ENTRY 22049 20180125 22652204900000001 SUBENT 22049001 20180125 22652204900100001 BIB 15 90 2204900100002 REFERENCE (J,NSE,96,52,1987) 2204900100003 TITLE Li-7(n,n't)He-4 reaction cross section via tritium 2204900100004 counting. 2204900100005 AUTHOR (S.M.Qaim,R.Woelfle) 2204900100006 INSTITUTE (2GERJUL) 2204900100007 FACILITY (CYCLO,2GERJUL) Julich variable energy compact 2204900100008 cyclotron CV 28. 2204900100009 INC-SPECT EN-RSL - The energy spread is due to angle of emission2204900100010 and deuteron energy loss in gas 2204900100011 En Average neutron flux Time of 2204900100012 MeV density (n/cm2/s) x 10**7 irradiation (h) 2204900100013 7.945 3.87 +- 0.23 4.85 2204900100014 8.446 3.28 +- 0.21 10.63 2204900100015 8.858 3.45 +- 0.28 5.73 2204900100016 9.447 4.71 +- 0.46 5.27 2204900100017 10.015 2.86 +- 0.18 5.52 2204900100018 10.478 2.80 +- 0.18 3.03 2204900100019 INC-SOURCE (D-D) Deuterium gas target. 2204900100020 Deuteron energies between 5.5 and 8 MeV, beam current 2204900100021 of 4 micro-Amps. 2204900100022 Neutron energy range 7.9 to 10.5 MeV. 2204900100023 Sample irradiation time between 3 and 10 hours. 2204900100024 METHOD (ACTIV) The tritium produced in each Li sample was 2204900100025 separated in a vacuum apparatus and its activity 2204900100026 determined in an anticoincidence proportional gas 2204900100027 counter. 2204900100028 .Cross sections were determined relative to activation 2204900100029 monitor reaction cross sections. 2204900100030 DETECTOR (PROPC) Anticoincidence proportional gas counter. 2204900100031 .Activation from monitor foils were detected with a 2204900100032 gamma spectrometer. 2204900100033 RAD-DET (1-H-3,B-) Beta minus from tritium decay. 2204900100034 SAMPLE (3-LI-7,ENR=0.9999) Metallic lithium, enriched in 2204900100035 Li-7 to 99.99 +/-0.01%. Nominal dimensions- 20 milli-m2204900100036 diameter 4 milli-m thick. Typical weight- 650 milli-g 2204900100037 with a variation +/- 20 milli-g. 2204900100038 .Samples were etched with methanol and encapsulated in 2204900100039 0.25 milli-m thick aluminum container. 2204900100040 .Two monitor foils, iron and aluminum, each 100 micro-m2204900100041 thick and having the same circular size as the Li-7 2204900100042 sample, were placed on either side of each sample. 2204900100043 CORRECTION .Tritium production by fast neutrons on Li-6 may Be 2204900100044 neglected due to the high enrichment of the sample. 2204900100045 .Corrections were applied for background neutrons pro- 2204900100046 duced via the interaction of deuterons with the target2204900100047 structural materials as well as via the breakup of 2204900100048 deuterons on D-2 gas. 2204900100049 ERR-ANALYS (ERR-T) The major sources of errors and their esti- 2204900100050 mated magnitudes are given below. 2204900100051 Source of uncertainty percent 2204900100052 (ERR-1) Uncertainty in sample weight 0.1 2204900100053 (ERR-2) Uncertainty in irradiation time 0.1 2204900100054 (ERR-3) Uncertainty in irradiation geometry 2204900100055 and beam deviation 3. 2204900100056 (ERR-4,0.5,9.6) Uncertainty in correction for 2204900100057 activity induced by back-ground neutrons 0.5-9.6 2204900100058 (ERR-5) Uncertainty in scattering of neutrons 2204900100059 in the sample 3. 2204900100060 (ERR-6,3.2,8.3) error in excitation function 2204900100061 of monitor reaction 3.2-8.3 2204900100062 (ERR-7) Uncertainty in efficiency of gamma 2204900100063 detector 3. 2204900100064 (ERR-8,1.5,1.9) Uncertainty in correction for 2204900100065 coincidence losses 1.5-1.9 2204900100066 (ERR-9,,0.2) Uncertainty in correction for 2204900100067 pile-up < 0.2 2204900100068 (ERR-S) Uncertainty in statistics of gamma 2204900100069 counting 1. 2204900100070 (ERR-10) Uncertainty in decay data 1. 2204900100071 (ERR-11,,0.8) Uncertainty in tritium loss 2204900100072 through recoil < 0.8 2204900100073 (ERR-12) Uncertainty in nonquantitative 2204900100074 removal of tritium 1. 2204900100075 (ERR-13) Uncertainty in aliquot of carrier H-2 2204900100076 used in tritium counting 2. 2204900100077 (ERR-14) Uncertainty in efficiency of gas 2204900100078 counter 3. 2204900100079 (ERR-15) Uncertainty in plateau used for 2204900100080 tritium counting 2. 2204900100081 (ERR-16,0.5,1.0) Uncertainty in statistics 2204900100082 of tritium counting 0.5-1.0 2204900100083 Total error: 8.1-12.6 2204900100084 DECAY-DATA (1-H-3,12.3YR) 2204900100085 HISTORY (19871014C) N.O. 2204900100086 (20170811A) SD:Updated to new date formats,lower case. 2204900100087 Meaningless zeros were deleted from the data. Author's 2204900100088 name corrected (Woelfe -> Woelfle). Small corrections 2204900100089 in all Subents. (DATA-ERR -> ERR-T). ERR-ANALYS update.2204900100090 INC-SPECT, COMMON added. 2204900100091 (20180125A) On. Major revision in 003. 2204900100092 ENDBIB 90 0 2204900100093 COMMON 11 6 2204900100094 ERR-1 ERR-2 ERR-3 ERR-5 ERR-7 ERR-10 2204900100095 ERR-12 ERR-13 ERR-14 ERR-15 ERR-S 2204900100096 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2204900100097 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2204900100098 0.1 0.1 3. 3. 3. 1. 2204900100099 1. 2. 3. 2. 1. 2204900100100 ENDCOMMON 6 0 2204900100101 ENDSUBENT 100 0 2204900199999 SUBENT 22049002 20170811 22652204900200001 BIB 3 5 2204900200002 REACTION ((3-LI-7(N,X)1-H-3,,SIG)/ 2204900200003 (13-AL-27(N,A)11-NA-24,,SIG)) 2204900200004 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,96(1987)52 2204900200005 HISTORY (20170811A) SD: MONITOR was deleted. SF3=N+T -> X, 2204900200006 SF4=He-4 -> H-3 in REACTION code. 2204900200007 ENDBIB 5 0 2204900200008 NOCOMMON 0 0 2204900200009 DATA 4 6 2204900200010 EN EN-RSL DATA ERR-T 2204900200011 MEV MEV NO-DIM NO-DIM 2204900200012 7.945 0.315 9.154 0.651 2204900200013 8.446 0.316 6.387 0.452 2204900200014 8.858 0.348 5.291 0.380 2204900200015 9.447 0.352 4.994 0.369 2204900200016 10.015 0.385 4.438 0.410 2204900200017 10.478 0.411 4.004 0.473 2204900200018 ENDDATA 8 0 2204900200019 ENDSUBENT 18 0 2204900299999 SUBENT 22049003 20180125 22652204900300001 BIB 3 6 2204900300002 REACTION ((3-LI-7(N,X)1-H-3,,SIG)/ 2204900300003 (26-FE-54(N,P)25-MN-54,,SIG)) 2204900300004 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,96(1987)52 2204900300005 HISTORY (20170811A) SD: MONITOR was deleted. SF3=N+T -> X, 2204900300006 SF4=He-4 -> H-3 in REACTION code. 2204900300007 (20180125A) On. MONIT-ERR=21.0 mb deleted. 2204900300008 ENDBIB 6 0 2204900300009 NOCOMMON 0 0 2204900300010 DATA 4 4 2204900300011 EN EN-RSL DATA ERR-T 2204900300012 MEV MEV NO-DIM NO-DIM 2204900300013 7.945 0.315 0.8274 0.0607 2204900300014 8.446 0.316 0.7517 0.0567 2204900300015 8.858 0.348 0.6833 0.0591 2204900300016 9.447 0.352 0.6770 0.0722 2204900300017 ENDDATA 6 0 2204900300018 ENDSUBENT 17 0 2204900399999 SUBENT 22049004 20170811 22652204900400001 BIB 3 5 2204900400002 REACTION ((3-LI-7(N,X)1-H-3,,SIG)/ 2204900400003 (26-FE-56(N,P)25-MN-56,,SIG)) 2204900400004 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,96(1987)52 2204900400005 HISTORY (20170811A) SD: MONITOR was deleted. SF3=N+T -> X 2204900400006 SF4=He-4 -> H-3 in REACTION code. 2204900400007 ENDBIB 5 0 2204900400008 NOCOMMON 0 0 2204900400009 DATA 4 2 2204900400010 EN EN-RSL DATA ERR-T 2204900400011 MEV MEV NO-DIM NO-DIM 2204900400012 10.015 0.385 5.493 0.513 2204900400013 10.478 0.411 4.634 0.555 2204900400014 ENDDATA 4 0 2204900400015 ENDSUBENT 14 0 2204900499999 SUBENT 22049005 20170811 22652204900500001 BIB 6 14 2204900500002 REACTION (3-LI-7(N,X)1-H-3,,SIG) Calculated as the mean value 2204900500003 for the two monitor reactions. 2204900500004 MONITOR ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG) 2204900500005 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG) cross sections 2204900500006 taken from NDF/B-V. 2204900500007 MONIT-REF ((MONIT1),,3,ENDF/B-V,,1979) 2204900500008 ((MONIT2),S.Tagesen+,B,PH-DAT,13-1,1981) 2204900500009 DECAY-MON ((MONIT1)11-NA-24,15.0HR,DG,1368.,1.) Monit1 2204900500010 ((MONIT2)25-MN-54,312.2D,DG,835.,1.) monit2 2204900500011 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,96(1987)52 2204900500012 (DEP,22049002) 2204900500013 (DEP,22049003) 2204900500014 HISTORY (20170811A) SD: BIB update. SF3=N+T -> X, 2204900500015 SF4=He-4 -> H-3 in REACTION code. 2204900500016 ENDBIB 14 0 2204900500017 COMMON 2 3 2204900500018 EN EN-RSL 2204900500019 MEV MEV 2204900500020 7.945 0.315 2204900500021 ENDCOMMON 3 0 2204900500022 DATA 6 1 2204900500023 DATA ERR-T MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 2204900500024 MB MB MB MB MB MB 2204900500025 372. 30. 37.83 1.21 476.2 21.0 2204900500026 ENDDATA 3 0 2204900500027 ENDSUBENT 26 0 2204900599999 SUBENT 22049006 20170811 22652204900600001 BIB 6 14 2204900600002 REACTION (3-LI-7(N,X)1-H-3,,SIG) Calculated as the 2204900600003 mean value for the two monitor reactions. 2204900600004 MONITOR ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG) 2204900600005 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG) cross sections 2204900600006 taken from NDF/B-V. 2204900600007 MONIT-REF ((MONIT1),,3,ENDF/B-V,,1979) 2204900600008 ((MONIT2),S.Tagesen+,B,PH-DAT,13-1,1981) 2204900600009 DECAY-MON ((MONIT1)11-NA-24,15.0HR,DG,1368.,1.) 2204900600010 ((MONIT2)25-MN-54,312.2D,DG,835.,1.) 2204900600011 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,96(1987)52 2204900600012 (DEP,22049002) 2204900600013 (DEP,22049003) 2204900600014 HISTORY (20170811A) SD: BIB update. SF3=N+T -> X, 2204900600015 SF4=He-4 -> H-3 in REACTION code. 2204900600016 ENDBIB 14 0 2204900600017 COMMON 2 3 2204900600018 EN EN-RSL 2204900600019 MEV MEV 2204900600020 8.446 0.316 2204900600021 ENDCOMMON 3 0 2204900600022 DATA 6 1 2204900600023 DATA ERR-T MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 2204900600024 MB MB MB MB MB MB 2204900600025 343. 30. 51.07 2.35 477.9 21.0 2204900600026 ENDDATA 3 0 2204900600027 ENDSUBENT 26 0 2204900699999 SUBENT 22049007 20170811 22652204900700001 BIB 6 14 2204900700002 REACTION (3-LI-7(N,X)1-H-3,,SIG) Calculated as the mean value 2204900700003 for the two monitor reactions. 2204900700004 MONITOR ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG) 2204900700005 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG) cross sections 2204900700006 taken from ENDF/B-V. 2204900700007 MONIT-REF ((MONIT1),,3,ENDF/B-V,,1979) 2204900700008 ((MONIT2),S.Tagesen+,B,PH-DAT,13-1,1981) 2204900700009 DECAY-MON ((MONIT1)11-NA-24,15.0HR,DG,1368.,1.) 2204900700010 ((MONIT2)25-MN-54,312.2D,DG,835.,1.) 2204900700011 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,96(1987)52 2204900700012 (DEP,22049002) 2204900700013 (DEP,22049003) 2204900700014 HISTORY (20170811A) SD: BIB update. SF3=N+T -> X, 2204900700015 SF4=He-4 -> H-3 in REACTION code. 2204900700016 ENDBIB 14 0 2204900700017 COMMON 2 3 2204900700018 EN EN-RSL 2204900700019 MEV MEV 2204900700020 8.858 0.348 2204900700021 ENDCOMMON 3 0 2204900700022 DATA 6 1 2204900700023 DATA ERR-T MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 2204900700024 MB MB MB MB MB MB 2204900700025 326. 34. 61.48 4.67 477.8 21.0 2204900700026 ENDDATA 3 0 2204900700027 ENDSUBENT 26 0 2204900799999 SUBENT 22049008 20170811 22652204900800001 BIB 6 14 2204900800002 REACTION (3-LI-7(N,X)1-H-3,,SIG) Calculated as the mean value 2204900800003 for the two monitor reactions. 2204900800004 MONITOR ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG) 2204900800005 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG) cross sections 2204900800006 taken from NDF/B-V. 2204900800007 MONIT-REF ((MONIT1),,3,ENDF/B-V,,1979) 2204900800008 ((MONIT2),S.Tagesen+,B,PH-DAT,13-1,1981) 2204900800009 DECAY-MON ((MONIT1)11-NA-24,15.0HR,DG,1368.,1.) 2204900800010 ((MONIT2)25-MN-54,312.2D,DG,835.,1.) 2204900800011 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,96(1987)52 2204900800012 (DEP,22049002) 2204900800013 (DEP,22049003) 2204900800014 HISTORY (20170811A) SD: BIB update. SF3=N+T -> X, 2204900800015 SF4=He-4 -> H-3 in REACTION code. 2204900800016 ENDBIB 14 0 2204900800017 COMMON 2 3 2204900800018 EN EN-RSL 2204900800019 MEV MEV 2204900800020 9.447 0.352 2204900800021 ENDCOMMON 3 0 2204900800022 DATA 6 1 2204900800023 DATA ERR-T MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 2204900800024 MB MB MB MB MB MB 2204900800025 350. 37. 75.37 6.71 476.5 21.0 2204900800026 ENDDATA 3 0 2204900800027 ENDSUBENT 26 0 2204900899999 SUBENT 22049009 20170811 22652204900900001 BIB 6 14 2204900900002 REACTION (3-LI-7(N,X)1-H-3,,SIG) Calculated as the mean value 2204900900003 for the two monitor reactions. 2204900900004 MONITOR ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG) 2204900900005 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG) cross sections 2204900900006 taken from NDF/B-V. 2204900900007 MONIT-REF ((MONIT1),,3,ENDF/B-V,,1979) 2204900900008 ((MONIT2),S.Tagesen+,B,PH-DAT,13-1,1981) 2204900900009 DECAY-MON ((MONIT1)11-NA-24,15.0HR,DG,1368.,1.) 2204900900010 ((MONIT2)25-MN-56,2.58HR,DG,847.,.9887) 2204900900011 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,96(1987)52 2204900900012 (DEP,22049002) 2204900900013 (DEP,22049004) 2204900900014 HISTORY (20170811A) SD: BIB update. SF3=N+T -> X, 2204900900015 SF4=He-4 -> H-3 in REACTION code. 2204900900016 ENDBIB 14 0 2204900900017 COMMON 2 3 2204900900018 EN EN-RSL 2204900900019 MEV MEV 2204900900020 10.015 0.385 2204900900021 ENDCOMMON 3 0 2204900900022 DATA 6 1 2204900900023 DATA ERR-T MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 2204900900024 MB MB MB MB MB MB 2204900900025 384. 40. 87.57 3.94 69.20 2.77 2204900900026 ENDDATA 3 0 2204900900027 ENDSUBENT 26 0 2204900999999 SUBENT 22049010 20170811 22652204901000001 BIB 6 14 2204901000002 REACTION (3-LI-7(N,X)1-H-3,,SIG) Calculated as the mean value 2204901000003 for the two monitor reactions. 2204901000004 MONITOR ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG) 2204901000005 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG) cross sections 2204901000006 taken from NDF/B-V. 2204901000007 MONIT-REF ((MONIT1),,3,ENDF/B-V,,1979) 2204901000008 ((MONIT2),S.Tagesen+,B,PH-DAT,13-1,1981) 2204901000009 DECAY-MON ((MONIT1)11-NA-24,15.0HR,DG,1368.,1.) 2204901000010 ((MONIT2)25-MN-56,2.58HR,DG,847.,.9887) 2204901000011 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,96(1987)52 2204901000012 (DEP,22049002) 2204901000013 (DEP,22049004) 2204901000014 HISTORY (20170811A) SD: BIB update. SF3=N+T -> X, 2204901000015 SF4=He-4 -> H-3 in REACTION code. 2204901000016 ENDBIB 14 0 2204901000017 COMMON 2 3 2204901000018 EN EN-RSL 2204901000019 MEV MEV 2204901000020 10.478 0.411 2204901000021 ENDCOMMON 3 0 2204901000022 DATA 6 1 2204901000023 DATA ERR-T MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 2204901000024 MB MB MB MB MB MB 2204901000025 371. 47. 96.21 4.33 76.81 3.07 2204901000026 ENDDATA 3 0 2204901000027 ENDSUBENT 26 0 2204901099999 ENDENTRY 10 0 2204999999999