ENTRY 21777 20210212 22972177700000001 SUBENT 21777001 20210212 22972177700100001 BIB 11 39 2177700100002 TITLE Measurement of neutron capture cross section and alpha 2177700100003 of 235U from 2 to 85 keV 2177700100004 AUTHOR (F.Corvi, L.Calabretta, M.Merla, T.Van Der Veen, 2177700100005 M.S.Moore) 2177700100006 INSTITUTE (2ZZZGEL) 2177700100007 REFERENCE ((S,ANL-83-4,347,1983)=(S,NEANDC(US)-214,347,1983)) 2177700100008 Tabulated data given 2177700100009 ((P,NEANDC(E)-232,(3),5,1982)=(P,INDC(EUR)-016,5,1982))2177700100010 Same tabulated data given 2177700100011 ((P,NEANDC(E)-222,(3),3,1981)=(P,INDC(EUR)-014,3,1981))2177700100012 alpha-values in fig. 2177700100013 FACILITY (LINAC,2ZZZGEL) Geel 140 MeV electron linac 2177700100014 INC-SOURCE (PHOTO) 14 ns burst width and 800 Hz repetition 2177700100015 frequency 2177700100016 SAMPLE U3O8 (2.549 gram of 235U in total) 2177700100017 (92-U-235,ENR=0.99508) 2177700100018 (92-U-234,ENR=0.00169) 2177700100019 (92-U-236,ENR=0.00026) 2177700100020 (92-U-238,ENR=0.00301) 2177700100021 METHOD (TOF) Detector system at 28.8 m from target 2177700100022 (COINC) 2177700100023 DETECTOR (FISCH) Multiplate fission chamber 2177700100024 (SCIN) C6F6 (10.2 cm diam. and 7.6 cm height). 2177700100025 Pulses in coincidence with fission chamber pulses 2177700100026 were considered to be due to fission gamma-rays. 2177700100027 (GLASD) Thin 6Li glass detector (0.5 mm thick) 2177700100028 ANALYSIS Background was determined by measuring Al black 2177700100029 resonances at 35 and 88 keV. 2177700100030 HISTORY (19820803C) T.N 2177700100031 (19820921E) 2177700100032 (20060426A) REACTION SF4 in SAN 004 corrected 2177700100033 (20061023U) Reference ANL-83-4,1983 added - SM 2177700100034 (20111219A) BIB information corrected. 3 SUBENTs added 2177700100035 (20160907A) SD:Subent 005, 006 deleted according 2177700100036 'NRDC 2014' Conclusion 30 ('Data sets derived by 2177700100037 other than the author are not for compilation...'). 2177700100038 (20170601A) On. 004 merged into 003. Major revision in 2177700100039 002 and 003. 2177700100040 (20210212U) On. REFERENCE updated. 2177700100041 ENDBIB 39 0 2177700100042 COMMON 1 3 2177700100043 EN-RSL 2177700100044 NSEC/M 2177700100045 0.5 2177700100046 ENDCOMMON 3 0 2177700100047 ENDSUBENT 46 0 2177700199999 SUBENT 21777002 20210212 22972177700200001 BIB 7 20 2177700200002 REACTION (92-U-235(N,F),,SIG,,AV) 2177700200003 MONITOR ((MONIT)92-U-235(N,F),,INT) 2177700200004 (3-LI-6(N,T)2-HE-4,,SIG) Flux shape 2177700200005 MONIT-REF ((MONIT),,3,ENDF/B-V,,1978) 2177700200006 COMMENT By compiler (2021-02-12): 2177700200007 The uncertainty in the monitor cross section integral 2177700200008 (241.2 b-eV) is not mentioned by the authors. The 2177700200009 evaluation report of the 235U(n,f) fast neutron cross 2177700200010 section for ENDF-B/V (W.P.Poenitz, ANL/NDM-045) 2177700200011 mentions he adopted 243.7+/-1.0 b-eV, which is 2177700200012 slightly higher than 241.2 b-eV. Table I of this 2177700200013 report (=Table 11 of W.P.Poenitz and G. de Saussure, 2177700200014 Prog.Nucl.Energy 13(1984)129) shows that the cross 2177700200015 section integral by de Saussure, ORNL-TM-1804, 1967 2177700200016 is 241.3+/-4.8 b-eV. 2177700200017 ERR-ANALYS (ERR-1) Fission chamber efficiency (1%) 2177700200018 (ERR-2) Shape normalization to 6Li(n,a) 2177700200019 STATUS (TABLE) Table III of ANL-83-4, p347 (1983) 2177700200020 HISTORY (20170601A) On. ERR-ANALYS revised. ERR-T -> ERR-2 2177700200021 (20210212U) On. COMMENT added. 2177700200022 ENDBIB 20 0 2177700200023 COMMON 4 3 2177700200024 EN-NRM-MIN EN-NRM-MAX MONIT ERR-1 2177700200025 EV EV B*EV PER-CENT 2177700200026 7.8 11. 241.2 1. 2177700200027 ENDCOMMON 3 0 2177700200028 DATA 4 22 2177700200029 EN-MIN EN-MAX DATA ERR-2 2177700200030 KEV KEV B B 2177700200031 2.0 3.0 5.231 0.073 2177700200032 3.0 4.0 4.684 0.072 2177700200033 4.0 5.0 4.157 0.069 2177700200034 5.0 5.8 3.772 0.065 2177700200035 6.0 7.0 3.235 0.059 2177700200036 7.0 8.0 3.148 0.059 2177700200037 8.0 9.0 2.937 0.057 2177700200038 9.0 10. 3.080 0.061 2177700200039 10. 12. 2.645 0.054 2177700200040 12. 14. 2.581 0.055 2177700200041 14. 16. 2.451 0.053 2177700200042 16. 18. 2.297 0.051 2177700200043 18. 20. 2.325 0.053 2177700200044 20. 25. 2.148 0.050 2177700200045 25. 30. 2.060 0.050 2177700200046 30. 33. 2.016 0.050 2177700200047 38. 40. 1.870 0.049 2177700200048 40. 50. 1.835 0.049 2177700200049 50. 60. 1.781 0.049 2177700200050 60. 70. 1.727 0.049 2177700200051 70. 80. 1.652 0.048 2177700200052 80. 85. 1.580 0.046 2177700200053 ENDDATA 24 0 2177700200054 ENDSUBENT 53 0 2177700299999 SUBENT 21777003 20170601 22622177700300001 BIB 6 13 2177700300002 REACTION 1(92-U-235(N,ABS),,ALF,,AV) 2177700300003 2(92-U-235(N,G)92-U-236,,SIG,,AV) 2177700300004 MONITOR 2(92-U-235(N,F),,SIG,,AV) 2177700300005 METHOD (PHWT) 2177700300006 ERR-ANALYS (ERR-1) Fission efficiency (1%) 2177700300007 (ERR-2) Capture normalization (6%) 2177700300008 1(ERR-3) Background subtraction and undetected fissions 2177700300009 2(ERR-3) Background subtraction, undetected fissions, 2177700300010 and 6Li(n,a) normalization. 2177700300011 STATUS (TABLE) Table III of ANL-83-4, p347 (1983) 2177700300012 (DEP,21777002) 235U(n,f) cross section 2177700300013 HISTORY (20170601A) On. ERR-ANALYS revised. ERR-T -> ERR-3. 2177700300014 004 merged into 003. 2177700300015 ENDBIB 13 0 2177700300016 COMMON 2 3 2177700300017 ERR-1 ERR-2 2177700300018 PER-CENT PER-CENT 2177700300019 1. 6. 2177700300020 ENDCOMMON 3 0 2177700300021 DATA 6 22 2177700300022 EN-MIN EN-MAX DATA 1ERR-3 1DATA 2ERR-3 22177700300023 KEV KEV NO-DIM NO-DIM B B 2177700300024 2.0 3.0 0.363 0.045 1.898 0.23 2177700300025 3.0 4.0 0.345 0.035 1.615 0.16 2177700300026 4.0 5.0 0.345 0.031 1.435 0.13 2177700300027 5.0 5.8 0.309 0.033 1.166 0.12 2177700300028 6.0 7.0 0.381 0.036 1.234 0.12 2177700300029 7.0 8.0 0.372 0.028 1.171 0.09 2177700300030 8.0 9.0 0.441 0.026 1.296 0.08 2177700300031 9.0 10. 0.361 0.022 1.111 0.070 2177700300032 10. 12. 0.366 0.021 0.967 0.060 2177700300033 12. 14. 0.359 0.020 0.926 0.054 2177700300034 14. 16. 0.345 0.018 0.846 0.049 2177700300035 16. 18. 0.384 0.018 0.883 0.045 2177700300036 18. 20. 0.321 0.016 0.745 0.041 2177700300037 20. 25. 0.359 0.016 0.770 0.038 2177700300038 25. 30. 0.332 0.015 0.683 0.035 2177700300039 30. 33. 0.312 0.021 0.630 0.045 2177700300040 38. 40. 0.300 0.025 0.561 0.049 2177700300041 40. 50. 0.312 0.021 0.572 0.042 2177700300042 50. 60. 0.301 0.018 0.537 0.036 2177700300043 60. 70. 0.302 0.018 0.523 0.034 2177700300044 70. 80. 0.291 0.021 0.482 0.038 2177700300045 80. 85. 0.297 0.029 0.468 0.048 2177700300046 ENDDATA 24 0 2177700300047 ENDSUBENT 46 0 2177700399999 NOSUBENT 21777004 20170601 22622177700400001 NOSUBENT 21777005 20160907 22522177700500001 NOSUBENT 21777006 20160907 22522177700600001 ENDENTRY 6 0 2177799999999