ENTRY 12535 20181102 14441253500000001 SUBENT 12535001 20181102 14441253500100001 BIB 8 21 1253500100002 INSTITUTE (1USAANL) 1253500100003 REFERENCE (J,NSE,1,62,1956) 1253500100004 (C,55GENEVA,7,261,1955) 1253500100005 AUTHOR (P.R.Fields,G.L.Pyle,M.G.Inghram,H.Diamond, 1253500100006 M.H.Studier,W.M.Manning) 1253500100007 TITLE Pile neutron cross sections of the heavier plutonium 1253500100008 isotopes. 1253500100009 SAMPLE Isotopic composition of sample (in %) 1253500100010 Sample CR-1 CR-2 CR-3 1253500100011 ------ ------------ ------------ ------------ 1253500100012 Pu-239 74.31+-0.22 53.3+-0.3 23.82+-0.16 1253500100013 Pu-240 21.96+-0.20 35.6+-0.2 49.35+-0.40 1253500100014 Pu-241 3.39+-0.07 9.17+-0.04 17.07+-0.24 1253500100015 Pu-242 0.337+-0.01 1.96+-0.03 9.76+-0.07 1253500100016 METHOD Samples irradiated for 6 months (CR-1, 1 year (CR-2), 1253500100017 and 2 years (CR-3). 1253500100018 STATUS (TABLE) Nucl.Sci.Eng.1,62(1956), text and abstract 1253500100019 HISTORY (19760804T) Translated from SCISRS 1253500100020 (19841004A) Converted to reaction formalism 1253500100021 (20181102U) OS. Several BIB corr., converted to lower 1253500100022 and upper case 1253500100023 ENDBIB 21 0 1253500100024 NOCOMMON 0 0 1253500100025 ENDSUBENT 24 0 1253500199999 SUBENT 12535002 20181102 14441253500200001 BIB 7 10 1253500200002 REACTION (94-PU-240(N,G)94-PU-241,,SIG,,SPA) 1253500200003 FACILITY (REAC,1CANCRC) 1253500200004 INC-SOURCE (REAC) U-D2O reactor, NRX 1253500200005 MONITOR (94-PU-239(N,G)94-PU-240,,SIG) 1253500200006 Based on Pu-239 thermal capture = 358 b 1253500200007 and effective thermal absorption = 1150 b. 1253500200008 ANALYSIS Average of values for 3 irradiations - CR-1(560+-55 b),1253500200009 CR-2 (550+-55 b), CR-3 (495+-50 b). 1253500200010 INC-SPECT Reactor spectrum 1253500200011 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1253500200012 ENDBIB 10 0 1253500200013 NOCOMMON 0 0 1253500200014 DATA 4 1 1253500200015 EN-DUMMY DATA DATA-ERR MONIT 1253500200016 MEV B B B 1253500200017 2.53 -08 5.30 +02 5.0 +01 358. 1253500200018 ENDDATA 3 0 1253500200019 ENDSUBENT 18 0 1253500299999 SUBENT 12535003 20181102 14441253500300001 BIB 5 7 1253500300002 REACTION (94-PU-240(N,G)94-PU-241,,SIG,,SPA) 1253500300003 FACILITY (REAC,1USAHED) 1253500300004 INC-SOURCE (REAC) Hanford graphite reactor. 1253500300005 MONITOR (94-PU-239(N,G)94-PU-240,,SIG) 1253500300006 Based on Pu-239 thermal capture = 358 b 1253500300007 and effective thermal absorption = 1150 b. 1253500300008 INC-SPECT Reactor spectrum 1253500300009 ENDBIB 7 0 1253500300010 NOCOMMON 0 0 1253500300011 DATA 3 1 1253500300012 EN-DUMMY DATA MONIT 1253500300013 EV B B 1253500300014 0.0253 515. 358. 1253500300015 ENDDATA 3 0 1253500300016 ENDSUBENT 15 0 1253500399999 SUBENT 12535004 20181102 14441253500400001 BIB 5 7 1253500400002 REACTION (94-PU-241(N,ABS),,SIG,,SPA) 1253500400003 FACILITY (REAC,1USAHED) 1253500400004 INC-SOURCE (REAC) Hanford graphite reactor. 1253500400005 MONITOR (94-PU-239(N,G)94-PU-240,,SIG) 1253500400006 Based on Pu-239 thermal capture = 358 b 1253500400007 and effective thermal absorption = 1150 b. 1253500400008 INC-SPECT Reactor spectrum 1253500400009 ENDBIB 7 0 1253500400010 NOCOMMON 0 0 1253500400011 DATA 3 1 1253500400012 EN-DUMMY DATA MONIT 1253500400013 MEV B B 1253500400014 2.53 -08 1.420 +03 358. 1253500400015 ENDDATA 3 0 1253500400016 ENDSUBENT 15 0 1253500499999 SUBENT 12535005 20181102 14441253500500001 BIB 6 8 1253500500002 REACTION (94-PU-241(N,ABS),,SIG,,SPA) 1253500500003 FACILITY (REAC,1CANCRC) 1253500500004 INC-SOURCE (REAC) U-D2O reactor, NRX 1253500500005 MONITOR (94-PU-239(N,G)94-PU-240,,SIG) 1253500500006 Based on Pu-239 thermal capture = 358 b 1253500500007 and effective thermal absorption = 1150 b 1253500500008 INC-SPECT Reactor spectrum 1253500500009 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1253500500010 ENDBIB 8 0 1253500500011 NOCOMMON 0 0 1253500500012 DATA 4 1 1253500500013 EN-DUMMY DATA DATA-ERR MONIT 1253500500014 MEV B B B 1253500500015 2.53 -08 1.450 +03 2.50 +02 358. 1253500500016 ENDDATA 3 0 1253500500017 ENDSUBENT 16 0 1253500599999 SUBENT 12535006 20181102 14441253500600001 BIB 6 8 1253500600002 REACTION (94-PU-241(N,F),,SIG,,SPA) 1253500600003 FACILITY (REAC,1CANCRC) 1253500600004 INC-SOURCE (REAC) U-D2O reactor, NRX 1253500600005 MONITOR (94-PU-239(N,G)94-PU-240,,SIG) 1253500600006 Based on Pu-239 thermal capture = 358 b 1253500600007 and effective thermal absorption = 1150 b. 1253500600008 INC-SPECT Reactor spectrum 1253500600009 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1253500600010 ENDBIB 8 0 1253500600011 NOCOMMON 0 0 1253500600012 DATA 4 1 1253500600013 EN-DUMMY DATA DATA-ERR MONIT 1253500600014 MEV B B B 1253500600015 2.53 -08 1.060 +03 2.10 +02 358. 1253500600016 ENDDATA 3 0 1253500600017 ENDSUBENT 16 0 1253500699999 SUBENT 12535007 20181102 14441253500700001 BIB 6 8 1253500700002 REACTION (94-PU-241(N,G)94-PU-242,,SIG,,SPA) 1253500700003 FACILITY (REAC,1CANCRC) 1253500700004 INC-SOURCE (REAC) U-D2O reactor, NRX 1253500700005 MONITOR (94-PU-239(N,G)94-PU-240,,SIG) 1253500700006 Based on Pu-239 thermal capture = 358 b 1253500700007 and effective thermal absorption = 1150 b. 1253500700008 INC-SPECT Reactor spectrum 1253500700009 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1253500700010 ENDBIB 8 0 1253500700011 NOCOMMON 0 0 1253500700012 DATA 4 1 1253500700013 EN-DUMMY DATA DATA-ERR MONIT 1253500700014 MEV B B B 1253500700015 2.53 -08 3.90 +02 8.0 +01 358. 1253500700016 ENDDATA 3 0 1253500700017 ENDSUBENT 16 0 1253500799999 SUBENT 12535008 20181102 14441253500800001 BIB 5 5 1253500800002 REACTION (94-PU-242(N,G)94-PU-243,,SIG,,SPA) 1253500800003 FACILITY (REAC,1USAANL) 1253500800004 INC-SOURCE (REAC) Central thimble of ANL heavy water reactor 1253500800005 COMMENT Short time irradiation 1253500800006 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1253500800007 ENDBIB 5 0 1253500800008 NOCOMMON 0 0 1253500800009 DATA 3 1 1253500800010 EN DATA DATA-ERR 1253500800011 MEV B B 1253500800012 2.53 -08 3.0 +01 1.0 +01 1253500800013 ENDDATA 3 0 1253500800014 ENDSUBENT 13 0 1253500899999 SUBENT 12535009 20181102 14441253500900001 BIB 7 11 1253500900002 REACTION (94-PU-243(N,G)94-PU-244,,SIG,,SPA) 1253500900003 FACILITY (REAC,1USAANL) 1253500900004 INC-SOURCE (REAC) MTR reactor 1253500900005 MONITOR (94-PU-239(N,G)94-PU-240,,SIG) 1253500900006 Based on Pu-239 thermal capture = 358 b 1253500900007 and effective thermal absorption = 1150 b. 1253500900008 ASSUMED (ASSUM,94-PU-242(N,G)94-PU-243,,SIG) 1253500900009 Assumed Pu-242 capture = 30 b and that Am-244 decays 1253500900010 0.039 percent by electron capture to Pu-244. 1253500900011 INC-SPECT Reactor spectrum 1253500900012 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1253500900013 ENDBIB 11 0 1253500900014 NOCOMMON 0 0 1253500900015 DATA 5 1 1253500900016 EN-DUMMY DATA DATA-ERR MONIT ASSUM 1253500900017 MEV B B B B 1253500900018 2.53 -08 1.70 +02 9.0 +01 358. 30. 1253500900019 ENDDATA 3 0 1253500900020 ENDSUBENT 19 0 1253500999999 SUBENT 12535010 20181102 14441253501000001 BIB 7 8 1253501000002 REACTION (94-PU-245(N,G)94-PU-246,,SIG,,SPA) 1253501000003 FACILITY (REAC,1USAANL) 1253501000004 INC-SOURCE (REAC) MTR reactor 1253501000005 METHOD (ACTIV) Activation. To Am-246. 1253501000006 MONITOR (94-PU-244(N,G)94-PU-245,,SIG) 1253501000007 Based on Pu244 capture=1.5 b 1253501000008 INC-SPECT Reactor spectrum 1253501000009 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1253501000010 ENDBIB 8 0 1253501000011 NOCOMMON 0 0 1253501000012 DATA 4 1 1253501000013 EN-DUMMY DATA DATA-ERR MONIT 1253501000014 MEV B B B 1253501000015 2.53 -08 2.60 +02 1.45 +02 1.5 1253501000016 ENDDATA 3 0 1253501000017 ENDSUBENT 16 0 1253501099999 SUBENT 12535011 20181102 14441253501100001 BIB 7 8 1253501100002 REACTION (94-PU-244(N,G)94-PU-245,,SIG,,SPA) 1253501100003 FACILITY (REAC,1USAANL) 1253501100004 INC-SOURCE (REAC) Argonne heavy water reactor, CP-3. 1253501100005 METHOD (ACTIV) Activation. To Am-245 1253501100006 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 1253501100007 Based on gold thermal capture=98 b 1253501100008 INC-SPECT Reactor spectrum 1253501100009 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1253501100010 ENDBIB 8 0 1253501100011 NOCOMMON 0 0 1253501100012 DATA 4 1 1253501100013 EN-DUMMY DATA DATA-ERR MONIT 1253501100014 MEV B B B 1253501100015 2.53 -08 1.5 +00 3. -01 98. 1253501100016 ENDDATA 3 0 1253501100017 ENDSUBENT 16 0 1253501199999 ENDENTRY 11 0 1253599999999