ENTRY 40066 20221014 4006600000001 SUBENT 40066001 20221014 20230412 4006600100001 BIB 14 40 4006600100002 TITLE The spectra of inelastic scattering neutrons and the 4006600100003 nuclear level density 4006600100004 AUTHOR (N.S.Biryukov,B.V.Zhuravlev,N.V.Kornilov,V.I.Plyaskin, 4006600100005 O.A.Sal'nikov) 4006600100006 REFERENCE (R,FEI-272,1,1971) 4006600100007 (W,BIRYUKOV,19731220) 4006600100008 INSTITUTE (4RUSFEI) 4006600100009 FACILITY (CYCLO,4RUSFEI) 4006600100010 INC-SOURCE (P-T) Neutron flux at an angle 30 degrees relative to 4006600100011 proton beam was used. Gas tritium target thickness - 4006600100012 60 keV, current on the target 0.4 microA, pulse 4006600100013 frequency 2.91 MHz. 4006600100014 SAMPLE Hollow truncated cone 4006600100015 METHOD (TOF) Time of flight method with the time resolution 4006600100016 2.25 nsec/m, flight path 2.84 m. Ring geometry. 4006600100017 DETECTOR (SCIN) Scintillation liquid in Al cylinder of 10 cm 4006600100018 diameter, 5 cm height, equipped by photomultiplier 4006600100019 FEU-63, protected by lead and thick layer of paraffin 4006600100020 and Li hydride. 4006600100021 256 channels analyzer, channel width 1.28 nsec. 4006600100022 Time resolution 2.25 nsec/m (FWHM). 4006600100023 Detection relative efficiency was measured and 4006600100024 presented on Fig.2 of FEI-272. 4006600100025 MONITOR Double diff. inel. scat. cs. (spectra) are given in 4006600100026 arbitrary units. Diff. elast. and inel. scat. cs. 4006600100027 were measured absolutely. 4006600100028 COMMENT The experimental neutron spectra were analyzed for 4006600100029 determining the nuclear temperature and the nuclear 4006600100030 level density parameter 4006600100031 CORRECTION The measured neutron spectra were corrected by the 4006600100032 dead time of the electronic scheme 4006600100033 ERR-ANALYS The neutron spectra error (10-20 %) consists of 4006600100034 statistical error, the error of detector efficiency and4006600100035 the error of determination of energy corresponding to 4006600100036 definite pulse analyzer channel. 4006600100037 (DATA-ERR) Type of uncertainty is not explained in the 4006600100038 article. 4006600100039 HISTORY (19731220C) Compiled at the centre 4006600100040 (20210706A) M.M. Update for current rules. 4006600100041 (20221014A) Subents 012-014 were corrected. 4006600100042 ENDBIB 40 0 4006600100043 NOCOMMON 0 0 4006600100044 ENDSUBENT 43 0 4006600199999 SUBENT 40066002 20210706 41974006600200001 BIB 2 2 4006600200002 REACTION (6-C-12(N,EL)6-C-12,,DA) 4006600200003 STATUS (TABLE) Table 4 of FEI-272 4006600200004 ENDBIB 2 0 4006600200005 COMMON 3 3 4006600200006 EN EN-RSL-HW ANG 4006600200007 MEV MEV ADEG 4006600200008 9.2 0.3 32. 4006600200009 ENDCOMMON 3 0 4006600200010 DATA 2 1 4006600200011 DATA DATA-ERR 4006600200012 MB/SR MB/SR 4006600200013 221. 15. 4006600200014 ENDDATA 3 0 4006600200015 ENDSUBENT 14 0 4006600299999 SUBENT 40066003 20210706 41974006600300001 BIB 2 2 4006600300002 REACTION (6-C-12(N,INL)6-C-12,PAR,DA) 4006600300003 STATUS (TABLE) Table 4 of FEI-272 4006600300004 ENDBIB 2 0 4006600300005 COMMON 4 3 4006600300006 E-LVL EN EN-RSL-HW ANG 4006600300007 MEV MEV MEV ADEG 4006600300008 4.43 9.2 0.3 32. 4006600300009 ENDCOMMON 3 0 4006600300010 DATA 2 1 4006600300011 DATA DATA-ERR 4006600300012 MB/SR MB/SR 4006600300013 47. 9.0 4006600300014 ENDDATA 3 0 4006600300015 ENDSUBENT 14 0 4006600399999 SUBENT 40066004 20210706 41974006600400001 BIB 3 4 4006600400002 REACTION (13-AL-27(N,X)0-NN-1,,DA/DE,,REL) 4006600400003 STATUS (TABLE) From author 4006600400004 HISTORY (20210706A) REACTION was corrected: 4006600400005 INL -> X, SF4=0-NN-1 (En is above (n,n+p) threshld). 4006600400006 ENDBIB 4 0 4006600400007 COMMON 3 3 4006600400008 EN EN-RSL-HW ANG 4006600400009 MEV MEV ADEG 4006600400010 9.2 0.3 32. 4006600400011 ENDCOMMON 3 0 4006600400012 DATA 3 60 4006600400013 E DATA DATA-ERR 4006600400014 MEV ARB-UNITS PER-CENT 4006600400015 6.0000E-01 4.0500E+00 4.8000E+01 4006600400016 7.0000E-01 3.4000E+00 3.6000E+01 4006600400017 8.0000E-01 6.8900E+00 1.3000E+01 4006600400018 9.0000E-01 7.1400E+00 9.8000E+00 4006600400019 1.0000E+00 8.1600E+00 7.5000E+00 4006600400020 1.1000E+00 8.6900E+00 6.6000E+00 4006600400021 1.2000E+00 8.2000E+00 6.6000E+00 4006600400022 1.3000E+00 7.8700E+00 6.2000E+00 4006600400023 1.4000E+00 7.9500E+00 7.2000E+00 4006600400024 1.5000E+00 7.9000E+00 6.3000E+00 4006600400025 1.6000E+00 7.9300E+00 6.9000E+00 4006600400026 1.7000E+00 7.9400E+00 7.9000E+00 4006600400027 1.8000E+00 7.8700E+00 6.9000E+00 4006600400028 1.9000E+00 7.7100E+00 8.0000E+00 4006600400029 2.0000E+00 7.4300E+00 8.1000E+00 4006600400030 2.1000E+00 7.1000E+00 8.3000E+00 4006600400031 2.2000E+00 6.6400E+00 8.2000E+00 4006600400032 2.3000E+00 6.0900E+00 1.0000E+01 4006600400033 2.4000E+00 5.5600E+00 1.0000E+01 4006600400034 2.5000E+00 4.9800E+00 1.0000E+01 4006600400035 2.6000E+00 4.3700E+00 1.1000E+01 4006600400036 2.7000E+00 3.7600E+00 1.1000E+01 4006600400037 2.8000E+00 3.3200E+00 1.2000E+01 4006600400038 2.9000E+00 2.8900E+00 1.1000E+01 4006600400039 3.0000E+00 2.3500E+00 1.1000E+01 4006600400040 3.1000E+00 1.9900E+00 1.3000E+01 4006600400041 3.1800E+00 1.7900E+00 1.4000E+01 4006600400042 3.2900E+00 1.5200E+00 1.2000E+01 4006600400043 3.4000E+00 1.3000E+00 1.5000E+01 4006600400044 3.4800E+00 1.1900E+00 1.6000E+01 4006600400045 3.5600E+00 1.1100E+00 1.6000E+01 4006600400046 3.6900E+00 1.0600E+00 1.3000E+01 4006600400047 3.8300E+00 1.0500E+00 1.6000E+01 4006600400048 3.9200E+00 9.2100E-01 1.6000E+01 4006600400049 4.0300E+00 1.0800E+00 1.6000E+01 4006600400050 4.1300E+00 1.0700E+00 1.8000E+01 4006600400051 4.2300E+00 1.2600E+00 1.8000E+01 4006600400052 4.3500E+00 1.3400E+00 1.8000E+01 4006600400053 4.4600E+00 1.2900E+00 1.8000E+01 4006600400054 4.5800E+00 1.2700E+00 1.8000E+01 4006600400055 4.7100E+00 1.4100E+00 1.9000E+01 4006600400056 4.8400E+00 1.3300E+00 1.9000E+01 4006600400057 5.0000E+00 1.2900E+00 2.0000E+01 4006600400058 5.1200E+00 9.1000E-01 2.0000E+01 4006600400059 5.2600E+00 8.0300E-01 2.0000E+01 4006600400060 5.4200E+00 1.0400E+00 2.0000E+01 4006600400061 5.5800E+00 1.2300E+00 2.0000E+01 4006600400062 5.7500E+00 1.9300E+00 2.0000E+01 4006600400063 5.9300E+00 2.2500E+00 2.1000E+01 4006600400064 6.1200E+00 2.5300E+00 2.1000E+01 4006600400065 6.3100E+00 2.3800E+00 2.2000E+01 4006600400066 6.5200E+00 1.8800E+00 2.2000E+01 4006600400067 6.7300E+00 1.4400E+00 2.3000E+01 4006600400068 6.9500E+00 8.5200E-01 2.7000E+01 4006600400069 7.1900E+00 7.1200E-01 2.8000E+01 4006600400070 7.4400E+00 4.8500E-01 2.9000E+01 4006600400071 7.7000E+00 3.7600E-01 2.9000E+01 4006600400072 7.9800E+00 2.3400E-01 2.7000E+01 4006600400073 8.2700E+00 1.5600E-01 2.8000E+01 4006600400074 8.5700E+00 1.2300E-01 2.9000E+01 4006600400075 ENDDATA 62 0 4006600400076 ENDSUBENT 75 0 4006600499999 SUBENT 40066005 20210706 41974006600500001 BIB 2 2 4006600500002 REACTION (13-AL-27(N,EL)13-AL-27,,DA) 4006600500003 STATUS (TABLE) Table 4 of FEI-272 4006600500004 ENDBIB 2 0 4006600500005 COMMON 3 3 4006600500006 EN EN-RSL-HW ANG 4006600500007 MEV MEV ADEG 4006600500008 9.2 0.3 32. 4006600500009 ENDCOMMON 3 0 4006600500010 DATA 2 1 4006600500011 DATA DATA-ERR 4006600500012 MB/SR MB/SR 4006600500013 186. 12. 4006600500014 ENDDATA 3 0 4006600500015 ENDSUBENT 14 0 4006600599999 SUBENT 40066006 20210706 41974006600600001 BIB 3 8 4006600600002 REACTION (13-AL-27(N,X)0-NN-1,PAR,DA) 4006600600003 STATUS (TABLE) Table 4 of FEI-272 4006600600004 (DEP,40066004) Quantity was obtained by normalization 4006600600005 and integration of measured spectrum (Subent 40066004) 4006600600006 and corresponds to the energy range of scattering 4006600600007 neutrons 0.7-9.2 MeV 4006600600008 HISTORY (20210706A) REACTION was corrected: 4006600600009 INL -> X, SF4=0-NN-1 (En is above (n,n+p) threshld). 4006600600010 ENDBIB 8 0 4006600600011 COMMON 3 3 4006600600012 EN EN-RSL-HW ANG 4006600600013 MEV MEV ADEG 4006600600014 9.2 0.3 32. 4006600600015 ENDCOMMON 3 0 4006600600016 DATA 4 1 4006600600017 E-MIN E-MAX DATA DATA-ERR 4006600600018 MEV MEV MB/SR MB/SR 4006600600019 0.7 9.2 85. 16. 4006600600020 ENDDATA 3 0 4006600600021 ENDSUBENT 20 0 4006600699999 SUBENT 40066007 20210706 41974006600700001 BIB 2 5 4006600700002 REACTION (13-AL-27(0,0),,TEM) 4006600700003 Nuclear Temperature 4006600700004 STATUS (TABLE) Table 1 of FEI-272 4006600700005 (DEP,40066004) Quantity was obtained by analyzing of 4006600700006 measured spectrum from Subent 40066004 4006600700007 ENDBIB 5 0 4006600700008 NOCOMMON 0 0 4006600700009 DATA 2 1 4006600700010 DATA DATA-ERR 4006600700011 MEV MEV 4006600700012 1.2 0.11 4006600700013 ENDDATA 3 0 4006600700014 ENDSUBENT 13 0 4006600799999 SUBENT 40066008 20210706 41974006600800001 BIB 3 4 4006600800002 REACTION (29-CU-0(N,X)0-NN-1,,DA/DE,,REL) 4006600800003 STATUS (TABLE) From author 4006600800004 HISTORY (20210706A) REACTION was corrected: 4006600800005 INL -> X, SF4=0-NN-1 (En is above (n,n+p) threshld). 4006600800006 ENDBIB 4 0 4006600800007 COMMON 3 3 4006600800008 EN EN-RSL-HW ANG 4006600800009 MEV MEV ADEG 4006600800010 9.2 0.3 32. 4006600800011 ENDCOMMON 3 0 4006600800012 DATA 3 60 4006600800013 E DATA DATA-ERR 4006600800014 MEV ARB-UNITS PER-CENT 4006600800015 6.0000E-01 1.0990E+01 3.5000E+01 4006600800016 7.0000E-01 1.1320E+01 2.4000E+01 4006600800017 8.0000E-01 1.1590E+01 2.1000E+01 4006600800018 9.0000E-01 1.2710E+01 1.7000E+01 4006600800019 1.0000E+00 1.1090E+01 1.5000E+01 4006600800020 1.1000E+00 9.9900E+00 1.4000E+01 4006600800021 1.2000E+00 8.8700E+00 1.3000E+01 4006600800022 1.3000E+00 8.3700E+00 1.2000E+01 4006600800023 1.4000E+00 8.5500E+00 1.1000E+01 4006600800024 1.5000E+00 8.4600E+00 1.0000E+01 4006600800025 1.6000E+00 8.2000E+00 9.8000E+00 4006600800026 1.7000E+00 7.8600E+00 9.6000E+00 4006600800027 1.8000E+00 7.4100E+00 9.4000E+00 4006600800028 1.9000E+00 6.9400E+00 9.3000E+00 4006600800029 2.0000E+00 6.5800E+00 9.2 4006600800030 2.1000E+00 6.2100E+00 9.2 4006600800031 2.2000E+00 5.7300E+00 9.2 4006600800032 2.3000E+00 5.2800E+00 9.2 4006600800033 2.4000E+00 4.8800E+00 9.3000E+00 4006600800034 2.5000E+00 4.4600E+00 9.4000E+00 4006600800035 2.6000E+00 4.0100E+00 9.4000E+00 4006600800036 2.7000E+00 3.5700E+00 9.5000E+00 4006600800037 2.8000E+00 3.2300E+00 9.7000E+00 4006600800038 2.9000E+00 2.9200E+00 9.9000E+00 4006600800039 3.0000E+00 2.5100E+00 1.0000E+01 4006600800040 3.1000E+00 2.2200E+00 1.0000E+01 4006600800041 3.2000E+00 2.0400E+00 1.1000E+01 4006600800042 3.3000E+00 1.7900E+00 1.1000E+01 4006600800043 3.4000E+00 1.5600E+00 1.1000E+01 4006600800044 3.4800E+00 1.4200E+00 1.2000E+01 4006600800045 3.5700E+00 1.2900E+00 1.2000E+01 4006600800046 3.7000E+00 1.1200E+00 1.2000E+01 4006600800047 3.8400E+00 9.6500E-01 1.3000E+01 4006600800048 3.9300E+00 8.7000E-01 1.3000E+01 4006600800049 4.0300E+00 7.8300E-01 1.4000E+01 4006600800050 4.1300E+00 7.0300E-01 1.4000E+01 4006600800051 4.2400E+00 6.2900E-01 1.5000E+01 4006600800052 4.3500E+00 5.6000E-01 1.5000E+01 4006600800053 4.4700E+00 4.9700E-01 1.6000E+01 4006600800054 4.5900E+00 4.4000E-01 1.7000E+01 4006600800055 4.7100E+00 3.8900E-01 1.8000E+01 4006600800056 4.8500E+00 3.4100E-01 2.0000E+01 4006600800057 4.9800E+00 2.9800E-01 2.1000E+01 4006600800058 5.1300E+00 2.5700E-01 2.4000E+01 4006600800059 5.2700E+00 2.2000E-01 2.6000E+01 4006600800060 5.4300E+00 1.8800E-01 3.0000E+01 4006600800061 5.5900E+00 1.5800E-01 3.3000E+01 4006600800062 5.7600E+00 1.3200E-01 4.0000E+01 4006600800063 5.9400E+00 1.0900E-01 4.8000E+01 4006600800064 6.1300E+00 8.9600E-02 5.8000E+01 4006600800065 6.3200E+00 7.1900E-02 7.1000E+01 4006600800066 6.5300E+00 5.6700E-02 8.8000E+01 4006600800067 6.7400E+00 4.3600E-02 8.8000E+01 4006600800068 6.9700E+00 3.2500E-02 9.0000E+01 4006600800069 7.2000E+00 2.3300E-02 8.9000E+01 4006600800070 7.4500E+00 1.6000E-02 9.2000E+01 4006600800071 7.7200E+00 1.0100E-02 9.5000E+01 4006600800072 7.9900E+00 5.7000E-03 9.2000E+01 4006600800073 8.2800E+00 2.5000E-03 9.7000E+01 4006600800074 8.5900E+00 7.5000E-04 1.1000E+02 4006600800075 ENDDATA 62 0 4006600800076 ENDSUBENT 75 0 4006600899999 SUBENT 40066009 20210706 41974006600900001 BIB 2 2 4006600900002 REACTION (29-CU-0(N,EL)29-CU-0,,DA) 4006600900003 STATUS (TABLE) Table 4 of FEI-272 4006600900004 ENDBIB 2 0 4006600900005 COMMON 3 3 4006600900006 EN EN-RSL-HW ANG 4006600900007 MEV MEV ADEG 4006600900008 9.2 0.3 32. 4006600900009 ENDCOMMON 3 0 4006600900010 DATA 2 1 4006600900011 DATA DATA-ERR 4006600900012 MB/SR MB/SR 4006600900013 291. 20. 4006600900014 ENDDATA 3 0 4006600900015 ENDSUBENT 14 0 4006600999999 SUBENT 40066010 20210706 41974006601000001 BIB 3 8 4006601000002 REACTION (29-CU-0(N,X)0-NN-1,PAR,DA) 4006601000003 STATUS (TABLE) Table 4 of FEI-272 4006601000004 (DEP,40066008) Quantity was obtained by normalization 4006601000005 and integration of measured spectrum (SUBENT 40066008) 4006601000006 and corresponds to the energy space of scattering 4006601000007 neutrons 0.7-9.2 MeV 4006601000008 HISTORY (20210706A) REACTION was corrected: 4006601000009 INL -> X, SF4=0-NN-1 (En is above (n,n+p) threshld). 4006601000010 ENDBIB 8 0 4006601000011 COMMON 3 3 4006601000012 EN EN-RSL-HW ANG 4006601000013 MEV MEV ADEG 4006601000014 9.2 0.3 32. 4006601000015 ENDCOMMON 3 0 4006601000016 DATA 4 1 4006601000017 E-MIN E-MAX DATA DATA-ERR 4006601000018 MEV MEV MB/SR MB/SR 4006601000019 0.7 9.2 88. 17. 4006601000020 ENDDATA 3 0 4006601000021 ENDSUBENT 20 0 4006601099999 SUBENT 40066011 20210706 41974006601100001 BIB 2 5 4006601100002 REACTION (29-CU-0(0,0),,TEM) 4006601100003 Nuclear temperature 4006601100004 STATUS (TABLE) Table 1 of FEI-272 4006601100005 (DEP,40066011) Quantity was obtained by analyzing of 4006601100006 measured spectrum from Subent 40066011 4006601100007 ENDBIB 5 0 4006601100008 NOCOMMON 0 0 4006601100009 DATA 2 1 4006601100010 DATA DATA-ERR 4006601100011 MEV MEV 4006601100012 0.79 0.07 4006601100013 ENDDATA 3 0 4006601100014 ENDSUBENT 13 0 4006601199999 SUBENT 40066012 20221014 20230412 4006601200001 BIB 3 6 4006601200002 REACTION (41-NB-93(N,X)0-NN-1,,DA/DE,,REL) 4006601200003 Spectrum in arbitrary units. 4006601200004 STATUS (TABLE) From author 4006601200005 HISTORY (20210706A) REACTION was corrected: 4006601200006 INL -> X, SF4=0-NN-1 (En is above (n,n+p) threshold). 4006601200007 (20221014U) Free text was corrected. 4006601200008 ENDBIB 6 0 4006601200009 COMMON 3 3 4006601200010 EN EN-RSL-HW ANG 4006601200011 MEV MEV ADEG 4006601200012 9.2 0.3 32. 4006601200013 ENDCOMMON 3 0 4006601200014 DATA 3 60 4006601200015 E DATA DATA-ERR 4006601200016 MEV ARB-UNITS PER-CENT 4006601200017 6.0000E-01 3.5700E+00 4.5000E+01 4006601200018 7.0000E-01 2.8000E+00 1.9000E+01 4006601200019 8.0000E-01 4.8900E+00 1.5000E+01 4006601200020 9.0000E-01 5.0200E+00 1.2000E+01 4006601200021 1.0000E+00 4.8900E+00 9.9000E+00 4006601200022 1.1000E+00 5.4500E+00 7.8000E+00 4006601200023 1.2000E+00 6.0400E+00 6.6000E+00 4006601200024 1.3000E+00 6.2200E+00 6.2000E+00 4006601200025 1.4000E+00 6.1700E+00 5.7000E+00 4006601200026 1.5000E+00 5.9000E+00 5.3000E+00 4006601200027 1.6000E+00 5.7100E+00 5.5000E+00 4006601200028 1.7000E+00 5.5400E+00 6.1000E+00 4006601200029 1.8000E+00 5.3300E+00 5.9000E+00 4006601200030 1.9000E+00 5.0500E+00 5.0000E+00 4006601200031 2.0000E+00 4.7500E+00 7.0000E+00 4006601200032 2.1000E+00 4.4800E+00 5.7000E+00 4006601200033 2.2000E+00 4.1500E+00 7.0000E+00 4006601200034 2.3000E+00 3.7600E+00 5.7000E+00 4006601200035 2.4000E+00 3.3300E+00 7.1000E+00 4006601200036 2.5000E+00 2.9600E+00 7.3000E+00 4006601200037 2.6000E+00 2.5900E+00 7.4000E+00 4006601200038 2.7000E+00 2.2300E+00 7.6000E+00 4006601200039 2.8000E+00 1.9700E+00 1.1000E+01 4006601200040 2.9000E+00 1.7300E+00 8.2000E+00 4006601200041 3.0000E+00 1.5100E+00 1.2000E+01 4006601200042 3.1000E+00 1.3000E+00 9.0000E+00 4006601200043 3.2000E+00 1.1200E+00 1.4000E+01 4006601200044 3.3000E+00 9.6500E-01 1.0000E+01 4006601200045 3.4000E+00 8.2500E-01 1.5000E+01 4006601200046 3.5000E+00 7.4500E-01 1.6000E+01 4006601200047 3.5800E+00 6.7300E-01 1.7000E+01 4006601200048 3.6600E+00 6.0900E-01 1.8000E+01 4006601200049 3.7500E+00 5.5200E-01 1.8000E+01 4006601200050 3.8900E+00 4.7600E-01 2.0000E+01 4006601200051 4.0400E+00 4.0900E-01 2.1000E+01 4006601200052 4.1500E+00 3.6900E-01 2.2000E+01 4006601200053 4.2500E+00 3.3300E-01 2.3000E+01 4006601200054 4.3700E+00 2.9900E-01 2.4000E+01 4006601200055 4.4800E+00 2.6700E-01 2.6000E+01 4006601200056 4.6000E+00 2.3800E-01 2.8000E+01 4006601200057 4.7300E+00 2.1100E-01 3.0000E+01 4006601200058 4.8600E+00 1.8600E-01 3.2000E+01 4006601200059 5.0000E+00 1.6300E-01 3.3000E+01 4006601200060 5.1400E+00 1.4100E-01 3.3000E+01 4006601200061 5.2900E+00 1.2000E-01 3.1000E+01 4006601200062 5.4500E+00 1.0200E-01 3.4000E+01 4006601200063 5.6100E+00 8.6300E-02 3.5000E+01 4006601200064 5.7800E+00 7.2000E-02 3.4000E+01 4006601200065 5.9700E+00 5.9000E-02 3.6000E+01 4006601200066 6.1500E+00 4.8000E-02 4.1000E+01 4006601200067 6.3500E+00 3.8000E-02 4.2000E+01 4006601200068 6.5500E+00 3.0000E-02 4.9000E+01 4006601200069 6.7700E+00 2.3000E-02 5.4000E+01 4006601200070 7.0000E+00 1.7000E-02 6.1000E+01 4006601200071 7.2400E+00 1.2000E-02 6.4000E+01 4006601200072 7.4900E+00 8.2000E-03 6.9000E+01 4006601200073 7.7500E+00 5.2000E-03 7.6000E+01 4006601200074 8.0300E+00 2.7000E-03 8.2000E+01 4006601200075 8.3200E+00 1.1000E-03 9.2000E+01 4006601200076 8.6300E+00 3.7000E-04 1.1000E+02 4006601200077 ENDDATA 62 0 4006601200078 ENDSUBENT 77 0 4006601299999 SUBENT 40066013 20221014 20230412 4006601300001 BIB 5 9 4006601300002 REACTION (41-NB-93(N,EL)41-NB-93,EXL,DA) 4006601300003 CRITIQUE Of S.Simakov. 4006601300004 Possible inclusion of inelastic scattering below 4006601300005 0.6 MeV. First ex.level 0.0308 MeV . 4006601300006 See REL-REF, page 134. 4006601300007 REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 4006601300008 STATUS (TABLE) Table 4 of FEI-272 4006601300009 HISTORY (20220714A) Code EXL was inserted according to the 4006601300010 comment of S.Simakov. 4006601300011 ENDBIB 9 0 4006601300012 COMMON 3 3 4006601300013 EN EN-RSL-HW ANG 4006601300014 MEV MEV ADEG 4006601300015 9.2 0.3 32. 4006601300016 ENDCOMMON 3 0 4006601300017 DATA 2 1 4006601300018 DATA DATA-ERR 4006601300019 MB/SR MB/SR 4006601300020 425. 30. 4006601300021 ENDDATA 3 0 4006601300022 ENDSUBENT 21 0 4006601399999 SUBENT 40066014 20221014 20230412 4006601400001 BIB 3 9 4006601400002 REACTION (41-NB-93(N,X)0-NN-1,PAR,DA) 4006601400003 STATUS (TABLE) Table 4 of FEI-272 4006601400004 (DEP,40066012) Quantity was obtained by normalization 4006601400005 and integration of measured spectrum (Subent 40066012) 4006601400006 and corresponds to the energy range of scattering 4006601400007 neutrons 0.7-9.2 MeV 4006601400008 HISTORY (20210706A) REACTION was corrected: 4006601400009 INL -> X, SF4=0-NN-1 (En is above (n,n+p) threshold). 4006601400010 (20221014U) Free text was corrected. 4006601400011 ENDBIB 9 0 4006601400012 COMMON 3 3 4006601400013 EN EN-RSL-HW ANG 4006601400014 MEV MEV ADEG 4006601400015 9.2 0.3 32. 4006601400016 ENDCOMMON 3 0 4006601400017 DATA 4 1 4006601400018 E-MIN E-MAX DATA DATA-ERR 4006601400019 MEV MEV MB/SR MB/SR 4006601400020 0.7 9.2 124. 24. 4006601400021 ENDDATA 3 0 4006601400022 ENDSUBENT 21 0 4006601499999 SUBENT 40066015 20210706 41974006601500001 BIB 2 5 4006601500002 REACTION (41-NB-93(0,0),,TEM) 4006601500003 Nuclear temperature 4006601500004 STATUS (TABLE) Table 1 of FEI-272 4006601500005 (DEP,40066012) Quantity was obtained by analyzing of 4006601500006 measured spectrum from Subent 40066012 4006601500007 ENDBIB 5 0 4006601500008 NOCOMMON 0 0 4006601500009 DATA 2 1 4006601500010 DATA DATA-ERR 4006601500011 MEV MEV 4006601500012 0.82 0.07 4006601500013 ENDDATA 3 0 4006601500014 ENDSUBENT 13 0 4006601599999 ENDENTRY 15 0 4006699999999