ENTRY 10333 20201113 14731033300000001 SUBENT 10333001 20201113 14731033300100001 BIB 8 16 1033300100002 TITLE Relative and absolute measurements of the fast-neutron 1033300100003 fission cross section of uranium-235 1033300100004 AUTHOR (W.P.Poenitz) 1033300100005 INSTITUTE (1USAANL) 1033300100006 REFERENCE (J,NSE,53,370,1974) 1033300100007 (C,70ANL,,281,1970) 1033300100008 Preliminary data for 51V(p,n)51Cr source 1033300100009 REL-REF (I,,W.P.Poenitz,J,NIM,109,413,1973) 1033300100010 Description of black neutron detector (BND) 1033300100011 FACILITY (VDG) 1033300100012 (DYNAM) 1033300100013 STATUS (APRVD) Approved by author. 1033300100014 HISTORY (19740308C) 1033300100015 (19830324A) Converted to REACTION formalism 1033300100016 (20020926A) Updated to new date formats, lower case. 1033300100017 (20201113A) On. 002-007 superseded. 009-015 added. 1033300100018 ENDBIB 16 0 1033300100019 NOCOMMON 0 0 1033300100020 ENDSUBENT 19 0 1033300199999 SUBENT 10333002 20201113 14731033300200001 BIB 9 45 1033300200002 REACTION (92-U-235(N,F),,SIG) 1033300200003 INC-SOURCE (P-LI7) 1033300200004 SAMPLE Sample S-4pi-400: 1033300200005 400 ug/cm2 thick, 19.63+/-0.1 cm2 area, 1033300200006 electrospraying on vyns, 1033300200007 7.811+/-0.039 mg 235U 1033300200008 (92-U-235,ENR=0.99505) 1033300200009 (92-U-234,ENR=0.00168) 1033300200010 (92-U-236,ENR=0.00026) 1033300200011 (92-U-238,ENR=0.00301) 1033300200012 METHOD Absolute measurement 1033300200013 (TOF) 173-cm flight path 1033300200014 DETECTOR (SCIN) 4pi-gas scintillation counter (4pi-GSC) for 1033300200015 fission fragment detection 1033300200016 (SCIN) Liquid scintillator (large BND), 1033300200017 26 cm diam., 35.5 cm length for neutron 1033300200018 detection 1033300200019 CORRECTION Corrected for 1033300200020 - attenuation in air (3.0%) 1033300200021 - second neutron group (0.8%) 1033300200022 - attenuation in fission chamber (0.7%) 1033300200023 - inscatter from fission chamber (0.5%) 1033300200024 - fission in non-235U isotopes (0.3%) 1033300200025 - BND efficiency (3.3%) 1033300200026 - collimator transmission (0.5%) 1033300200027 - energy dependence of fission efficiency (0.3%) 1033300200028 - fission counting efficiency (5.1%) 1033300200029 ERR-ANALYS (ERR-T) Total uncertainty (2.2%)1033300200030 (ERR-S) statistical uncertainty of count rates (1.4%)1033300200031 (ERR-1) attenuation in air (0.3%)1033300200032 (ERR-2) second neutron group (0.1%)1033300200033 (ERR-3) attenuation in fission chamber (0.1%)1033300200034 (ERR-4) inscatter from fission chamber (0.1%)1033300200035 (ERR-5) fission in non-235U isotopes (0.1%)1033300200036 (ERR-6) BND efficiency (1.0%)1033300200037 (ERR-10) collimator transmission (0.2%)1033300200038 (ERR-13) energy dependence of fission efficiency (0.1%)1033300200039 (ERR-14) fission counting efficiency (1.0%)1033300200040 (ERR-15) mass assignment (0.5%)1033300200041 (ERR-16) BG subtraction, count rate integration (0.5%)1033300200042 (ERR-17) geometrical factors (0.5%)1033300200043 STATUS (TABLE) Text (p.385) of Nucl.Sci.Eng.53(1974)370 1033300200044 (SPSDD,10333009) Renormalized by 0.2% for 235U mass 1033300200045 HISTORY (20020926A) Energy error added to data. 1033300200046 (20201113A) On. ERR-ANALYS updated. Superseded. 1033300200047 ENDBIB 45 0 1033300200048 COMMON 12 6 1033300200049 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 1033300200050 ERR-10 ERR-13 ERR-14 ERR-15 ERR-16 ERR-17 1033300200051 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033300200052 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033300200053 1.4 0.1 0.1 0.1 0.1 1.0 1033300200054 0.2 0.1 1.0 0.5 0.5 0.5 1033300200055 ENDCOMMON 6 0 1033300200056 DATA 5 1 1033300200057 EN EN-ERR DATA ERR-T ERR-S 1033300200058 KEV KEV MB PER-CENT PER-CENT 1033300200059 3500. 3. 1198. 2.2 1.4 1033300200060 ENDDATA 3 0 1033300200061 ENDSUBENT 60 0 1033300299999 SUBENT 10333003 20201113 14731033300300001 BIB 10 55 1033300300002 REACTION (92-U-235(N,F),,SIG) 1033300300003 INC-SOURCE (P-LI7) 1033300300004 SAMPLE Sample S-2pi-4: 1033300300005 100 ug/cm2 thick, 5 cm2 area, 1033300300006 evaporated on stainless steel (0.025 cm), 1033300300007 0.3856+/-0.0019 mg 235U 1033300300008 (92-U-235,ENR=0.9340) 1033300300009 (92-U-234,ENR=0.00843) 1033300300010 (92-U-236,ENR=0.00317) 1033300300011 (92-U-238,ENR=0.05436) 1033300300012 REL-REF (M,,W.P.Poenitz+,R,ANL-NDM-84,1983) 1033300300013 235U sample mass determination 1033300300014 METHOD Absolute measurement 1033300300015 (TOF) 1033300300016 DETECTOR (IOCH) fast-timing Ionization chamber (FT-IC) for 1033300300017 fission fragment detection 1033300300018 (SCIN) Black neutron detector (small BND), 1033300300019 17.6 cm diam., 30 cm length for neutron detection 1033300300020 CORRECTION Corrected for 1033300300021 - attenuation in air (7.9%) 1033300300022 - second neutron group (1.7%) 1033300300023 - attenuation in fission chamber (2.0%) 1033300300024 - inscatter from fission chamber (0.8%) 1033300300025 - fission in non-235U isotopes (0.9%) 1033300300026 - BND efficiency (4.0%) 1033300300027 - angular distribution of source reaction (0.5%) 1033300300028 - neutron return to BND (0.5%) 1033300300029 - BND entrance window (0.3%) 1033300300030 - collimator transmission (0.8%) 1033300300031 - inscatter from tantalum cup (0.7%) 1033300300032 - inelastic scattering in backing (0.1%) 1033300300033 - energy dependence of fission efficiency (0.2%) 1033300300034 - fission counting efficiency (1.9%) 1033300300035 ERR-ANALYS (ERR-T) Total uncertainty (2.4%)1033300300036 (ERR-S) statistical uncertainty of count rates (1.2%)1033300300037 (ERR-1) attenuation in air (0.8%)1033300300038 (ERR-2) second neutron group (0.2%)1033300300039 (ERR-3) attenuation in fission chamber (0.2%)1033300300040 (ERR-4) inscatter from fission chamber (0.4%)1033300300041 (ERR-5) fission in non-235U isotopes (0.1%)1033300300042 (ERR-6) BND efficiency (1.0%)1033300300043 (ERR-7) angular distribution of source reaction (0.1%)1033300300044 (ERR-8) neutron return to BND (0.3%)1033300300045 (ERR-9) BND entrance window (0.1%)1033300300046 (ERR-10) collimator transmission (0.2%)1033300300047 (ERR-11) inscatter from tantalum cup (0.3%)1033300300048 (ERR-12) inelastic scattering in backing (0.1%)1033300300049 (ERR-13) energy dependence of fission efficiency (0.1%)1033300300050 (ERR-14) fission counting efficiency (0.5%)1033300300051 (ERR-15) mass assignment (0.5%)1033300300052 (ERR-16) BG subtraction, count rate integration (0.5%)1033300300053 (ERR-17) geometrical factors (1.2%)1033300300054 STATUS (TABLE) Text (p.385) of Nucl.Sci.Eng.53(1974)370 1033300300055 (SPSDD,10333010) Renormalized by 1.1% for 235U mass 1033300300056 HISTORY (20201113A) On. ERR-ANALYS updated. Superseded. 1033300300057 ENDBIB 55 0 1033300300058 COMMON 17 9 1033300300059 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 1033300300060 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 1033300300061 ERR-13 ERR-14 ERR-15 ERR-16 ERR-17 1033300300062 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033300300063 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033300300064 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033300300065 0.8 0.2 0.2 0.4 0.1 1.0 1033300300066 0.1 0.3 0.1 0.2 0.3 0.1 1033300300067 0.1 0.5 0.5 0.5 1.2 1033300300068 ENDCOMMON 9 0 1033300300069 DATA 5 1 1033300300070 EN EN-ERR DATA ERR-T ERR-S 1033300300071 KEV KEV MB PER-CENT PER-CENT 1033300300072 800. 3. 1134. 2.4 1.2 1033300300073 ENDDATA 3 0 1033300300074 ENDSUBENT 73 0 1033300399999 SUBENT 10333004 20201113 14731033300400001 BIB 9 34 1033300400002 REACTION (92-U-235(N,F),,SIG) 1033300400003 INC-SOURCE 51V(p,n)51Cr 1033300400004 SAMPLE Sample AG-1: 1033300400005 55 ug/cm2 thick, 184.1+/-1.1 cm2 area, 1033300400006 electroplating on Ag (0.025 cm thick) 1033300400007 10.23+/-0.20 mg 235U 1033300400008 235U/234U/236U/238U: 99.86%/0.028%/0.068%/0.054% 1033300400009 Sample AG-10: 1033300400010 75 ug/cm2 thick, 186.9+/-1.1 cm2 area, 1033300400011 electroplating on Ag (0.025 cm thick) 1033300400012 13.91+/-0.28 mg 235U 1033300400013 235U/234U/236U/238U: 99.564%/0.047%/0.311%/0.078% 1033300400014 Sample AG-20: 1033300400015 60 ug/cm2 thick, 189.6+/-1.1 cm2 area, 1033300400016 electroplating on Ag (0.050 cm thick) 1033300400017 11.24+/-0.28 mg 235U 1033300400018 235U/234U/236U/238U: 99.564%/0.047%/0.311%/0.078% 1033300400019 METHOD Associated activity technique 1033300400020 DETECTOR (FISCH) Spherical ionization chambers (SS-IC-1,2,3) for1033300400021 fission fragment detection 1033300400022 (NAICR) NaI(Tl) detector for 51Cr gamma detection 1033300400023 CORRECTION Corrected for neutrons scattered from 1033300400024 - inner sphere (2.5-4.2%) 1033300400025 - outer sphere (0.3-0.6%) 1033300400026 - teflon roads (0.4%) 1033300400027 - teflon rings (0.7%) 1033300400028 - air-cooling tube (0.1%) 1033300400029 - target construction (0.5%) 1033300400030 - inelastic scattering (0.4%) 1033300400031 Total correction: 4.9-6.9%. 1033300400032 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1033300400033 STATUS (TABLE) Table XI of Nucl.Sci.Eng.53(1974)370 1033300400034 (SPSDD,10333011) 1033300400035 HISTORY (20201113A) On. EN-RSL -> EN-RSL-HW. Superseded. 1033300400036 ENDBIB 34 0 1033300400037 NOCOMMON 0 0 1033300400038 DATA 4 6 1033300400039 EN EN-RSL-HW DATA DATA-ERR 1033300400040 KEV KEV MB MB 1033300400041 448. 60. 1220. 44. 1033300400042 552. 60. 1121. 43. 1033300400043 553. 50. 1110. 41. 1033300400044 600. 59. 1116. 41. 1033300400045 602. 52. 1100. 40. 1033300400046 644. 65. 1101. 42. 1033300400047 ENDDATA 8 0 1033300400048 ENDSUBENT 47 0 1033300499999 SUBENT 10333005 20201113 14731033300500001 BIB 8 27 1033300500002 REACTION (92-U-235(N,F),,SIG) 1033300500003 INC-SOURCE (P-LI7) 1033300500004 SAMPLE Sample S-4pi-400: 1033300500005 400 ug/cm2 thick, 19.63+/-0.1 cm2 area, 1033300500006 electrospraying on vyns, 1033300500007 7.811+/-0.039 mg 235U 1033300500008 (92-U-235,ENR=0.99505) 1033300500009 (92-U-234,ENR=0.00168) 1033300500010 (92-U-236,ENR=0.00026) 1033300500011 (92-U-238,ENR=0.00301) 1033300500012 METHOD Absolute measurement with vanadium bath calibrated 1033300500013 with a 252Cf source 1033300500014 DETECTOR (SCIN) 4pi-gas scintillation counter (4pi-GSC) for 1033300500015 fission fragment detection 1033300500016 (NAICR) for detection of n-p capture gamma (2.2 MeV) 1033300500017 ERR-ANALYS (ERR-T) Total uncertainty due to 1033300500018 (ERR-S) statistics for fission counting (2.3%) 1033300500019 (ERR-1) calibration of vanadium bath (2.3%) 1033300500020 (ERR-2) fission-counting efficiency (1.0%) 1033300500021 (ERR-3) uranium mass (0.5%) 1033300500022 (ERR-4) homogeneity of uranium distribution (1.0%) 1033300500023 (ERR-5) correction (0.5%) 1033300500024 STATUS (TABLE) Text (p.388) of Nucl.Sci.Eng.53(1974)370 1033300500025 (SPSDD,10333012) Renormalized by 0.2% for 235U mass, 1033300500026 0.9% for 252Cf nu-bar 1033300500027 HISTORY (20020926A) Energy error added to data. 1033300500028 (20201113A) On. ERR-ANALYS updated. Superseded. 1033300500029 ENDBIB 27 0 1033300500030 COMMON 5 3 1033300500031 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1033300500032 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033300500033 2.3 1.0 0.5 1.0 0.5 1033300500034 ENDCOMMON 3 0 1033300500035 DATA 5 1 1033300500036 EN EN-ERR DATA ERR-T ERR-S 1033300500037 KEV KEV MB MB PER-CENT 1033300500038 498. 3. 1151. 42. 2.3 1033300500039 ENDDATA 3 0 1033300500040 ENDSUBENT 39 0 1033300599999 SUBENT 10333006 20201113 14731033300600001 BIB 10 47 1033300600002 REACTION (92-U-235(N,F),,SIG) 1033300600003 MONITOR (92-U-235(N,F),,SIG) 1033300600004 Shape normalized at 800 keV to absolute measurement 1033300600005 INC-SOURCE (P-LI7) 1033300600006 SAMPLE Sample S-2pi-2: 1033300600007 500 ug/cm2 thick, 20 cm2 area, 1033300600008 electroplating on Mo (0.013 cm thick) 1033300600009 (92-U-235,ENR=0.9841) 1033300600010 (92-U-234,ENR=0.0103) 1033300600011 (92-U-236,ENR=0.00457) 1033300600012 (92-U-238,ENR=0.00103) 1033300600013 METHOD (TOF) 1033300600014 DETECTOR (FISCH) Fast-timing ionization chamber (FT-IC) for 1033300600015 fission fragment detection 1033300600016 (SCIN) Black neutron detector (small BND), 1033300600017 17.6 cm diam., 30 cm length for neutron detection 1033300600018 CORRECTION Corrected for 1033300600019 - attenuation in air (5-12%) 1033300600020 - attenuation in chamber (1.5-2.5%) 1033300600021 - second neutron group (0-13%) 1033300600022 - inscatter from fission counter (1.4-2.5%) 1033300600023 - inscatter from target (0.6-1.0%) 1033300600024 - inelastic scattering in fission counter (0.0-0.2%) 1033300600025 - fission in non-235U isotopes (0.2-1.5%) 1033300600026 - angular distribution of source reaction (1.0-2.5%) 1033300600027 - energy dependence of fission efficiency (0.1-0.5%) 1033300600028 - BND efficiency (3.4-11.5%) 1033300600029 - backscatter to BND (0.0-1.5%) 1033300600030 - collimator transmission (0.5-1.5%) 1033300600031 ERR-ANALYS (ERR-T) Uncertainty at 68% confidence level and do not 1033300600032 contain the uncertainty of the normalization 1033300600033 (ERR-1,0.5,1.2) attenuation in air 1033300600034 (ERR-2,0.2,0.3) attenuation in chamber 1033300600035 (ERR-3,0.0,1.0) second neutron group 1033300600036 (ERR-4,0.3,0.5) inscatter from fission counter 1033300600037 (ERR-5,0.3,0.5) inscatter from target 1033300600038 (ERR-6) inelastic scatt. in fission counter 1033300600039 (ERR-7,0.1,0.2) fission in non-235U isotopes 1033300600040 (ERR-8,0.2,0.5) angular distribut. of source reaction 1033300600041 (ERR-9,0.1,0.2) energy dependence of fiss. efficiency 1033300600042 (ERR-10,1.0,2.0) BND efficiency 1033300600043 (ERR-11,0.2,0.5) backscatter to BND 1033300600044 (ERR-12,0.2,0.3) collimator transmission 1033300600045 STATUS (TABLE) Table V of Nucl.Sci.Eng.53(1974)370 1033300600046 (DEP,10333003) 800 keV absolute measurement 1033300600047 (SPSDD,10333013) Error budget added, some points merged1033300600048 HISTORY (20201113A) On. Partial uncertainties coded. 1033300600049 ENDBIB 47 0 1033300600050 COMMON 4 3 1033300600051 EN-ERR ERR-6 EN-NRM MONIT 1033300600052 KEV PER-CENT KEV MB 1033300600053 3. 0.1 799. 1134. 1033300600054 ENDCOMMON 3 0 1033300600055 DATA 4 45 1033300600056 EN EN-RSL-HW DATA ERR-T 1033300600057 KEV KEV MB MB 1033300600058 399. 30. 1223. 44. 1033300600059 499. 30. 1164. 21. 1033300600060 600. 28. 1107. 18. 1033300600061 685. 27. 1136. 20. 1033300600062 799. 27. 1134. 21. 1033300600063 847. 12. 1115. 22. 1033300600064 867. 12. 1156. 24. 1033300600065 887. 12. 1147. 25. 1033300600066 897. 12. 1157. 27. 1033300600067 917. 12. 1174. 24. 1033300600068 947. 12. 1220. 27. 1033300600069 966. 12. 1217. 28. 1033300600070 997. 12. 1194. 30. 1033300600071 1017. 12. 1190. 33. 1033300600072 1047. 12. 1170. 30. 1033300600073 1100. 25. 1200. 26. 1033300600074 1185. 23. 1205. 29. 1033300600075 1401. 23. 1196. 30. 1033300600076 1491. 23. 1208. 31. 1033300600077 1492. 23. 1219. 30. 1033300600078 1550. 23. 1225. 32. 1033300600079 1601. 22. 1233. 32. 1033300600080 1601. 22. 1238. 32. 1033300600081 1650. 22. 1261. 33. 1033300600082 1700. 22. 1260. 33. 1033300600083 1702. 22. 1249. 32. 1033300600084 1750. 22. 1258. 33. 1033300600085 1801. 21. 1266. 33. 1033300600086 1801. 21. 1232. 32. 1033300600087 1850. 21. 1283. 33. 1033300600088 1903. 21. 1282. 33. 1033300600089 1951. 21. 1284. 33. 1033300600090 2000. 21. 1285. 33. 1033300600091 2012. 20. 1300. 32. 1033300600092 2053. 20. 1285. 33. 1033300600093 2093. 20. 1268. 32. 1033300600094 2093. 20. 1261. 33. 1033300600095 2133. 20. 1272. 33. 1033300600096 2202. 20. 1290. 32. 1033300600097 2203. 20. 1286. 35. 1033300600098 2253. 20. 1259. 34. 1033300600099 2302. 20. 1281. 34. 1033300600100 2403. 19. 1315. 32. 1033300600101 2703. 18. 1243. 32. 1033300600102 2803. 18. 1233. 31. 1033300600103 ENDDATA 47 0 1033300600104 ENDSUBENT 103 0 1033300699999 SUBENT 10333007 20201113 14731033300700001 BIB 11 35 1033300700002 REACTION (92-U-235(N,F),,SIG) 1033300700003 MONITOR (92-U-235(N,F),,SIG) 1033300700004 Shape normalized at 498 keV to absolute measurement 1033300700005 INC-SOURCE (P-LI7) 1033300700006 SAMPLE Sample S-2pi-1: 1033300700007 400 ug/cm2 thick, 20 cm2 area, 1033300700008 electroplating on Mo (0.013 cm thick) 1033300700009 (92-U-235,ENR=0.9986) 1033300700010 (92-U-234,ENR=0.00028) 1033300700011 (92-U-236,ENR=0.00068) 1033300700012 (92-U-238,ENR=0.00054) 1033300700013 METHOD (TOF) 1033300700014 DETECTOR (SCIN) 2pi-gas scintillation counter (2pi-GSC) for 1033300700015 fission fragment detection 1033300700016 (NAICR) Grey neutron detector (GND) for detection 1033300700017 of capture gamma-rays originated from neutron captures1033300700018 by moderator. 1033300700019 FLAG (1.) Small paraffin cube (P) 1033300700020 (2.) Large 400-l container with pure water (W) 1033300700021 (3.) Large 400-l container with MnSO4 solution (Mn) 1033300700022 (4.) Large 400-l container with V(SO)4 solution (V) 1033300700023 CORRECTION Corrected for 1033300700024 - attenuation in air 1033300700025 - attenuation in chamber 1033300700026 - inscatter from target and backing 1033300700027 - second neutron group 1033300700028 - inscatter from collimator 1033300700029 ERR-ANALYS (ERR-T) Data error given includes energy-dependence of 1033300700030 neutron detector efficiency, and 1033300700031 (ERR-S,1.5,3.5) statistical uncertainty (1.5-3.5%) 1033300700032 (ERR-1,0.5,2.0) correction (0.5-2.0%) 1033300700033 STATUS (TABLE) Table VI of Nucl.Sci.Eng.53(1974)370 1033300700034 (DEP,10333005) 498 keV absolute measurement 1033300700035 (SPSDD,10333014) 1033300700036 HISTORY (20201113A) On. Partial uncertainties coded. 1033300700037 ENDBIB 35 0 1033300700038 COMMON 2 3 1033300700039 EN-NRM MONIT 1033300700040 KEV MB 1033300700041 498. 1151. 1033300700042 ENDCOMMON 3 0 1033300700043 DATA 5 74 1033300700044 EN EN-RSL-HW DATA ERR-T FLAG 1033300700045 KEV KEV MB MB NO-DIM 1033300700046 35. 3. 2017. 76. 2. 1033300700047 47. 5. 1824. 60. 2. 1033300700048 68. 5. 1690. 45. 2. 1033300700049 84. 5. 1579. 38. 2. 1033300700050 97. 8. 1579. 35. 2. 1033300700051 121. 8. 1502. 31. 2. 1033300700052 141. 15. 1426. 21. 1. 1033300700053 144. 23. 1392. 33. 2. 1033300700054 174. 10. 1379. 28. 2. 1033300700055 179. 25. 1362. 18. 1. 1033300700056 194. 23. 1384. 42. 2. 1033300700057 218. 18. 1348. 46. 2. 1033300700058 231. 25. 1326. 18. 1. 1033300700059 273. 35. 1358. 40. 2. 1033300700060 282. 25. 1290. 20. 1. 1033300700061 297. 10. 1259. 29. 2. 1033300700062 393. 25. 1222. 21. 1. 1033300700063 399. 35. 1161. 28. 2. 1033300700064 427. 29. 1214. 27. 2. 1033300700065 434. 15. 1144. 35. 2. 1033300700066 502. 31. 1132. 21. 2. 1033300700067 509. 16. 1128. 21. 3. 1033300700068 514. 26. 1139. 24. 4. 1033300700069 556. 28. 1190. 18. 2. 1033300700070 593. 25. 1154. 15. 1. 1033300700071 604. 30. 1125. 18. 2. 1033300700072 647. 27. 1113. 17. 2. 1033300700073 692. 25. 1104. 18. 2. 1033300700074 706. 29. 1108. 24. 2. 1033300700075 711. 24. 1099. 24. 3. 1033300700076 757. 24. 1119. 20. 2. 1033300700077 807. 28. 1078. 23. 2. 1033300700078 809. 24. 1126. 25. 3. 1033300700079 861. 23. 1158. 27. 3. 1033300700080 887. 28. 1175. 26. 2. 1033300700081 897. 25. 1172. 18. 1. 1033300700082 903. 27. 1114. 24. 2. 1033300700083 944. 45. 1252. 22. 2. 1033300700084 957. 27. 1238. 28. 2. 1033300700085 960. 23. 1218. 31. 3. 1033300700086 997. 25. 1212. 24. 1. 1033300700087 1036. 51. 1225. 26. 2. 1033300700088 1041. 45. 1195. 26. 3. 1033300700089 1103. 44. 1198. 23. 2. 1033300700090 1109. 43. 1195. 27. 4. 1033300700091 1194. 25. 1246. 24. 1. 1033300700092 1199. 64. 1217. 26. 2. 1033300700093 1227. 42. 1239. 27. 3. 1033300700094 1278. 41. 1205. 21. 2. 1033300700095 1300. 43. 1154. 26. 4. 1033300700096 1406. 41. 1244. 28. 4. 1033300700097 1414. 48. 1241. 28. 2. 1033300700098 1421. 40. 1263. 28. 3. 1033300700099 1498. 40. 1225. 28. 4. 1033300700100 1515. 40. 1294. 26. 2. 1033300700101 1605. 55. 1299. 29. 2. 1033300700102 1704. 74. 1286. 28. 4. 1033300700103 1818. 73. 1285. 29. 4. 1033300700104 1819. 44. 1302. 32. 2. 1033300700105 1823. 35. 1279. 29. 3. 1033300700106 1911. 33. 1294. 33. 3. 1033300700107 1970. 72. 1338. 31. 4. 1033300700108 2007. 70. 1344. 33. 4. 1033300700109 2010. 53. 1397. 32. 2. 1033300700110 2027. 28. 1363. 32. 3. 1033300700111 2107. 68. 1338. 35. 4. 1033300700112 2204. 67. 1337. 36. 4. 1033300700113 2304. 66. 1354. 37. 4. 1033300700114 2499. 64. 1250. 36. 4. 1033300700115 2802. 61. 1252. 39. 4. 1033300700116 2820. 45. 1315. 41. 2. 1033300700117 2837. 30. 1315. 34. 3. 1033300700118 3000. 58. 1234. 40. 4. 1033300700119 3500. 53. 1192. 45. 4. 1033300700120 ENDDATA 76 0 1033300700121 ENDSUBENT 120 0 1033300799999 SUBENT 10333008 20201113 14731033300800001 BIB 9 25 1033300800002 REACTION (92-U-235(N,F),,SIG) 1033300800003 MONITOR ((MONIT1)3-LI-6(N,T)2-HE-4,,SIG) 1033300800004 for shape normalization (3000 mb at 250 keV) 1033300800005 ((MONIT2)92-U-235(N,F),,SIG) 1033300800006 for absolute normalization at 250 keV 1033300800007 INC-SOURCE (P-LI7) 1033300800008 SAMPLE Sample S-2pi-5: 1033300800009 400 ug/cm2 thick, 11 cm2 area, 1033300800010 (92-U-235,ENR=0.9837) 1033300800011 (92-U-234,ENR=0.00027) 1033300800012 (92-U-236,ENR=0.00056) 1033300800013 (92-U-238,ENR=0.0154) 1033300800014 METHOD (TOF) 1033300800015 DETECTOR (SCIN) 2pi-gas scintillation counter (2pi-GSC) for 1033300800016 fission fragment detection 1033300800017 (GLASD) Li-glass (0.1 cm thick, 3.8 cm diam.) detector 1033300800018 for neutrons 1033300800019 ERR-ANALYS (ERR-T) Major contributions to data error: 1033300800020 (ERR-S) statistics (1.5-1.8%) 1033300800021 (ERR-1) normalization procedure (2.0%) 1033300800022 STATUS (TABLE) Table VII of Nucl.Sci.Eng.53(1974)370 1033300800023 (PENTZ) Statistical uncertainty from GMA #562 1033300800024 (DEP,10333007) 250 keV normalization point 1033300800025 (COREL,10333015) 235U(n,f)/6Li(n,t) ratio renormalized 1033300800026 HISTORY (20201113A) On. ERR-S taken from GMA #562. 1033300800027 ENDBIB 25 0 1033300800028 COMMON 3 3 1033300800029 EN-NRM2 MONIT2 ERR-1 1033300800030 KEV MB PER-CENT 1033300800031 250. 1320. 2.0 1033300800032 ENDCOMMON 3 0 1033300800033 DATA 6 9 1033300800034 EN EN-RSL-HW DATA ERR-T ERR-S MONIT1 1033300800035 KEV KEV MB MB PER-CENT MB 1033300800036 34.5 5. 1996. 60. 1.8 820. 1033300800037 42. 5. 1856. 54. 1.8 750. 1033300800038 45.5 5. 1866. 54. 1.7 725. 1033300800039 60. 5. 1795. 52. 1.7 665. 1033300800040 75. 5. 1737. 51. 1.6 635. 1033300800041 83. 5. 1629. 47. 1.6 630. 1033300800042 90. 5. 1579. 44. 1.5 625. 1033300800043 101. 5. 1589. 44. 1.5 625. 1033300800044 109. 5. 1574. 44. 1.5 630. 1033300800045 ENDDATA 11 0 1033300800046 ENDSUBENT 45 0 1033300899999 SUBENT 10333009 20201113 14731033300900001 BIB 8 30 1033300900002 REACTION (92-U-235(N,F),,SIG) 1033300900003 INC-SOURCE (P-LI7) 1033300900004 SAMPLE Sample S-4pi-400: 1033300900005 400 ug/cm2 thick, 19.63+/-0.1 cm2 area, 1033300900006 electrospraying on vyns, 1033300900007 7.811+/-0.039 mg 235U 1033300900008 (92-U-235,ENR=0.99505) 1033300900009 (92-U-234,ENR=0.00168) 1033300900010 (92-U-236,ENR=0.00026) 1033300900011 (92-U-238,ENR=0.00301) 1033300900012 METHOD Absolute measurement 1033300900013 (TOF) 173-cm flight path 1033300900014 DETECTOR (SCIN) 4pi-gas scintillation counter (4pi-GSC) for 1033300900015 fission fragment detection 1033300900016 (SCIN) Liquid scintillator (large BND), 1033300900017 26 cm diam., 35.5 cm length for neutron 1033300900018 detection 1033300900019 ERR-ANALYS (ERR-T) Total uncertainty (2.4%) 1033300900020 (ERR-S) statistical uncertainty (1.4%) 1033300900021 (ERR-1) 235U mass (1.0%) 1033300900022 (ERR-2) geometry (0.5%) 1033300900023 (ERR-3) background (0.5%) 1033300900024 (ERR-4) air attenuation (0.3%) 1033300900025 (ERR-5) BND detection efficiency (1.0%) 1033300900026 (ERR-6) inscatter from fission chamber +non U5 (0.2%) 1033300900027 (ERR-7) fission detection efficiency (1.0%) 1033300900028 (ERR-8) collimator transmission (0.2%) 1033300900029 (ERR-9) inscatter from target (0.2%) 1033300900030 STATUS (PENTZ) GMA input #558 1033300900031 HISTORY (20201113C) On 1033300900032 ENDBIB 30 0 1033300900033 COMMON 9 6 1033300900034 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 1033300900035 ERR-7 ERR-8 ERR-9 1033300900036 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033300900037 PER-CENT PER-CENT PER-CENT 1033300900038 1.0 0.5 0.5 0.3 1.0 0.2 1033300900039 1.0 0.2 0.2 1033300900040 ENDCOMMON 6 0 1033300900041 DATA 6 1 1033300900042 EN EN-ERR EN-RSL-HW DATA ERR-T ERR-S 1033300900043 KEV PER-CENT PER-CENT B PER-CENT PER-CENT 1033300900044 3500. 0.3 1.6 1.196 2.4 1.4 1033300900045 ENDDATA 3 0 1033300900046 ENDSUBENT 45 0 1033300999999 SUBENT 10333010 20201113 14731033301000001 BIB 8 30 1033301000002 REACTION (92-U-235(N,F),,SIG) 1033301000003 INC-SOURCE (P-LI7) 1033301000004 SAMPLE Sample S-2pi-4: 1033301000005 100 ug/cm2 thick, 5 cm2 area, 1033301000006 evaporated on stainless steel (0.025 cm), 1033301000007 0.3856+/-0.0019 mg 235U 1033301000008 (92-U-235,ENR=0.9340) 1033301000009 (92-U-234,ENR=0.00843) 1033301000010 (92-U-236,ENR=0.00317) 1033301000011 (92-U-238,ENR=0.05436) 1033301000012 METHOD Absolute measurement 1033301000013 (TOF) 1033301000014 DETECTOR (IOCH) fast-timing Ionization chamber (FT-IC) for 1033301000015 fission fragment detection 1033301000016 (SCIN) Black neutron detector (small BND), 1033301000017 17.6 cm diam., 30 cm length for neutron detection 1033301000018 ERR-ANALYS (ERR-T) Total uncertainty (2.5%) 1033301000019 (ERR-S) statistical uncertainty (1.2%) 1033301000020 (ERR-1) 235U mass (0.3%) 1033301000021 (ERR-2) geometry (1.2%) 1033301000022 (ERR-3) background (0.5%) 1033301000023 (ERR-4) air attenuation (0.8%) 1033301000024 (ERR-5) BND detection efficiency (1.1%) 1033301000025 (ERR-6) fission counter scatt. and attenuation (0.5%) 1033301000026 (ERR-7) fission detection efficiency (0.5%) 1033301000027 (ERR-8) collimator transmission (0.3%) 1033301000028 (ERR-9) inscatter from target (0.3%) 1033301000029 (ERR-10) second neutron group (0.8%) 1033301000030 STATUS (PENTZ) GMA input #557 1033301000031 HISTORY (20201113C) On 1033301000032 ENDBIB 30 0 1033301000033 COMMON 10 6 1033301000034 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 1033301000035 ERR-7 ERR-8 ERR-9 ERR-10 1033301000036 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033301000037 PER-CENT PER-CENT PER-CENT PER-CENT 1033301000038 0.3 1.2 0.5 0.8 1.1 0.5 1033301000039 0.5 0.3 0.3 0.8 1033301000040 ENDCOMMON 6 0 1033301000041 DATA 5 1 1033301000042 EN EN-ERR DATA ERR-T ERR-S 1033301000043 KEV PER-CENT B PER-CENT PER-CENT 1033301000044 800. 0.6 1.122 2.5 1.2 1033301000045 ENDDATA 3 0 1033301000046 ENDSUBENT 45 0 1033301099999 SUBENT 10333011 20201113 14731033301100001 BIB 8 31 1033301100002 REACTION (92-U-235(N,F),,SIG) 1033301100003 INC-SOURCE 51V(p,n)51Cr 1033301100004 SAMPLE Sample AG-1: 1033301100005 55 ug/cm2 thick, 184.1+/-1.1 cm2 area, 1033301100006 electroplating on Ag (0.025 cm thick) 1033301100007 10.23+/-0.20 mg 235U 1033301100008 235U/234U/236U/238U: 99.86%/0.028%/0.068%/0.054% 1033301100009 Sample AG-10: 1033301100010 75 ug/cm2 thick, 186.9+/-1.1 cm2 area, 1033301100011 electroplating on Ag (0.025 cm thick) 1033301100012 13.91+/-0.28 mg 235U 1033301100013 235U/234U/236U/238U: 99.564%/0.047%/0.311%/0.078% 1033301100014 Sample AG-20: 1033301100015 60 ug/cm2 thick, 189.6+/-1.1 cm2 area, 1033301100016 electroplating on Ag (0.050 cm thick) 1033301100017 11.24+/-0.28 mg 235U 1033301100018 235U/234U/236U/238U: 99.564%/0.047%/0.311%/0.078% 1033301100019 METHOD Associated activity technique 1033301100020 DETECTOR (FISCH) Spherical ionization chambers (SS-IC-1,2,3) for1033301100021 fission fragment detection 1033301100022 (NAICR) NaI(Tl) detector for 51Cr gamma detection 1033301100023 ERR-ANALYS (ERR-T) Total uncertainty (3.6-3.8%) 1033301100024 (ERR-S,,,U) statistical uncertainty (2.2-2.6%) 1033301100025 (ERR-1,,,F) 235U mass (2.0%) 1033301100026 (ERR-2,,,F) associated activity calibration (0.8%) 1033301100027 (ERR-3,,,P) neutron scattering (1.0%) 1033301100028 (ERR-4,,,P) background (0.5%) 1033301100029 (ERR-5,,,P) fission detection efficiency (1.0%) 1033301100030 (ERR-6,,,P) association activity counting (1.0%) 1033301100031 STATUS (PENTZ) GMA input #561 1033301100032 HISTORY (20201113C) On 1033301100033 ENDBIB 31 0 1033301100034 COMMON 6 3 1033301100035 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 1033301100036 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033301100037 2.0 0.8 1.0 0.5 1.0 1.0 1033301100038 ENDCOMMON 3 0 1033301100039 DATA 5 6 1033301100040 EN EN-RSL-HW DATA ERR-T ERR-S 1033301100041 KEV PER-CENT B PER-CENT PER-CENT 1033301100042 448. 13.4 1.220 3.6 2.2 1033301100043 552. 10.9 1.121 3.8 2.6 1033301100044 553. 9.0 1.110 3.7 2.4 1033301100045 600. 9.8 1.116 3.7 2.4 1033301100046 602. 8.6 1.100 3.6 2.3 1033301100047 644. 10.1 1.101 3.7 2.4 1033301100048 ENDDATA 8 0 1033301100049 ENDSUBENT 48 0 1033301199999 SUBENT 10333012 20201113 14731033301200001 BIB 8 26 1033301200002 REACTION (92-U-235(N,F),,SIG) 1033301200003 INC-SOURCE (P-LI7) 1033301200004 SAMPLE Sample S-4pi-400: 1033301200005 400 ug/cm2 thick, 19.63+/-0.1 cm2 area, 1033301200006 electrospraying on vyns, 1033301200007 7.811+/-0.039 mg 235U 1033301200008 (92-U-235,ENR=0.99505) 1033301200009 (92-U-234,ENR=0.00168) 1033301200010 (92-U-236,ENR=0.00026) 1033301200011 (92-U-238,ENR=0.00301) 1033301200012 METHOD Absolute measurement with vanadium bath calibrated 1033301200013 with a 252Cf source 1033301200014 DETECTOR (SCIN) 4pi-gas scintillation counter (4pi-GSC) for 1033301200015 fission fragment detection 1033301200016 (NAICR) for detection of n-p capture gamma (2.2 MeV) 1033301200017 ERR-ANALYS (ERR-T) Total uncertainty (3.9%) 1033301200018 (ERR-S) statistics for fission counting (2.3%) 1033301200019 (ERR-1) calibration of vanadium bath (2.3%) 1033301200020 (ERR-2) 235U mass (1.0%) 1033301200021 (ERR-3) fission detection efficiency (1.0%) 1033301200022 (ERR-4) homogeneity of uranium distribution (1.0%) 1033301200023 (ERR-5) correction (0.5%) 1033301200024 (ERR-6) background (1.0%) 1033301200025 (ERR-7) inscatter from fission counter (0.2%) 1033301200026 STATUS (PENTZ) GMA input #560 1033301200027 HISTORY (20201113C) On 1033301200028 ENDBIB 26 0 1033301200029 COMMON 7 6 1033301200030 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 1033301200031 ERR-7 1033301200032 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033301200033 PER-CENT 1033301200034 2.3 1.0 1.0 1.0 0.5 1.0 1033301200035 0.2 1033301200036 ENDCOMMON 6 0 1033301200037 DATA 6 1 1033301200038 EN EN-ERR EN-RSL-HW DATA ERR-T ERR-S 1033301200039 KEV PER-CENT PER-CENT B PER-CENT PER-CENT 1033301200040 498. 1.0 5.6 1.138 3.9 2.3 1033301200041 ENDDATA 3 0 1033301200042 ENDSUBENT 41 0 1033301299999 SUBENT 10333013 20201113 14731033301300001 BIB 10 31 1033301300002 REACTION (92-U-235(N,F),,SIG) 1033301300003 MONITOR (92-U-235(N,F),,SIG) 1033301300004 Shape normalized at 800 keV to absolute measurement 1033301300005 INC-SOURCE (P-LI7) 1033301300006 SAMPLE Sample S-2pi-2: 1033301300007 500 ug/cm2 thick, 20 cm2 area, 1033301300008 electroplating on Mo (0.013 cm thick) 1033301300009 (92-U-235,ENR=0.9841) 1033301300010 (92-U-234,ENR=0.0103) 1033301300011 (92-U-236,ENR=0.00457) 1033301300012 (92-U-238,ENR=0.00103) 1033301300013 METHOD (TOF) 1033301300014 DETECTOR (FISCH) Fast-timing ionization chamber (FT-IC) for 1033301300015 fission fragment detection 1033301300016 (SCIN) Black neutron detector (small BND), 1033301300017 17.6 cm diam., 30 cm length for neutron detection 1033301300018 ERR-ANALYS (ERR-T) Total uncertainty (1.8-3.0%)1033301300019 (ERR-S,,,U) statistics for fission counting (0.8-1.0%)1033301300020 (ERR-1,,,P) BND efficiency (1.1-2.6%)1033301300021 (ERR-2,,,P) fis. detection efficiency+non-U5(0.1-0.4%)1033301300022 (ERR-3,,,P) inscatter from fission counter (0.4-0.6%)1033301300023 (ERR-4,,,P) collimator transmission (0.5-0.9%)1033301300024 (ERR-5,,,P) secondary neutrons (0.1-0.9%)1033301300025 (ERR-6,,,P) inscatter from target (0.3-0.5%)1033301300026 (ERR-7,,,P) angular dist. of source reaction(0.3-0.5%)1033301300027 COMMENT By compiler (2020-11-13): 1033301300028 This data set is treated as a shape data set in GMA 1033301300029 input (Not renormalized from 10333.006). 1033301300030 STATUS (PENTZ) GMA input #556 1033301300031 (DEP,10333003) 800 keV absolute measurement 1033301300032 HISTORY (20201113C) On 1033301300033 ENDBIB 31 0 1033301300034 COMMON 2 3 1033301300035 EN-NRM MONIT 1033301300036 KEV MB 1033301300037 799. 1134. 1033301300038 ENDCOMMON 3 0 1033301300039 DATA 13 39 1033301300040 EN EN-ERR EN-RSL-HW DATA ERR-T ERR-S 1033301300041 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 1033301300042 ERR-7 1033301300043 KEV PER-CENT PER-CENT B PER-CENT PER-CENT 1033301300044 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033301300045 PER-CENT 1033301300046 399. 1.1 7.5 1.208 3.0 1.0 1033301300047 2.6 0.1 0.6 0.5 0.1 0.5 1033301300048 0.3 1033301300049 499. 0.9 6.0 1.150 2.4 1.0 1033301300050 1.9 0.1 0.6 0.5 0.1 0.5 1033301300051 0.3 1033301300052 600. 0.7 4.7 1.094 1.8 1.0 1033301300053 1.1 0.1 0.6 0.5 0.1 0.5 1033301300054 0.3 1033301300055 685. 0.6 3.9 1.122 1.8 1.0 1033301300056 1.1 0.1 0.6 0.5 0.1 0.5 1033301300057 0.3 1033301300058 799. 0.5 3.4 1.120 1.9 1.0 1033301300059 1.1 0.2 0.6 0.9 0.1 0.5 1033301300060 0.3 1033301300061 847. 0.2 1.4 1.102 1.9 1.0 1033301300062 1.1 0.2 0.6 0.9 0.2 0.5 1033301300063 0.3 1033301300064 867. 0.2 1.4 1.142 1.9 1.0 1033301300065 1.1 0.2 0.6 0.9 0.2 0.5 1033301300066 0.3 1033301300067 887. 0.2 1.4 1.133 1.9 1.0 1033301300068 1.1 0.2 0.6 0.9 0.2 0.5 1033301300069 0.3 1033301300070 897. 0.2 1.3 1.143 1.9 1.0 1033301300071 1.1 0.2 0.6 0.9 0.2 0.5 1033301300072 0.3 1033301300073 917. 0.2 1.3 1.160 1.9 1.0 1033301300074 1.1 0.2 0.6 0.9 0.2 0.5 1033301300075 0.3 1033301300076 947. 0.2 1.3 1.205 1.9 1.0 1033301300077 1.1 0.2 0.6 0.9 0.2 0.5 1033301300078 0.3 1033301300079 966. 0.2 1.2 1.202 1.9 1.0 1033301300080 1.1 0.2 0.6 0.9 0.2 0.5 1033301300081 0.3 1033301300082 997. 0.2 1.2 1.179 1.9 1.0 1033301300083 1.1 0.2 0.6 0.9 0.2 0.5 1033301300084 0.3 1033301300085 1017. 0.2 1.2 1.176 1.9 0.9 1033301300086 1.1 0.2 0.5 0.9 0.2 0.4 1033301300087 0.4 1033301300088 1047. 0.2 1.1 1.156 1.9 0.9 1033301300089 1.1 0.2 0.5 0.9 0.2 0.4 1033301300090 0.4 1033301300091 1100. 0.3 2.3 1.185 1.8 0.9 1033301300092 1.1 0.2 0.5 0.8 0.3 0.4 1033301300093 0.4 1033301300094 1185. 0.3 1.9 1.190 1.8 0.9 1033301300095 1.1 0.2 0.5 0.8 0.3 0.4 1033301300096 0.4 1033301300097 1401. 0.2 1.6 1.181 1.8 0.9 1033301300098 1.1 0.2 0.5 0.7 0.4 0.4 1033301300099 0.4 1033301300100 1491. 0.2 1.5 1.198 1.8 0.9 1033301300101 1.1 0.2 0.5 0.7 0.4 0.4 1033301300102 0.4 1033301300103 1550. 0.2 1.5 1.210 1.8 0.9 1033301300104 1.1 0.2 0.5 0.7 0.4 0.4 1033301300105 0.4 1033301300106 1601. 0.2 1.4 1.220 1.8 0.9 1033301300107 1.1 0.2 0.5 0.7 0.5 0.4 1033301300108 0.4 1033301300109 1650. 0.2 1.3 1.245 1.8 0.9 1033301300110 1.1 0.2 0.5 0.7 0.5 0.4 1033301300111 0.4 1033301300112 1701. 0.2 1.3 1.238 1.8 0.9 1033301300113 1.1 0.3 0.5 0.7 0.5 0.4 1033301300114 0.4 1033301300115 1750. 0.2 1.3 1.242 1.8 0.9 1033301300116 1.1 0.3 0.5 0.7 0.5 0.4 1033301300117 0.4 1033301300118 1801. 0.2 1.2 1.234 1.8 0.9 1033301300119 1.1 0.3 0.5 0.7 0.5 0.4 1033301300120 0.4 1033301300121 1850. 0.2 1.1 1.268 1.8 0.9 1033301300122 1.1 0.3 0.5 0.7 0.5 0.4 1033301300123 0.4 1033301300124 1903. 0.2 1.1 1.267 1.9 0.9 1033301300125 1.1 0.3 0.5 0.7 0.6 0.4 1033301300126 0.4 1033301300127 1951. 0.2 1.1 1.269 1.9 0.9 1033301300128 1.1 0.3 0.5 0.7 0.6 0.4 1033301300129 0.4 1033301300130 2000. 0.1 1.0 1.270 1.9 0.9 1033301300131 1.1 0.3 0.5 0.7 0.6 0.4 1033301300132 0.4 1033301300133 2012. 0.1 1.0 1.285 1.9 0.9 1033301300134 1.1 0.3 0.5 0.7 0.6 0.4 1033301300135 0.4 1033301300136 2053. 0.1 1.0 1.270 1.9 0.9 1033301300137 1.2 0.3 0.5 0.7 0.6 0.4 1033301300138 0.4 1033301300139 2093. 0.1 1.0 1.249 1.9 0.9 1033301300140 1.2 0.3 0.5 0.7 0.6 0.4 1033301300141 0.4 1033301300142 2133. 0.1 0.9 1.257 2.0 0.9 1033301300143 1.2 0.3 0.5 0.7 0.7 0.4 1033301300144 0.4 1033301300145 2202. 0.1 0.9 1.273 2.0 0.9 1033301300146 1.3 0.3 0.5 0.7 0.7 0.4 1033301300147 0.4 1033301300148 2253. 0.1 0.9 1.243 2.1 0.9 1033301300149 1.4 0.3 0.5 0.8 0.7 0.4 1033301300150 0.4 1033301300151 2302. 0.1 0.9 1.266 2.1 0.9 1033301300152 1.4 0.3 0.5 0.8 0.7 0.4 1033301300153 0.4 1033301300154 2403. 0.1 0.8 1.299 2.2 0.8 1033301300155 1.5 0.3 0.4 0.8 0.8 0.3 1033301300156 0.5 1033301300157 2703. 0.1 0.7 1.228 2.5 0.8 1033301300158 1.9 0.4 0.4 0.8 0.9 0.3 1033301300159 0.5 1033301300160 2803. 0.1 0.6 1.218 2.6 0.8 1033301300161 2.0 0.4 0.4 0.8 0.9 0.3 1033301300162 0.5 1033301300163 ENDDATA 123 0 1033301300164 ENDSUBENT 163 0 1033301399999 SUBENT 10333014 20201113 14731033301400001 BIB 9 29 1033301400002 REACTION (92-U-235(N,F),,SIG) 1033301400003 INC-SOURCE (P-LI7) 1033301400004 SAMPLE Sample S-2pi-1: 1033301400005 400 ug/cm2 thick, 20 cm2 area, 1033301400006 electroplating on Mo (0.013 cm thick) 1033301400007 (92-U-235,ENR=0.9986) 1033301400008 (92-U-234,ENR=0.00028) 1033301400009 (92-U-236,ENR=0.00068) 1033301400010 (92-U-238,ENR=0.00054) 1033301400011 METHOD (TOF) 1033301400012 DETECTOR (SCIN) 2pi-gas scintillation counter (2pi-GSC) for 1033301400013 fission fragment detection 1033301400014 (NAICR) Grey neutron detector (GND) for detection 1033301400015 of capture gamma-rays originated from neutron captures1033301400016 by moderator. 1033301400017 ERR-ANALYS (ERR-T) Total uncertainty (2.0-3.8%)1033301400018 (ERR-S,,,U) statistics for fission counting (0.2-3.3%)1033301400019 (ERR-1,,,P) GND efficiency (0.5-3.5%)1033301400020 (ERR-2,,,P) neutron scatt. and attenuation (0.5-1.4%)1033301400021 (ERR-3,,,P) fission detection efficiency (0.2-0.5%)1033301400022 (ERR-4,,,P) background (0.8-1.3%)1033301400023 (ERR-5,,,P) secondary neutrons (0.2-0.5%)1033301400024 (ERR-6,,,P) integration (1.0%)1033301400025 COMMENT By compiler (2020-11-13): 1033301400026 This data set is treated as a shape data set in GMA 1033301400027 input. 1033301400028 (Renormalization factor from 007 is not a constant.) 1033301400029 STATUS (PENTZ) GMA input #559 1033301400030 HISTORY (20201113C) On 1033301400031 ENDBIB 29 0 1033301400032 COMMON 1 3 1033301400033 ERR-6 1033301400034 PER-CENT 1033301400035 1.0 1033301400036 ENDCOMMON 3 0 1033301400037 DATA 11 52 1033301400038 EN EN-ERR EN-RSL-HW DATA ERR-T ERR-S 1033301400039 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1033301400040 KEV PER-CENT PER-CENT B PER-CENT PER-CENT 1033301400041 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1033301400042 35. 1.3 8.6 2.036 3.8 3.3 1033301400043 0.5 0.8 0.5 1.3 0.2 1033301400044 47. 1.6 10.6 1.789 3.4 2.8 1033301400045 0.5 0.8 0.5 1.3 0.2 1033301400046 68. 1.1 7.4 1.669 2.8 2.0 1033301400047 0.5 0.8 0.5 1.3 0.2 1033301400048 84. 0.9 6.0 1.548 2.5 1.1 1033301400049 0.5 1.4 0.5 1.3 0.2 1033301400050 97. 1.2 8.2 1.548 2.4 1.2 1033301400051 0.5 1.0 0.5 1.3 0.2 1033301400052 121. 1.0 6.6 1.472 2.2 1.0 1033301400053 0.5 0.9 0.5 1.3 0.2 1033301400054 142.5 2.0 13.3 1.381 2.1 0.6 1033301400055 0.6 0.9 0.5 1.3 0.2 1033301400056 176.5 1.5 9.9 1.343 2.0 0.3 1033301400057 0.6 0.8 0.5 1.3 0.2 1033301400058 194. 1.8 11.9 1.357 3.1 2.4 1033301400059 0.6 0.8 0.5 1.3 0.2 1033301400060 218. 1.2 8.3 1.322 3.5 2.9 1033301400061 0.6 0.8 0.5 1.3 0.2 1033301400062 231. 1.6 10.8 1.301 2.0 0.3 1033301400063 0.6 0.8 0.5 1.3 0.2 1033301400064 273. 1.9 12.8 1.332 3.0 2.3 1033301400065 0.6 0.7 0.5 1.3 0.2 1033301400066 282. 1.3 8.9 1.265 2.0 0.3 1033301400067 0.6 0.7 0.5 1.3 0.2 1033301400068 297. 0.5 3.4 1.235 2.5 1.5 1033301400069 0.6 0.7 0.5 1.3 0.2 1033301400070 396. 1.1 7.6 1.168 2.2 0.7 1033301400071 0.7 1.0 0.5 1.2 0.2 1033301400072 430.5 0.8 5.1 1.156 2.7 1.7 1033301400073 0.7 1.1 0.5 1.2 0.2 1033301400074 508.3 0.7 4.8 1.111 2.1 0.3 1033301400075 0.7 1.0 0.5 1.2 0.2 1033301400076 556. 0.8 5.0 1.167 2.0 0.3 1033301400077 0.8 0.8 0.4 1.2 0.2 1033301400078 598.5 0.7 4.6 1.117 2.0 0.3 1033301400079 0.8 0.7 0.4 1.2 0.2 1033301400080 647. 0.6 4.2 1.092 2.0 0.3 1033301400081 0.8 0.7 0.4 1.2 0.2 1033301400082 692. 0.5 3.6 1.083 2.0 0.3 1033301400083 0.8 0.7 0.4 1.2 0.3 1033301400084 708.5 0.6 3.7 1.082 2.2 1.1 1033301400085 0.8 0.7 0.4 1.2 0.3 1033301400086 757. 0.5 3.2 1.097 2.0 0.3 1033301400087 0.9 0.7 0.4 1.2 0.3 1033301400088 808. 0.5 3.2 1.081 2.3 1.1 1033301400089 0.9 0.7 0.4 1.2 0.3 1033301400090 861. 0.4 2.7 1.136 2.4 1.4 1033301400091 0.9 0.7 0.4 1.2 0.3 1033301400092 887. 0.5 3.2 1.152 2.3 1.1 1033301400093 0.9 0.7 0.4 1.2 0.3 1033301400094 900. 0.4 2.9 1.121 2.0 0.3 1033301400095 0.9 0.7 0.4 1.2 0.3 1033301400096 944. 0.7 4.8 1.228 2.1 0.3 1033301400097 1.0 0.7 0.4 1.2 0.3 1033301400098 958.5 0.4 2.6 1.204 2.5 1.5 1033301400099 1.0 0.7 0.4 1.2 0.3 1033301400100 997. 0.4 2.5 1.189 2.1 0.5 1033301400101 1.0 0.7 0.4 1.2 0.3 1033301400102 1038. 0.7 4.6 1.187 2.2 0.9 1033301400103 1.0 0.7 0.4 1.2 0.3 1033301400104 1106. 0.6 3.9 1.173 2.2 0.7 1033301400105 1.1 0.7 0.4 1.1 0.3 1033301400106 1196. 0.6 3.7 1.207 2.1 0.2 1033301400107 1.2 0.7 0.4 1.1 0.3 1033301400108 1227. 0.5 3.4 1.215 2.2 0.8 1033301400109 1.2 0.7 0.4 1.1 0.3 1033301400110 1278. 0.5 3.2 1.182 2.2 0.3 1033301400111 1.3 0.7 0.4 1.1 0.3 1033301400112 1300. 0.5 3.3 1.132 2.3 0.9 1033301400113 1.3 0.7 0.4 1.1 0.3 1033301400114 1410. 0.5 3.2 1.218 2.3 0.7 1033301400115 1.4 0.7 0.4 1.1 0.3 1033301400116 1421. 0.4 2.8 1.239 2.3 0.5 1033301400117 1.4 0.7 0.4 1.1 0.3 1033301400118 1506. 0.4 2.7 1.235 2.3 0.3 1033301400119 1.5 0.6 0.4 1.1 0.3 1033301400120 1605. 0.5 3.4 1.274 2.3 0.3 1033301400121 1.6 0.6 0.3 1.1 0.3 1033301400122 1704. 0.6 4.3 1.261 2.4 0.3 1033301400123 1.7 0.6 0.3 1.1 0.3 1033301400124 1820. 0.4 2.8 1.264 2.4 0.3 1033301400125 1.8 0.6 0.3 1.0 0.3 1033301400126 1911. 0.3 1.7 1.269 2.5 0.5 1033301400127 1.9 0.6 0.3 1.0 0.3 1033301400128 1970. 0.6 3.7 1.312 2.6 0.3 1033301400129 2.0 0.6 0.3 1.0 0.3 1033301400130 2015. 0.4 2.5 1.341 2.6 0.3 1033301400131 2.0 0.6 0.3 1.0 0.3 1033301400132 2107. 0.5 3.2 1.312 2.7 0.3 1033301400133 2.1 0.6 0.3 1.0 0.4 1033301400134 2204. 0.4 3.0 1.311 2.7 0.3 1033301400135 2.2 0.6 0.3 1.0 0.4 1033301400136 2304. 0.4 2.9 1.328 2.8 0.3 1033301400137 2.3 0.6 0.3 1.0 0.4 1033301400138 2499. 0.4 2.6 1.226 3.0 0.3 1033301400139 2.5 0.6 0.3 0.9 0.4 1033301400140 2820. 0.2 1.6 1.269 3.2 0.3 1033301400141 2.8 0.6 0.2 0.9 0.4 1033301400142 3000. 0.3 1.9 1.210 3.4 0.3 1033301400143 3.0 0.6 0.2 0.9 0.4 1033301400144 3500. 0.2 1.5 1.169 3.8 0.3 1033301400145 3.5 0.5 0.2 0.8 0.5 1033301400146 ENDDATA 108 0 1033301400147 ENDSUBENT 146 0 1033301499999 SUBENT 10333015 20201113 14731033301500001 BIB 9 26 1033301500002 REACTION ((92-U-235(N,F),,SIG)/(3-LI-6(N,T)2-HE-4,,SIG)) 1033301500003 INC-SOURCE (P-LI7) 1033301500004 SAMPLE Sample S-2pi-5: 1033301500005 400 ug/cm2 thick, 11 cm2 area, 1033301500006 (92-U-235,ENR=0.9837) 1033301500007 (92-U-234,ENR=0.00027) 1033301500008 (92-U-236,ENR=0.00056) 1033301500009 (92-U-238,ENR=0.0154) 1033301500010 METHOD (TOF) 1033301500011 DETECTOR (SCIN) 2pi-gas scintillation counter (2pi-GSC) for 1033301500012 fission fragment detection 1033301500013 (GLASD) Li-glass (0.1 cm thick, 3.8 cm diam.) detector 1033301500014 for neutrons 1033301500015 ERR-ANALYS (ERR-T) Total uncertainty (1.5-2.5%)1033301500016 (ERR-S,,,U) statistics (0.8-1.8%)1033301500017 (ERR-1,,,P) fission fragment detection (0.5%)1033301500018 (ERR-2,,,P) Li det., transmission, scatt. (0.2-0.3%)1033301500019 (ERR-3,,,P) inscatter from fission counter (0.5%)1033301500020 (ERR-4,,,P) inscatter from target (0.5%)1033301500021 (ERR-5,,,P) background, integration (0.8-1.5%)1033301500022 COMMENT By compiler (2020-11-13): 1033301500023 This data set is treated as a shape data set in GMA 1033301500024 input. 235U(n,f)/6Li(n,t) in 008 multiplied by ~0.951.1033301500025 STATUS (PENTZ) GMA input #562 1033301500026 (COREL,10333008) 235U(n,f) before renormalization 1033301500027 HISTORY (20201113C) On 1033301500028 ENDBIB 26 0 1033301500029 COMMON 3 3 1033301500030 ERR-1 ERR-3 ERR-4 1033301500031 PER-CENT PER-CENT PER-CENT 1033301500032 0.5 0.5 0.5 1033301500033 ENDCOMMON 3 0 1033301500034 DATA 8 10 1033301500035 EN EN-ERR EN-RSL-HW DATA ERR-T ERR-S 1033301500036 ERR-2 ERR-5 1033301500037 KEV PER-CENT PER-CENT NO-DIM PER-CENT PER-CENT 1033301500038 PER-CENT PER-CENT 1033301500039 34.5 8.7 14.5 2.314 1.8 0.2 1033301500040 1.5 2.5 1033301500041 42. 7.1 11.9 2.353 1.8 0.2 1033301500042 1.5 2.5 1033301500043 45.5 6.6 11.0 2.447 1.7 0.2 1033301500044 1.5 2.4 1033301500045 60. 5.0 8.3 2.566 1.7 0.2 1033301500046 1.4 2.4 1033301500047 75. 4.0 6.7 2.601 1.6 0.2 1033301500048 1.4 2.3 1033301500049 83. 3.6 6.0 2.458 1.6 0.2 1033301500050 1.3 2.2 1033301500051 90. 3.3 5.6 2.402 1.5 0.2 1033301500052 1.3 2.2 1033301500053 101. 3.0 5.0 2.417 1.5 0.2 1033301500054 1.3 2.2 1033301500055 109. 2.8 4.6 2.376 1.5 0.2 1033301500056 1.3 2.2 1033301500057 250. 1.2 1.6 0.4183 0.8 0.3 1033301500058 0.8 1.5 1033301500059 ENDDATA 24 0 1033301500060 ENDSUBENT 59 0 1033301599999 ENDENTRY 15 0 1033399999999