ENTRY 23577 20200801 22932357700000001 SUBENT 23577001 20200801 22932357700100001 BIB 8 17 2357700100002 TITLE Determination of the 243,246,248Cm thermal neutron 2357700100003 induced fission cross sections 2357700100004 AUTHOR (O.Serot, C.Wagemans, S.Vermote, J.Heyse, T.Soldner, 2357700100005 P.Geltenbort) 2357700100006 REFERENCE (S,AIP-798,182,2005) 2357700100007 INSTITUTE (2FR ILL) T.Soldner, P.Geltenbort 2357700100008 (2FR CAD) O.Serot, J.Heyse 2357700100009 (2BLGGHT) C.Wagemans, S.Vermote 2357700100010 (2ZZZGEL) J.Heyse 2357700100011 FACILITY (REAC,2FR ILL) High flux reactor of the ILL 2357700100012 INC-SOURCE (REAC) PF1B cold neutron guide of 76 m length. 2357700100013 INC-SPECT Neutron flux 1.3E+10 n/(sec*cm2). 2357700100014 Average neutron wave length 3.9 Angstrom corresponds 2357700100015 to En=5.38 meV. 2357700100016 Flux was measured by U-235 sample (99.97% U-235, 2357700100017 16.5 ug mass) of the same dimensions as Cm sample. 2357700100018 HISTORY (20200801C) M.M. 2357700100019 ENDBIB 17 0 2357700100020 NOCOMMON 0 0 2357700100021 ENDSUBENT 20 0 2357700199999 SUBENT 23577002 20200801 22932357700200001 BIB 9 31 2357700200002 REACTION (96-CM-243(N,F),,SIG) 2357700200003 SAMPLE Isotopic composition at 2005 ( data of experiment) 2357700200004 Cm-243 - 97.110%, 4.42E+15 atoms; 2357700200005 Cm-244 - 1.473%, 6.70E+13 atoms; 2357700200006 Cm-245 - 0.065%, 2.95E+12 atoms; 2357700200007 Pu-239 - 1.352%, 5.15E+13 atoms. 2357700200008 2 ug Cm-oxide, deposited on 30 um thick Al backing, 2357700200009 diameter 15 mm. 2357700200010 DETECTOR (SIBAR) 450 mm2 large Si-Au surface-barrier detector 2357700200011 for fission fragment detection. 2357700200012 METHOD Cm-243: 2357700200013 measuring time 3470 sec, 2357700200014 fission counting rate 140.6+-1.4 fis/sec (stat.+syst. 2357700200015 uncertainties), 2357700200016 detection efficiency 1.3313+-0.0003 % 2357700200017 U-235 flux measurement: 2357700200018 measuring time 300 sec, 2357700200019 fission counting rate - 1409.8+-4.7 fis/sec. 2357700200020 detection efficiency 1.4063+-0.0003 %. 2357700200021 ANALYSIS Cm-243 fission cross section at 5.38 meV was determined2357700200022 by formulas (1,2) in AIP-798,182,2005 . 2357700200023 Contribution of impurity fissions subtracted by 2357700200024 using the Cm-244 and Pu-239 fission cross sections from2357700200025 JEFF-3.0 and the Cm-245 fission cross section from 2357700200026 JENDL-3.3. 2357700200027 ASSUMED (ASSUM1,96-CM-244(N,F),,SIG) 2357700200028 (ASSUM2,96-CM-245(N,F),,SIG) 2357700200029 (ASSUM4,94-PU-239(N,F),,SIG) 2357700200030 MONITOR ((MONIT)92-U-235(N,F),,SIG) 2357700200031 ERR-ANALYS (DATA-ERR) Includes statistical and systematic errors 2357700200032 STATUS (TABLE) Text page 185 of AIP-798,182,2005 2357700200033 ENDBIB 31 0 2357700200034 COMMON 5 3 2357700200035 EN ASSUM4 ASSUM4-ERR MONIT MONIT-ERR 2357700200036 EV B B B B 2357700200037 5.38 E-03 1582. 20. 1325. 16. 2357700200038 ENDCOMMON 3 0 2357700200039 DATA 6 1 2357700200040 DATA DATA-ERR ASSUM1 ASSUM1-ERR ASSUM2 ASSUM2-ERR 2357700200041 B B B B B B 2357700200042 1240. 28. 2.78 0.57 5267. 211. 2357700200043 ENDDATA 3 0 2357700200044 ENDSUBENT 43 0 2357700299999 SUBENT 23577003 20200801 22932357700300001 BIB 5 13 2357700300002 REACTION (96-CM-243(N,F),,SIG,,,DERIV) 2357700300003 REL-REF (A,,C.E.Bemis Jr+,J,NSE,63,413,1977) 609.+-26.9 b 2357700300004 (D,,E.K.Hulet+,J,PR,107,1294,1957) 2357700300005 somewhat lower, 690.+-50 b 2357700300006 (D,,K.D.Zhuravlev+,J,AE,47,55,1979) 2357700300007 somewhat lower, 672.+-60. b 2357700300008 ANALYSIS Cm-243 fission cross section at thermal point was 2357700300009 derived from measured fission cross section at 5.38 meV2357700300010 assuming 1/v law. 2357700300011 ERR-ANALYS (DATA-ERR) Includes uncertainties of directly measured 2357700300012 cross section at 5.38 meV and of 1/v law assumption. 2357700300013 STATUS (TABLE) Text page 185 of AIP-798,182,2005 2357700300014 (DEP,23577002) Cross section at 5.38 meV 2357700300015 ENDBIB 13 0 2357700300016 COMMON 1 3 2357700300017 EN 2357700300018 EV 2357700300019 0.0253 2357700300020 ENDCOMMON 3 0 2357700300021 DATA 2 1 2357700300022 DATA DATA-ERR 2357700300023 B B 2357700300024 572. 25. 2357700300025 ENDDATA 3 0 2357700300026 ENDSUBENT 25 0 2357700399999 SUBENT 23577004 20200801 22932357700400001 BIB 9 36 2357700400002 REACTION (96-CM-246(N,F),,SIG) 2357700400003 SAMPLE Cm-243 - 0.006 %, 6.85E+12 atoms; 2357700400004 Cm-244 - 0.060 %, 6.81E+13 atoms; 2357700400005 Cm-245 - 0.008 %, 9.46E+12 atoms; 2357700400006 Cm-246 - 99.887%, 1.13E+17 atoms; 2357700400007 Cm-247 - 0.025 %, 2.83E+13 atoms; 2357700400008 Cm-248 - 0.014 %, 1.58E+13 atoms. 2357700400009 2 ug Cm-oxide, deposited on 30 um thick Al backing, 2357700400010 diameter 15 mm, mass 46.4 ug. 2357700400011 DETECTOR (SIBAR) 2000 mm2 large surface-barrier detector 2357700400012 for fission fragment detection. 2357700400013 (SIBAR) 50 mm2 large surface barrier detector for 2357700400014 alphas counting from B-10(n,alpha) reaction. 2357700400015 METHOD Cm-246: 2357700400016 measuring time 14.86 hr, 2357700400017 fission counting rate ( background subtracted) 2357700400018 9.64+-0.28(stat.+syst.uncertainties) fis/sec, 2357700400019 U-235 flux measurement: 2357700400020 measuring time 300 sec, 2357700400021 fission counting rate (dead time corrected) - 2357700400022 7687.+-230.(stat.+syst.uncertainties) fis/sec. 2357700400023 B-10 sample was used to determine dead time and 2357700400024 small neutron flux fluctuations via B-10(n,alpha)Li-7 2357700400025 reaction. 2357700400026 ANALYSIS Cm-246 fission cross section at 5.38 meV was determined2357700400027 by formulas (1,2) in AIP-798,182,2005. 2357700400028 Contribution of impurity fissions subtracted by 2357700400029 using the Cm-244,247 and Pu-239 fission cross sections 2357700400030 from JEFF-3.0 and the Cm-245 fission cross section from2357700400031 JENDL-3.3. 2357700400032 ASSUMED (ASSUM1,96-CM-244(N,F),,SIG) 2357700400033 (ASSUM2,96-CM-245(N,F),,SIG) 2357700400034 (ASSUM3,96-CM-247(N,F),,SIG) 2357700400035 MONITOR ((MONIT)92-U-235(N,F),,SIG) 2357700400036 ERR-ANALYS (DATA-ERR) Includes statistical and systematic errors 2357700400037 STATUS (TABLE) Text page 188 of AIP-798,182,2005 2357700400038 ENDBIB 36 0 2357700400039 COMMON 3 3 2357700400040 EN MONIT MONIT-ERR 2357700400041 EV B B 2357700400042 5.38 E-03 1325. 16. 2357700400043 ENDCOMMON 3 0 2357700400044 DATA 8 1 2357700400045 DATA DATA-ERR ASSUM1 ASSUM1-ERR ASSUM2 ASSUM2-ERR 2357700400046 ASSUM3 ASSUM3-ERR 2357700400047 MB MB B B B B 2357700400048 B B 2357700400049 25. 47. 2.78 0.57 5267. 211. 2357700400050 189. 12. 2357700400051 ENDDATA 6 0 2357700400052 ENDSUBENT 51 0 2357700499999 SUBENT 23577005 20200801 22932357700500001 BIB 5 12 2357700500002 REACTION (96-CM-246(N,F),,SIG,,,DERIV) 2357700500003 REL-REF (D,,R.W.Benjamin+,J,NSE,47,203,1972) 2357700500004 much smaller, 170+-100 mb 2357700500005 (D,,K.D.Zhuravlev+,J,AE,39,285,1975) 2357700500006 much smaller, 140.+-50. mb 2357700500007 ANALYSIS Cm-246 fission cross section at thermal point was 2357700500008 derived from measured fission cross section at 5.38 meV2357700500009 assuming 1/v law. 2357700500010 ERR-ANALYS (DATA-ERR) Includes uncertainties of directly measured 2357700500011 cross section at 5.38 meV and of 1/v law assumption. 2357700500012 STATUS (TABLE) Text page 188 of AIP-798,182,2005 2357700500013 (DEP,23577004) Cross section at 5.38 meV 2357700500014 ENDBIB 12 0 2357700500015 COMMON 1 3 2357700500016 EN 2357700500017 EV 2357700500018 0.0253 2357700500019 ENDCOMMON 3 0 2357700500020 DATA 2 1 2357700500021 DATA DATA-ERR 2357700500022 MB MB 2357700500023 12. 25. 2357700500024 ENDDATA 3 0 2357700500025 ENDSUBENT 24 0 2357700599999 SUBENT 23577006 20200801 22932357700600001 BIB 9 35 2357700600002 REACTION (96-CM-248(N,F),,SIG) 2357700600003 SAMPLE Cm-244 - 0.817 %, 6.98E+14 atoms; 2357700600004 Cm-245 - 0.020 %, 1.73E+13 atoms; 2357700600005 Cm-246 - 1.323 %, 1.13E+15 atoms; 2357700600006 Cm-247 - 0.232 %, 1.98E+14 atoms; 2357700600007 Cm-248 - 97.608%, 8.34E+16 atoms. 2357700600008 2 ug Cm-oxide, deposited on 30 um thick Al backing, 2357700600009 diameter 15 mm, mass 46.4 ug. 2357700600010 DETECTOR (SIBAR) 2000 mm2 large surface-barrier detector 2357700600011 for fission fragment detection. 2357700600012 (SIBAR) 50 mm2 large surface barrier detector for 2357700600013 alphas counting from B-10(n,alpha) reaction. 2357700600014 METHOD Cm-248: 2357700600015 measuring time 14.48 hr, 2357700600016 fission counting rate ( background subtracted) 2357700600017 27.7+-0.2(stat.+syst.uncertainties) fis/sec, 2357700600018 U-235 flux measurement: 2357700600019 measuring time 120 sec, 2357700600020 fission counting rate (dead time corrected) - 2357700600021 7643.+-235.(stat.+syst.uncertainties) fis/sec. 2357700600022 B-10 sample was used to determine dead time and 2357700600023 small neutron flux fluctuations via B-10(n,alpha)Li-7 2357700600024 reaction. 2357700600025 ANALYSIS Cm-248 fission cross section at 5.38 meV was determined2357700600026 by formulas (1,2) in AIP-798,182,2005 . 2357700600027 Contribution of impurity fissions subtracted by 2357700600028 using the Cm-244,247 and Pu-239 fission cross sections 2357700600029 from JEFF-3.0 and the Cm-245 fission cross section from2357700600030 JENDL-3.3. 2357700600031 ASSUMED (ASSUM1,96-CM-244(N,F),,SIG) 2357700600032 (ASSUM2,96-CM-245(N,F),,SIG) 2357700600033 (ASSUM3,96-CM-247(N,F),,SIG) 2357700600034 MONITOR ((MONIT)92-U-235(N,F),,SIG) 2357700600035 ERR-ANALYS (DATA-ERR) Includes statistical and systematic errors 2357700600036 STATUS (TABLE) Text page 189 of AIP-798,182,2005 2357700600037 ENDBIB 35 0 2357700600038 COMMON 3 3 2357700600039 EN MONIT MONIT-ERR 2357700600040 EV B B 2357700600041 5.38 E-03 1325. 16. 2357700600042 ENDCOMMON 3 0 2357700600043 DATA 8 1 2357700600044 DATA DATA-ERR ASSUM1 ASSUM1-ERR ASSUM2 ASSUM2-ERR 2357700600045 ASSUM3 ASSUM3-ERR 2357700600046 MB MB B B B B 2357700600047 B B 2357700600048 685. 84. 2.78 0.57 5267. 211. 2357700600049 189. 12. 2357700600050 ENDDATA 6 0 2357700600051 ENDSUBENT 50 0 2357700699999 SUBENT 23577007 20200801 22932357700700001 BIB 5 10 2357700700002 REACTION (96-CM-248(N,F),,SIG,,,DERIV) 2357700700003 REL-REF (A,,R.W.Benjamin+,J,NSE,47,203,1972) 340.+-70. mb 2357700700004 (A,,K.D.Zhuravlev+,J,AE,39,285,1975) 390.+-70. mb 2357700700005 ANALYSIS Cm-248 fission cross section at thermal point was 2357700700006 derived from measured fission cross section at 5.38 meV2357700700007 assuming 1/v law. 2357700700008 ERR-ANALYS (DATA-ERR) Includes uncertainties of directly measured 2357700700009 cross section at 5.38 meV and of 1/v law assumption. 2357700700010 STATUS (TABLE) Text page 189 of AIP-798,182,2005 2357700700011 (DEP,23577006) Cross section at 5.38 meV 2357700700012 ENDBIB 10 0 2357700700013 COMMON 1 3 2357700700014 EN 2357700700015 EV 2357700700016 0.0253 2357700700017 ENDCOMMON 3 0 2357700700018 DATA 2 1 2357700700019 DATA DATA-ERR 2357700700020 MB MB 2357700700021 316. 43. 2357700700022 ENDDATA 3 0 2357700700023 ENDSUBENT 22 0 2357700799999 ENDENTRY 7 0 2357799999999