 2.0283 1115305100083 7.1801 106.7485 1.5262 1115305100084 7.3746 13.6746 1.1238 1115305100085 7.5772 -3.0741 0.7579 1115305100086 ENDDATA 65 0 1115305100087 ENDSUBENT 86 0 1115305199999 SUBENT 11153052 20180327 14391115305200001 BIB 5 12 1115305200002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115305200003 CORRECTION The energy spectra are intended only to show the 1115305200004 continuum neutrons. The cross sections for the 1115305200005 discrete peaks given in the energy spectra have not 1115305200006 been corrected for multiple scattering and 1115305200007 attenuation. The cross sections for discrete peaks are 1115305200008 given separately and have been corrected properly. 1115305200009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305200010 spectra taken with the incident neutron energies of 1115305200011 5.74 and 7.5 MeV. 1115305200012 STATUS (TABLE) page 35 of LANL-3765. 1115305200013 HISTORY (20180327C) BP 1115305200014 ENDBIB 12 0 1115305200015 COMMON 2 3 1115305200016 EN ANG 1115305200017 MEV ADEG 1115305200018 7.5 55.0 1115305200019 ENDCOMMON 3 0 1115305200020 DATA 3 63 1115305200021 E DATA ERR-S 1115305200022 MEV MB/SR/MEV MB/SR/MEV 1115305200023 0.3961 -2.9933 4.6870 1115305200024 0.4981 26.8040 1.5648 1115305200025 0.5997 23.5370 1.1654 1115305200026 0.7002 23.0982 1.0164 1115305200027 0.8031 21.4867 0.8559 1115305200028 0.9084 19.6193 0.8104 1115305200029 1.0105 19.4646 0.7848 1115305200030 1.1073 17.8005 0.8171 1115305200031 1.2059 20.1542 0.7580 1115305200032 1.3105 18.1397 0.7546 1115305200033 1.4127 16.8063 0.7563 1115305200034 1.5181 18.4671 0.7065 1115305200035 1.6253 17.3493 0.7351 1115305200036 1.7216 17.3474 0.7990 1115305200037 1.8148 15.7374 0.7642 1115305200038 1.9158 16.0066 0.7187 1115305200039 2.0254 16.2417 0.6699 1115305200040 2.1290 15.4052 0.7389 1115305200041 2.2245 16.2085 0.7151 1115305200042 2.3265 14.5693 0.6734 1115305200043 2.4357 14.1412 0.6472 1115305200044 2.5325 13.8418 0.7707 1115305200045 2.6356 12.9633 0.5902 1115305200046 2.7447 12.5702 0.7105 1115305200047 2.8371 12.3946 0.6592 1115305200048 2.9342 10.6862 0.6228 1115305200049 3.0365 10.4396 0.5651 1115305200050 3.1441 11.4420 0.9644 1115305200051 3.2576 9.9606 0.5326 1115305200052 3.3774 10.5927 0.5205 1115305200053 3.4714 9.4539 0.6975 1115305200054 3.5698 9.6999 0.4842 1115305200055 3.6720 8.7101 0.6746 1115305200056 3.7791 10.4593 0.4738 1115305200057 3.8905 11.4522 0.6877 1115305200058 3.9676 14.6831 0.7115 1115305200059 4.0881 20.8581 0.5617 1115305200060 4.2135 31.3387 0.9067 1115305200061 4.3005 36.5068 0.9540 1115305200062 4.3903 42.1314 0.0644 1115305200063 4.4829 35.8554 0.9004 1115305200064 4.5785 22.9857 0.7479 1115305200065 4.6771 11.4576 0.6408 1115305200066 4.7790 7.5631 0.5620 1115305200067 4.8843 5.7646 0.5280 1115305200068 4.9930 5.3730 0.5343 1115305200069 5.1055 5.1493 0.5145 1115305200070 5.2217 4.9638 0.4298 1115305200071 5.3420 7.0357 0.4246 1115305200072 5.4665 7.9360 0.4970 1115305200073 5.5955 9.6862 0.5132 1115305200074 5.7290 12.8755 0.5647 1115305200075 5.8673 17.8178 0.6137 1115305200076 6.0108 31.8817 0.7206 1115305200077 6.1595 59.9595 0.9077 1115305200078 6.3139 103.2318 1.1191 1115305200079 6.4741 126.6639 1.2530 1115305200080 6.6405 81.2221 1.0422 1115305200081 6.8134 27.8141 0.7287 1115305200082 6.9931 7.6574 0.6198 1115305200083 7.1801 2.0170 0.5951 1115305200084 7.3746 -0.0221 0.4807 1115305200085 7.5772 0.5732 0.1285 1115305200086 ENDDATA 65 0 1115305200087 ENDSUBENT 86 0 1115305299999 SUBENT 11153053 20180327 14391115305300001 BIB 5 12 1115305300002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115305300003 CORRECTION The energy spectra are intended only to show the 1115305300004 continuum neutrons. The cross sections for the 1115305300005 discrete peaks given in the energy spectra have not 1115305300006 been corrected for multiple scattering and 1115305300007 attenuation. The cross sections for discrete peaks are 1115305300008 given separately and have been corrected properly. 1115305300009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305300010 spectra taken with the incident neutron energies of 1115305300011 5.74 and 7.5 MeV. 1115305300012 STATUS (TABLE) page 36 of LANL-3765. 1115305300013 HISTORY (20180327C) BP 1115305300014 ENDBIB 12 0 1115305300015 COMMON 2 3 1115305300016 EN ANG 1115305300017 MEV ADEG 1115305300018 7.5 72.5 1115305300019 ENDCOMMON 3 0 1115305300020 DATA 3 63 1115305300021 E DATA ERR-S 1115305300022 MEV MB/SR/MEV MB/SR/MEV 1115305300023 0.3961 35.2818 2.8782 1115305300024 0.4981 29.7219 1.5240 1115305300025 0.5997 26.4329 1.1352 1115305300026 0.7002 23.1856 0.9923 1115305300027 0.8031 21.3840 0.8154 1115305300028 0.9084 19.4553 0.7628 1115305300029 1.0105 19.5630 0.7433 1115305300030 1.1073 19.1622 0.7707 1115305300031 1.2059 17.4559 0.7124 1115305300032 1.3105 16.0577 0.6922 1115305300033 1.4127 17.3533 0.6983 1115305300034 1.5181 16.4423 0.6649 1115305300035 1.6253 17.3864 0.6908 1115305300036 1.7216 16.3989 0.7531 1115305300037 1.8148 16.0210 0.7296 1115305300038 1.9158 14.7591 0.6713 1115305300039 2.0254 14.6947 0.6130 1115305300040 2.1290 13.7793 0.6635 1115305300041 2.2245 13.3534 0.6330 1115305300042 2.3265 10.9676 0.6005 1115305300043 2.4357 10.6650 0.5732 1115305300044 2.5325 10.5278 0.6648 1115305300045 2.6356 10.3914 0.5240 1115305300046 2.7447 9.3910 0.6090 1115305300047 2.8371 8.1695 0.5663 1115305300048 2.9342 8.8608 0.5238 1115305300049 3.0365 7.7552 0.4985 1115305300050 3.1441 7.9339 0.4956 1115305300051 3.2576 8.2128 0.4794 1115305300052 3.3774 8.8983 0.4640 1115305300053 3.4714 10.6272 0.6620 1115305300054 3.5698 13.7976 0.4932 1115305300055 3.6720 18.3522 0.7530 1115305300056 3.7791 26.3226 0.5851 1115305300057 3.8905 33.3269 0.8979 1115305300058 3.9676 32.9903 0.8934 1115305300059 4.0881 21.2859 0.5504 1115305300060 4.2135 8.6497 0.6285 1115305300061 4.3005 4.9017 0.5520 1115305300062 4.3903 4.2737 0.4987 1115305300063 4.4829 2.3937 0.4801 1115305300064 4.5785 3.0453 0.4662 1115305300065 4.6771 2.9983 0.4610 1115305300066 4.7790 2.7552 0.4683 1115305300067 4.8843 3.1234 0.4601 1115305300068 4.9930 3.2696 0.4673 1115305300069 5.1055 4.2850 0.4819 1115305300070 5.2217 4.7599 0.4899 1115305300071 5.3420 8.8454 0.5288 1115305300072 5.4665 14.2380 0.5884 1115305300073 5.5955 24.0710 0.6899 1115305300074 5.7290 39.7166 0.7917 1115305300075 5.8673 47.5079 0.8335 1115305300076 6.0108 33.9589 0.7082 1115305300077 6.1595 16.3411 0.5469 1115305300078 6.3139 6.8115 0.4332 1115305300079 6.4741 2.3003 0.3826 1115305300080 6.6405 1.8044 0.3947 1115305300081 6.8134 0.6928 0.4256 1115305300082 6.9931 0.0326 0.4271 1115305300083 7.1801 -0.0722 0.3741 1115305300084 7.3746 -0.2093 0.2898 1115305300085 7.5772 0.1326 0.2185 1115305300086 ENDDATA 65 0 1115305300087 ENDSUBENT 86 0 1115305399999 SUBENT 11153054 20180327 14391115305400001 BIB 5 12 1115305400002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115305400003 CORRECTION The energy spectra are intended only to show the 1115305400004 continuum neutrons. The cross sections for the 1115305400005 discrete peaks given in the energy spectra have not 1115305400006 been corrected for multiple scattering and 1115305400007 attenuation. The cross sections for discrete peaks are 1115305400008 given separately and have been corrected properly. 1115305400009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305400010 spectra taken with the incident neutron energies of 1115305400011 5.74 and 7.5 MeV. 1115305400012 STATUS (TABLE) page 36 of LANL-3765. 1115305400013 HISTORY (20180327C) BP 1115305400014 ENDBIB 12 0 1115305400015 COMMON 2 3 1115305400016 EN ANG 1115305400017 MEV ADEG 1115305400018 7.5 90.0 1115305400019 ENDCOMMON 3 0 1115305400020 DATA 3 63 1115305400021 E DATA ERR-S 1115305400022 MEV MB/SR/MEV MB/SR/MEV 1115305400023 0.3961 47.7740 2.7464 1115305400024 0.4981 25.7869 1.4912 1115305400025 0.5997 22.6915 1.1366 1115305400026 0.7002 19.3513 0.9839 1115305400027 0.8031 18.2530 0.8142 1115305400028 0.9084 15.8466 0.7492 1115305400029 1.0105 15.0336 0.7282 1115305400030 1.1073 16.7313 0.7438 1115305400031 1.2059 15.1718 0.6791 1115305400032 1.3105 15.3988 0.6743 1115305400033 1.4127 14.0842 0.6718 1115305400034 1.5181 14.4765 0.6390 1115305400035 1.6253 13.7462 0.6708 1115305400036 1.7216 13.0279 0.7116 1115305400037 1.8148 12.4645 0.6509 1115305400038 1.9158 10.0749 0.5841 1115305400039 2.0254 10.9034 0.5351 1115305400040 2.1290 8.8243 0.5971 1115305400041 2.2245 9.6300 0.5771 1115305400042 2.3265 8.6942 0.5473 1115305400043 2.4357 8.8924 0.5206 1115305400044 2.5325 5.9994 0.5952 1115305400045 2.6356 6.0621 0.4630 1115305400046 2.7447 5.6710 0.5359 1115305400047 2.8371 6.9737 0.5007 1115305400048 2.9342 7.1023 0.4869 1115305400049 3.0365 7.1788 0.4847 1115305400050 3.1441 10.5750 0.5081 1115305400051 3.2576 17.4451 0.5642 1115305400052 3.3774 24.5345 0.6135 1115305400053 3.4714 30.7085 0.9173 1115305400054 3.5698 22.1586 0.5765 1115305400055 3.6720 10.1231 0.6463 1115305400056 3.7791 4.8864 0.4144 1115305400057 3.8905 2.4798 0.5669 1115305400058 3.9676 2.4893 0.5999 1115305400059 4.0881 1.5785 0.4197 1115305400060 4.2135 1.7094 0.5896 1115305400061 4.3005 2.3031 0.5755 1115305400062 4.3903 2.6960 0.6081 1115305400063 4.4829 2.6712 0.6119 1115305400064 4.5785 2.4421 0.6139 1115305400065 4.6771 3.4205 0.6132 1115305400066 4.7790 6.1667 0.5970 1115305400067 4.8843 10.8804 0.6022 1115305400068 4.9930 17.2698 0.6321 1115305400069 5.1055 28.7818 0.7130 1115305400070 5.2217 38.6080 0.7791 1115305400071 5.3420 40.4336 0.7835 1115305400072 5.4665 28.6297 0.6684 1115305400073 5.5955 11.9486 0.4855 1115305400074 5.7290 3.9762 0.3763 1115305400075 5.8673 2.4007 0.3581 1115305400076 6.0108 1.0347 0.3402 1115305400077 6.1595 0.5068 0.3060 1115305400078 6.3139 0.2733 0.2879 1115305400079 6.4741 -0.4081 0.3110 1115305400080 6.6405 0.3879 0.3554 1115305400081 6.8134 -0.0986 0.3707 1115305400082 6.9931 -0.1312 0.3382 1115305400083 7.1801 -0.3171 0.2565 1115305400084 7.3746 -0.0670 0.2052 1115305400085 7.5772 -0.0224 0.1656 1115305400086 ENDDATA 65 0 1115305400087 ENDSUBENT 86 0 1115305499999 SUBENT 11153055 20180327 14391115305500001 BIB 5 12 1115305500002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115305500003 CORRECTION The energy spectra are intended only to show the 1115305500004 continuum neutrons. The cross sections for the 1115305500005 discrete peaks given in the energy spectra have not 1115305500006 been corrected for multiple scattering and 1115305500007 attenuation. The cross sections for discrete peaks are 1115305500008 given separately and have been corrected properly. 1115305500009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305500010 spectra taken with the incident neutron energies of 1115305500011 5.74 and 7.5 MeV. 1115305500012 STATUS (TABLE) page 37 of LANL-3765. 1115305500013 HISTORY (20180327C) BP 1115305500014 ENDBIB 12 0 1115305500015 COMMON 2 3 1115305500016 EN ANG 1115305500017 MEV ADEG 1115305500018 7.5 110.0 1115305500019 ENDCOMMON 3 0 1115305500020 DATA 3 63 1115305500021 E DATA ERR-S 1115305500022 MEV MB/SR/MEV MB/SR/MEV 1115305500023 0.3961 30.4344 2.4421 1115305500024 0.4981 20.0127 1.4176 1115305500025 0.5997 18.6581 1.0644 1115305500026 0.7002 17.1812 0.9044 1115305500027 0.8031 15.8094 0.7668 1115305500028 0.9084 15.2227 0.7221 1115305500029 1.0105 14.5306 0.6927 1115305500030 1.1073 14.8969 0.7009 1115305500031 1.2059 14.8895 0.6410 1115305500032 1.3105 12.2942 0.6196 1115305500033 1.4127 12.0089 0.6253 1115305500034 1.5181 10.2957 0.5888 1115305500035 1.6253 9.3446 0.6112 1115305500036 1.7216 9.4377 0.6141 1115305500037 1.8148 9.2837 0.5797 1115305500038 1.9158 9.4631 0.5373 1115305500039 2.0254 9.0966 0.4928 1115305500040 2.1290 5.4437 0.5170 1115305500041 2.2245 5.8962 0.5017 1115305500042 2.3265 5.6910 0.4796 1115305500043 2.4157 5.8270 0.4620 1115305500044 2.5325 5.7040 0.5569 1115305500045 2.6356 6.1191 0.4300 1115305500046 2.7447 9.1619 0.5291 1115305500047 2.8371 14.5242 0.5702 1115305500048 2.9342 20.9345 0.6210 1115305500049 3.0365 22.0087 0.6299 1115305500050 3.1441 11.3710 0.5111 1115305500051 3.2570 4.0652 0.4175 1115305500052 3.3774 2.4840 0.4009 1115305500053 3.4714 2.8942 0.5681 1115305500054 3.5698 2.5855 0.4037 1115305500055 3.6720 2.5431 0.5697 1115305500056 3.7791 1.8906 0.3994 1115305500057 3.8905 2.1459 0.5710 1115305500058 3.9676 2.1875 0.5598 1115305500059 4.0881 3.2578 0.3618 1115305500060 4.2135 5.2354 0.5169 1115305500061 4.3005 5.7431 0.5163 1115305500062 4.3903 10.4063 0.5711 1115305500063 4.4829 19.1517 0.6763 1115305500064 4.5785 33.8581 0.8080 1115305500065 4.6771 42.7909 0.8779 1115305500066 4.7790 42.1839 0.8444 1115305500067 4.8843 25.8395 0.6805 1115305500068 4.9930 10.0060 0.4758 1115305500069 5.1055 3.1672 0.3512 1115305500070 5.2217 1.9955 0.3053 1115305500071 5.3420 1.2189 0.3000 1115305500072 5.4665 0.7777 0.3107 1115305500073 5.5955 0.2405 0.3046 1115305500074 5.7290 0.4758 0.3323 1115305500075 5.8673 0.3216 0.3223 1115305500076 6.0108 0.1350 0.2913 1115305500077 6.1595 -0.0983 0.2731 1115305500078 6.3139 0.1344 0.2667 1115305500079 6.4741 0.5955 0.2936 1115305500080 6.6405 -0.0771 0.3103 1115305500081 6.8134 -0.3681 0.2826 1115305500082 6.9931 -0.2927 0.2437 1115305500083 7.1801 0.2301 0.2085 1115305500084 7.3746 -0.2768 0.1848 1115305500085 7.5772 0.2945 0.1622 1115305500086 ENDDATA 65 0 1115305500087 ENDSUBENT 86 0 1115305599999 SUBENT 11153056 20180327 14391115305600001 BIB 5 12 1115305600002 REACTION (3-LI-6(N,X)0-NN-1,,DA/DE,,RAW) 1115305600003 CORRECTION The energy spectra are intended only to show the 1115305600004 continuum neutrons. The cross sections for the 1115305600005 discrete peaks given in the energy spectra have not 1115305600006 been corrected for multiple scattering and 1115305600007 attenuation. The cross sections for discrete peaks are 1115305600008 given separately and have been corrected properly. 1115305600009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305600010 spectra taken with the incident neutron energies of 1115305600011 5.74 and 7.5 MeV. 1115305600012 STATUS (TABLE) page 37 of LANL-3765. 1115305600013 HISTORY (20180327C) BP 1115305600014 ENDBIB 12 0 1115305600015 COMMON 2 3 1115305600016 EN ANG 1115305600017 MEV ADEG 1115305600018 7.5 135.0 1115305600019 ENDCOMMON 3 0 1115305600020 DATA 3 63 1115305600021 E DATA ERR-S 1115305600022 MEV MB/SR/MEV MB/SR/MEV 1115305600023 0.3961 22.5076 2.4134 1115305600024 0.4981 23.5228 1.4078 1115305600025 0.5997 18.1181 1.0357 1115305600026 0.7002 16.1663 0.9026 1115305600027 0.8031 14.9772 0.7725 1115305600028 0.9084 13.6865 0.7208 1115305600029 1.0105 13.4485 0.6982 1115305600030 1.1073 12.7894 0.7137 1115305600031 1.2059 11.1282 0.6555 1115305600032 1.3105 9.6106 0.6390 1115305600033 1.4127 9.4419 0.6465 1115305600034 1.5181 10.7424 0.6289 1115305600035 1.6253 9.5852 0.6600 1115305600036 1.7216 7.8531 0.6532 1115305600037 1.8148 6.2427 0.6364 1115305600038 1.9158 6.2657 0.6134 1115305600039 2.0254 6.7865 0.6431 1115305600040 2.1290 4.1907 0.8657 1115305600041 2.2245 5.1328 1.0760 1115305600042 2.3265 6.4333 0.8984 1115305600043 2.4357 10.1138 0.6940 1115305600044 2.5325 18.0632 0.7802 1115305600045 2.6356 20.0946 0.5825 1115305600046 2.7447 7.6068 0.5203 1115305600047 2.8371 3.2898 0.4404 1115305600048 2.9342 1.2111 0.4110 1115305600049 3.0365 1.8880 0.3970 1115305600050 3.1441 2.4189 0.3701 1115305600051 3.2576 1.9876 0.3496 1115305600052 3.3774 2.4510 0.3401 1115305600053 3.4714 2.2789 0.4890 1115305600054 3.5698 2.7240 0.5500 1115305600055 3.6720 2.9317 0.5199 1115305600056 3.7791 4.4933 0.4025 1115305600057 3.8905 6.4615 0.5962 1115305600058 3.9676 9.4318 0.6230 1115305600059 4.0881 20.6137 0.5628 1115305600060 4.2135 51.3022 0.9804 1115305600061 4.3005 40.5182 0.8719 1115305600062 4.3903 17.8292 0.6576 1115305600063 4.4829 6.1679 0.5320 1115305600064 4.5785 3.3228 0.4413 1115305600065 4.6771 2.0728 0.3918 1115305600066 4.7790 1.1545 0.3430 1115305600067 4.8843 0.9243 0.3268 1115305600068 4.9930 0.7545 0.2979 1115305600069 5.1055 0.2640 0.3021 1115305600070 5.2217 0.0525 0.3058 1115305600071 5.3420 0.5341 0.3267 1115305600072 5.4665 -0.0437 0.3386 1115305600073 5.5955 -0.0163 0.3503 1115305600074 5.7290 0.4741 0.2596 1115305600075 5.8673 0.0536 0.3341 1115305600076 6.0108 -0.3667 0.2991 1115305600077 6.1595 0.3109 0.2740 1115305600078 6.3139 0.1985 0.2997 1115305600079 6.4741 -0.5812 0.3535 1115305600080 6.6405 0.2583 0.3852 1115305600081 6.8134 -0.1448 0.3029 1115305600082 6.9931 -0.0712 0.2173 1115305600083 7.1801 0.1723 0.1920 1115305600084 7.3746 -0.2801 0.1772 1115305600085 7.5772 0.0045 0.1568 1115305600086 ENDDATA 65 0 1115305600087 ENDSUBENT 86 0 1115305699999 SUBENT 11153057 20180327 14391115305700001 BIB 5 12 1115305700002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115305700003 CORRECTION The energy spectra are intended only to show the 1115305700004 continuum neutrons. The cross sections for the 1115305700005 discrete peaks given in the energy spectra have not 1115305700006 been corrected for multiple scattering and 1115305700007 attenuation. The cross sections for discrete peaks are 1115305700008 given separately and have been corrected properly. 1115305700009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305700010 spectra taken with the incident neutron energies of 1115305700011 5.74 and 7.5 MeV. 1115305700012 STATUS (TABLE) page 40 of LANL-3765. 1115305700013 HISTORY (20180327C) BP 1115305700014 ENDBIB 12 0 1115305700015 COMMON 2 3 1115305700016 EN ANG 1115305700017 MEV ADEG 1115305700018 7.5 39.0 1115305700019 ENDCOMMON 3 0 1115305700020 DATA 3 63 1115305700021 E DATA ERR-S 1115305700022 MEV MB/SR/MEV MB/SR/MEV 1115305700023 0.3961 93.1072 5.2187 1115305700024 0.4981 1.4917 1.9078 1115305700025 0.5997 2.1800 1.4108 1115305700026 0.7002 2.2834 1.2148 1115305700027 0.8011 3.9451 1.0271 1115305700028 0.9084 6.3174 0.9624 1115305700029 1.0105 7.4247 0.9197 1115305700030 1.1073 8.2611 0.9463 1115305700031 1.2059 9.0117 0.8848 1115305700032 1.3105 10.4514 0.8677 1115305700033 1.4127 9.0803 0.8837 1115305700034 1.5181 9.6027 0.8059 1115305700035 1.6253 9.9741 0.8423 1115305700036 1.7216 12.4085 0.9276 1115305700037 1.8148 12.6546 0.9238 1115305700038 1.9158 14.9850 0.9003 1115305700039 2.0254 15.9593 0.8564 1115305700040 2.1290 20.6816 0.9734 1115305700041 2.2245 32.5235 1.0130 1115305700042 2.3265 50.7327 1.0722 1115305700043 2.4357 91.6036 1.0403 1115305700044 2.5325 32.0944 1.0856 1115305700045 2.6356 15.6855 0.7548 1115305700046 2.7447 7.2254 0.8358 1115305700047 2.8371 4.0058 0.7849 1115305700048 2.9342 5.8414 0.7332 1115305700049 3.0365 6.0547 0.6711 1115305700050 3.1441 6.3534 0.6290 1115305700051 3.2576 5.7163 0.5961 1115305700052 3.3774 6.0323 0.5859 1115305700053 3.4714 6.3886 0.8245 1115305700054 3.5698 6.3914 0.5428 1115305700055 3.6720 6.7360 0.7474 1115305700056 3.7791 6.1299 0.5152 1115305700057 3.8905 6.3180 0.7108 1115305700058 3.9676 6.8075 0.7201 1115305700059 4.0881 8.8820 0.5177 1115305700060 4.2135 11.1361 0.7688 1115305700061 4.3005 12.0806 0.7779 1115305700062 4.3903 12.4094 0.7978 1115305700063 4.4829 10.3510 0.7666 1115305700064 4.5785 10.3857 0.7501 1115305700065 4.6771 8.9978 0.7030 1115305700066 4.7790 9.2820 0.6909 1115305700067 4.8843 10.8121 0.6855 1115305700068 4.9930 11.4683 0.6953 1115305700069 5.1055 12.7446 0.7202 1115305700070 5.2217 12.8094 0.6962 1115305700071 5.3420 15.1312 0.7025 1115305700072 5.4665 14.7964 0.6704 1115305700073 5.5955 16.9205 0.6848 1115305700074 5.7290 19.2329 0.7070 1115305700075 5.8673 23.9804 0.7381 1115305700076 6.0108 30.0844 0.7620 1115305700077 6.1595 41.9151 0.8358 1115305700078 6.3139 67.6353 0.9000 1115305700079 6.4741 109.7988 1.2553 1115305700080 6.6405 202.5911 1.6393 1115305700081 6.8134 369.2012 2.1397 1115305700082 6.9931 404.4846 2.2663 1115305700083 7.1801 204.8347 1.7806 1115305700084 7.3746 41.2349 1.2015 1115305700085 7.5772 4.2663 0.7754 1115305700086 ENDDATA 65 0 1115305700087 ENDSUBENT 86 0 1115305799999 SUBENT 11153058 20180327 14391115305800001 BIB 5 12 1115305800002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115305800003 CORRECTION The energy spectra are intended only to show the 1115305800004 continuum neutrons. The cross sections for the 1115305800005 discrete peaks given in the energy spectra have not 1115305800006 been corrected for multiple scattering and 1115305800007 attenuation. The cross sections for discrete peaks are 1115305800008 given separately and have been corrected properly. 1115305800009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305800010 spectra taken with the incident neutron energies of 1115305800011 5.74 and 7.5 MeV. 1115305800012 STATUS (TABLE) page 40 of LANL-3765. 1115305800013 HISTORY (20180327C) BP 1115305800014 ENDBIB 12 0 1115305800015 COMMON 2 3 1115305800016 EN ANG 1115305800017 MEV ADEG 1115305800018 7.5 55.0 1115305800019 ENDCOMMON 3 0 1115305800020 DATA 3 63 1115305800021 E DATA ERR-S 1115305800022 MEV MB/SR/MEV MB/SR/MEV 1115305800023 0.3961 -12.8614 4.5118 1115305800024 0.4981 14.7110 1.4609 1115305800025 0.5997 11.7783 1.0725 1115305800026 0.7002 13.0707 0.9340 1115305800027 0.8031 13.5115 0.7897 1115305800028 0.9084 12.7370 0.7493 1115305800029 1.0105 13.1201 0.7261 1115305800030 1.1073 13.4846 0.7677 1115305800031 1.2059 14.4528 0.7030 1115305800032 1.3105 13.5310 0.7056 1115305800033 1.4127 12.7602 0.7091 1115305800034 1.5181 14.5129 0.6627 1115305800035 1.6253 15.8718 0.7060 1115305800036 1.7216 16.9493 0.7756 1115305800037 1.8148 20.1835 0.7753 1115305800038 1.9158 26.2810 0.7697 1115305800039 2.0254 41.8749 0.8150 1115305800040 2.1290 56.4329 0.9990 1115305800041 2.2245 49.0010 0.9225 1115305800042 2.3265 28.2670 0.7589 1115305800043 2.4357 13.0814 0.6227 1115305800044 2.5325 9.3480 0.7079 1115305800045 2.6356 7.4645 0.5308 1115305800046 2.7447 4.8835 0.6168 1115305800047 2.8371 6.5917 0.5845 1115305800048 2.9342 4.9793 0.5482 1115305800049 3.0365 4.6463 0.5091 1115305800050 3.1441 4.8989 0.4811 1115305800051 3.2576 4.7886 0.4641 1115305800052 3.3774 4.5673 0.4439 1115305800053 3.4714 4.8389 0.6104 1115305800054 3.5698 4.2637 0.4141 1115305800055 3.6720 3.3151 0.5774 1115305800056 3.7791 4.1509 0.3974 1115305800057 3.8905 3.7828 0.5644 1115305800058 3.9676 3.6543 0.5487 1115305800059 4.0881 5.4120 0.4194 1115305800060 4.2135 5.6547 0.6174 1115305800061 4.3005 4.2261 0.6097 1115305800062 4.3903 5.5199 0.5811 1115305800063 4.4829 4.8606 0.5636 1115305800064 4.5785 5.0839 0.5249 1115305800065 4.6771 5.1105 0.5480 1115305800066 4.7790 6.5956 0.5355 1115305800067 4.8843 7.2001 0.5332 1115305800068 4.9930 7.3684 0.5455 1115305800069 5.1055 7.4977 0.5311 1115305800070 5.2217 8.3680 0.5211 1115305800071 5.3420 10.0946 0.5125 1115305800072 5.4665 11.0659 0.5240 1115305800073 5.5955 13.8849 0.5504 1115305800074 5.7290 21.0899 0.6356 1115305800075 5.8673 31.4637 0.7210 1115305800076 6.0108 46.1421 0.5091 1115305800077 6.1595 62.3052 0.9080 1115305800078 6.3139 87.5810 1.0310 1115305800079 6.4741 134.9233 1.2723 1115305800080 6.6405 147.4934 1.3238 1115305800081 6.8134 80.1969 1.0226 1115305800082 6.9931 24.2465 0.7274 1115305800083 7.1801 6.4999 0.6136 1115305800084 7.3746 1.3849 0.4794 1115305800085 7.5772 1.4572 0.3309 1115305800086 ENDDATA 65 0 1115305800087 ENDSUBENT 86 0 1115305899999 SUBENT 11153059 20180327 14391115305900001 BIB 5 12 1115305900002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115305900003 CORRECTION The energy spectra are intended only to show the 1115305900004 continuum neutrons. The cross sections for the 1115305900005 discrete peaks given in the energy spectra have not 1115305900006 been corrected for multiple scattering and 1115305900007 attenuation. The cross sections for discrete peaks are 1115305900008 given separately and have been corrected properly. 1115305900009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115305900010 spectra taken with the incident neutron energies of 1115305900011 5.74 and 7.5 MeV. 1115305900012 STATUS (TABLE) page 41 of LANL-3765. 1115305900013 HISTORY (20180327C) BP 1115305900014 ENDBIB 12 0 1115305900015 COMMON 2 3 1115305900016 EN ANG 1115305900017 MEV ADEG 1115305900018 7.5 72.5 1115305900019 ENDCOMMON 3 0 1115305900020 DATA 3 63 1115305900021 E DATA ERR-S 1115305900022 MEV MB/SR/MEV MB/SR/MEV 1115305900023 0.3961 20.3044 2.7448 1115305900024 0.4981 11.5955 1.3919 1115305900025 0.5997 13.8296 1.0400 1115305900026 0.7002 12.8901 0.9092 1115305900027 0.8031 12.0690 0.7406 1115305900028 0.9084 12.8107 0.7019 1115305900029 1.0105 12.6064 0.6793 1115305900030 1.1073 14.0777 0.7153 1115305900031 1.2059 13.1256 0.6644 1115305900032 1.3105 13.2597 0.6534 1115305900033 1.4127 13.8943 0.6542 1115305900034 1.5181 17.0776 0.6504 1115305900035 1.6253 23.9999 0.7172 1115305900036 1.7216 34.0679 0.8561 1115305900037 1.8148 47.5095 0.9123 1115305900038 1.9158 43.5194 0.8418 1115305900039 2.0254 24.6639 0.6693 1115305900040 2.1290 9.6929 0.6079 1115305900041 2.2245 7.3530 0.5601 1115305900042 2.3265 5.1745 0.5297 1115305900043 2.4357 4.4949 0.5001 1115305900044 2.5325 4.5180 0.5774 1115305900045 2.6356 4.3833 0.4540 1115305900046 2.7447 4.5192 0.5370 1115305900047 2.8371 3.8089 0.4994 1115305900048 2.9342 4.6082 0.4579 1115305900049 3.0365 3.4927 0.4322 1115305900050 3.1441 2.5318 0.4165 1115305900051 3.2576 3.5126 0.4104 1115305900052 3.3774 3.5599 0.3881 1115305900053 3.4714 3.7196 0.5312 1115305900054 3.5698 3.4473 0.3666 1115305900055 3.6720 1.8183 0.4899 1115305900056 3.7791 3.3069 0.3534 1115305900057 3.8905 3.3725 0.5102 1115305900058 3.9676 4.0140 0.5281 1115305900059 4.0881 3.8155 0.3823 1115305900060 4.2135 4.0396 0.5481 1115305900061 4.3005 3.9972 0.5224 1115305900062 4.3903 3.7651 0.4760 1115305900063 4.4829 4.0611 0.4909 1115305900064 4.5795 4.0150 0.4673 1115305900065 4.6771 4.7151 0.4735 1115305900066 4.7790 4.2502 0.4761 1115305900067 4.8842 6.4713 0.4946 1115305900068 4.9930 6.3687 0.4965 1115305900069 5.1055 7.8326 0.5146 1115305900070 5.2217 10.9575 0.5524 1115305900071 5.3420 18.1444 0.6171 1115305900072 5.4665 29.7461 0.7202 1115305900073 5.5955 40.6858 0.8080 1115305900074 5.7290 49.4727 0.8462 1115305900075 5.8675 50.0739 0.8344 1115305900076 6.0108 49.9487 0.8055 1115305900077 6.1595 46.2919 0.7669 1115305900078 6.3139 26.4614 0.6107 1115305900079 6.4741 10.8333 0.4748 1115305900080 6.6405 4.8505 0.4211 1115305900081 6.8134 1.6991 0.4232 1115305900082 6.9931 0.8244 0.4215 1115305900083 7.1801 0.6813 0.3709 1115305900084 7.3746 -0.0602 0.2822 1115305900085 7.5772 0.2057 0.2129 1115305900086 ENDDATA 65 0 1115305900087 ENDSUBENT 86 0 1115305999999 SUBENT 11153060 20180327 14391115306000001 BIB 5 12 1115306000002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115306000003 CORRECTION The energy spectra are intended only to show the 1115306000004 continuum neutrons. The cross sections for the 1115306000005 discrete peaks given in the energy spectra have not 1115306000006 been corrected for multiple scattering and 1115306000007 attenuation. The cross sections for discrete peaks are 1115306000008 given separately and have been corrected properly. 1115306000009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115306000010 spectra taken with the incident neutron energies of 1115306000011 5.74 and 7.5 MeV. 1115306000012 STATUS (TABLE) page 41 of LANL-3765. 1115306000013 HISTORY (20180327C) BP 1115306000014 ENDBIB 12 0 1115306000015 COMMON 2 3 1115306000016 EN ANG 1115306000017 MEV ADEG 1115306000018 7.5 90.0 1115306000019 ENDCOMMON 3 0 1115306000020 DATA 3 63 1115306000021 E DATA ERR-S 1115306000022 MEV MB/SR/MEV MB/SR/MEV 1115306000023 0.3961 22.3228 2.6782 1115306000024 0.4981 12.6511 1.4209 1115306000025 0.5997 13.3840 1.0726 1115306000026 0.7002 13.1830 0.9213 1115306000027 0.8031 9.2146 0.7567 1115306000028 0.9084 11.8904 0.7015 1115306000029 1.0105 11.9225 0.6856 1115306000030 1.1073 12.4523 0.7021 1115306000031 1.2059 12.1480 0.6493 1115306000032 1.3105 14.9443 0.6546 1115306000033 1.4127 22.2876 0.7099 1115306000034 1.5181 35.2011 0.7530 1115306000035 1.6253 36.1827 0.7952 1115306000036 1.7216 21.4293 0.7517 1115306000037 1.8148 10.4973 0.6159 1115306000038 1.9158 7.1417 0.5332 1115306000039 2.0254 3.8865 0.4920 1115306000040 2.1290 3.7735 0.5246 1115306000041 2.2245 3.8486 0.5063 1115306000042 2.3265 2.7318 0.4776 1115306000043 2.4357 2.4105 0.4482 1115306000044 2.5325 3.3199 0.5342 1115306000045 2.6356 2.4563 0.4144 1115306000046 2.7447 2.9386 0.4714 1115306000047 2.8371 3.0893 0.4396 1115306000048 2.9342 2.6654 0.4319 1115306000049 3.0365 3.4571 0.4184 1115306000050 3.1441 3.6535 0.4144 1115306000051 3.2576 3.3848 0.3931 1115306000052 3.3774 3.7933 0.3944 1115306000053 3.4714 4.7140 0.5599 1115306000054 3.5698 4.4848 0.3845 1115306000055 3.6720 5.5575 0.5388 1115306000056 3.7791 3.9453 0.3859 1115306000057 3.8905 3.6836 0.5662 1115306000058 3.9676 4.5799 0.5876 1115306000059 4.0881 4.5410 0.4197 1115306000060 4.2135 3.6539 0.5716 1115306000061 4.3005 5.5820 0.5938 1115306000062 4.3903 5.8394 0.6058 1115306000063 4.4829 5.5254 0.6124 1115306000064 4.5785 6.5934 0.6305 1115306000065 4.6771 8.2835 0.6405 1115306000066 4.7790 10.4881 0.6377 1115306000067 4.8843 17.9378 0.6800 1115306000068 4.9930 28.3754 0.7410 1115306000069 5.1055 39.4575 0.7958 1115306000070 5.2217 45.9094 0.8239 1115306000071 5.3420 53.0552 0.8647 1115306000072 5.4665 60.0361 0.9020 1115306000073 5.5955 58.3442 0.9839 1115306000074 5.7290 40.0928 0.7449 1115306000075 5.8673 15.3566 0.5130 1115306000076 6.0108 4.9688 0.3711 1115306000077 6.1595 2.5207 0.3282 1115306000078 6.3139 1.1397 0.3036 1115306000079 6.4741 0.4632 0.3043 1115306000080 6.6405 0.2228 0.3448 1115306000081 6.8134 -0.0967 0.3627 1115306000082 6.9931 0.4342 0.3289 1115306000083 7.1801 -0.0983 0.2574 1115306000084 7.3746 -0.4316 0.2036 1115306000085 7.5772 0.1379 0.1755 1115306000086 ENDDATA 65 0 1115306000087 ENDSUBENT 86 0 1115306099999 SUBENT 11153061 20180327 14391115306100001 BIB 5 12 1115306100002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115306100003 CORRECTION The energy spectra are intended only to show the 1115306100004 continuum neutrons. The cross sections for the 1115306100005 discrete peaks given in the energy spectra have not 1115306100006 been corrected for multiple scattering and 1115306100007 attenuation. The cross sections for discrete peaks are 1115306100008 given separately and have been corrected properly. 1115306100009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115306100010 spectra taken with the incident neutron energies of 1115306100011 5.74 and 7.5 MeV. 1115306100012 STATUS (TABLE) page 42 of LANL-3765. 1115306100013 HISTORY (20180327C) BP 1115306100014 ENDBIB 12 0 1115306100015 COMMON 2 3 1115306100016 EN ANG 1115306100017 MEV ADEG 1115306100018 7.5 110.0 1115306100019 ENDCOMMON 3 0 1115306100020 DATA 3 62 1115306100021 E DATA ERR-S 1115306100022 MEV MB/SR/MEV MB/SR/MEV 1115306100023 0.3961 17.4756 2.2887 1115306100024 0.4981 14.3203 1.3397 1115306100025 0.5997 12.0896 0.9924 1115306100026 0.7002 11.8892 0.8433 1115306100027 0.8031 10.6265 0.7110 1115306100028 0.9084 11.6068 0.6760 1115306100029 1.0105 11.8683 0.6527 1115306100030 1.1073 12.2565 0.6593 1115306100031 1.2059 21.2745 0.6626 1115306100032 1.3105 29.6571 0.7158 1115306100033 1.4127 19.9610 0.6645 1115306100034 1.5191 8.6678 0.5572 1115306100035 1.6253 5.3735 0.5582 1115306100036 1.7216 5.9554 0.5609 1115306100037 1.8148 3.9861 0.5100 1115306100038 1.9158 3.2932 0.4596 1115306100039 2.0254 3.7237 0.4235 1115306100040 2.1290 2.7074 0.4679 1115306100041 2.2245 3.2549 0.4551 1115306100042 2.3265 2.1753 0.4235 1115306100043 2.4357 2.7703 0.4128 1115306100044 2.5325 2.6784 0.4987 1115306100045 2.6356 2.5694 0.3772 1115306100046 2.7447 2.7009 0.4280 1115306100047 2.8371 3.1198 0.4136 1115306100048 2.9342 3.3923 0.4047 1115306100049 3.0365 4.6680 0.4290 1115306100050 3.1441 5.3328 0.4263 1115306100051 3.2576 4.9014 0.4141 1115306100052 3.3774 4.0792 0.4069 1115306100053 3.4714 4.2390 0.5715 1115306100054 3.5698 4.0414 0.4065 1115306100055 3.6720 4.5937 0.5821 1115306100056 3.7791 4.7810 0.4165 1115306100057 3.8905 5.5891 0.6009 1115306100058 3.9676 4.0142 0.5672 1115306100059 4.0881 6.1646 0.3814 1115306100060 4.2135 7.2279 0.5305 1115306100061 4.3005 8.9009 0.5460 1115306100062 4.3903 13.4249 0.5940 1115306100063 4.4829 20.0122 0.6684 1115306100064 4.5785 30.8799 0.7620 1115306100065 4.6771 39.8921 0.8343 1115306100066 4.7790 47.1591 0.8661 1115306100067 4.8843 57.0944 0.9276 1115306100068 4.9930 67.2556 0.9824 1115306100069 5.1055 64.3763 0.9493 1115306100070 5.2217 41.8057 0.7658 1115306100071 5.3420 14.1203 0.4921 1115306100072 5.4665 4.6653 0.3693 1115306100073 5.5955 1.9849 0.3263 1115306100074 5.7290 1.3748 0.3360 1115306100075 6.0108 0.5252 0.2875 1115306100076 6.1595 0.5436 0.2746 1115306100077 6.3139 0.1903 0.2578 1115306100078 6.4741 0.4032 0.2795 1115306100079 6.6405 -0.2347 0.2959 1115306100080 6.8134 -0.0366 0.2777 1115306100081 6.9931 0.0104 0.2404 1115306100082 7.1801 0.1962 0.1999 1115306100083 7.3746 -0.1153 0.1815 1115306100084 7.5772 0.0964 0.1503 1115306100085 ENDDATA 64 0 1115306100086 ENDSUBENT 85 0 1115306199999 SUBENT 11153062 20180327 14391115306200001 BIB 5 12 1115306200002 REACTION (3-LI-7(N,X)0-NN-1,,DA/DE,,RAW) 1115306200003 CORRECTION The energy spectra are intended only to show the 1115306200004 continuum neutrons. The cross sections for the 1115306200005 discrete peaks given in the energy spectra have not 1115306200006 been corrected for multiple scattering and 1115306200007 attenuation. The cross sections for discrete peaks are 1115306200008 given separately and have been corrected properly. 1115306200009 ERR-ANALYS (ERR-S) Statistical errors were used for the energy 1115306200010 spectra taken with the incident neutron energies of 1115306200011 5.74 and 7.5 MeV. 1115306200012 STATUS (TABLE) page 42 of LANL-3765. 1115306200013 HISTORY (20180327C) BP 1115306200014 ENDBIB 12 0 1115306200015 COMMON 2 3 1115306200016 EN ANG 1115306200017 MEV ADEG 1115306200018 7.5 135.0 1115306200019 ENDCOMMON 3 0 1115306200020 DATA 3 63 1115306200021 E DATA ERR-S 1115306200022 MEV MB/SR/MEV MB/SR/MEV 1115306200023 0.3961 17.6419 2.3729 1115306200024 0.4981 17.5606 1.3610 1115306200025 0.5997 12.5210 0.9919 1115306200026 0.7002 10.7845 0.8581 1115306200027 0.8031 10.8183 0.7353 1115306200028 0.9084 11.8762 0.6967 1115306200029 1.0105 17.6041 0.7099 1115306200030 1.1073 20.7508 0.7520 1115306200031 1.2059 11.6220 0.6458 1115306200032 1.3105 6.3133 0.6022 1115306200033 1.4127 5.0193 0.5991 1115306200034 1.5181 5.2426 0.5755 1115306200035 1.6253 4.8531 0.6091 1115306200036 1.7216 3.9071 0.6035 1115306200037 1.8148 3.0777 0.5944 1115306200038 1.9158 2.5346 0.5676 1115306200039 2.0254 2.0740 0.5913 1115306200040 2.1290 1.3660 0.8207 1115306200041 2.2245 3.1126 1.0314 1115306200042 2.3265 2.5418 0.8480 1115306200043 2.4357 2.6119 0.6202 1115306200044 2.5325 2.2767 0.6051 1115306200045 2.6356 1.9572 0.4097 1115306200046 2.7447 3.1132 0.4519 1115306200047 2.8371 4.3981 0.4467 1115306200048 2.9342 4.1764 0.4427 1115306200049 3.0365 2.9763 0.4040 1115306200050 3.1441 3.3855 0.3770 1115306200051 3.2576 3.5083 0.3649 1115306200052 3.3774 3.9698 0.3556 1115306200053 3.4714 4.0677 0.5135 1115306200054 3.5698 3.3437 0.3557 1115306200055 3.6720 4.1988 0.5301 1115306200056 3.7791 5.0840 0.3997 1115306200057 3.8905 6.2761 0.5818 1115306200058 3.9676 8.0378 0.5905 1115306200059 4.0881 17.1369 0.4697 1115306200060 4.2135 28.7430 0.7621 1115306200061 4.3005 32.0851 0.7817 1115306200062 4.3903 33.6781 0.8075 1115306200063 4.4829 50.2849 0.9396 1115306200064 4.5785 71.2015 1.0738 1115306200065 4.6771 63.5071 1.0019 1115306200066 4.7790 31.1582 0.7230 1115306200067 4.8843 9.7570 0.4700 1115306200068 4.9930 3.5282 0.3491 1115306200069 5.1055 2.2129 0.3354 1115306200070 5.2217 1.3256 0.3245 1115306200071 5.3420 0.4667 0.3178 1115306200072 5.4665 -0.1715 0.3276 1115306200073 5.5955 0.1668 0.3441 1115306200074 5.7290 0.5601 0.3517 1115306200075 5.8673 0.3597 0.3305 1115306200076 6.0108 0.3218 0.3031 1115306200077 6.1595 0.5803 0.2723 1115306200078 6.3139 -0.1045 0.2856 1115306200079 6.4741 -0.2720 0.3475 1115306200080 6.6405 0.1007 0.3717 1115306200081 6.8134 0.1433 0.2997 1115306200082 6.9931 0.0785 0.2115 1115306200083 7.1801 0.2891 0.1918 1115306200084 7.3746 -0.0311 0.1808 1115306200085 7.5772 0.3552 0.1651 1115306200086 ENDDATA 65 0 1115306200087 ENDSUBENT 86 0 1115306299999 ENDENTRY 62 0 1115399999999