ENTRY 10636 20201129 14751063600000001 SUBENT 10636001 20201129 14751063600100001 BIB 12 33 1063600100002 TITLE A measurement of the fission cross section of 1063600100003 plutonium-241 from 8 eV to 70 keV 1063600100004 AUTHOR (G.W.Carlson, J.W.Behrens, J.B.Czirr) 1063600100005 INSTITUTE (1USALRL) 1063600100006 REFERENCE (J,NSE,63,149,1977) 1063600100007 FACILITY (LINAC,1USALRL) Livermore linear accelerator 1063600100008 INC-SOURCE (PHOTO) Pulsed neutron source 1063600100009 METHOD (TOF) Two data sets were taken: 1063600100010 - low energy data set (thermal to 2.0 keV) 1063600100011 - high energy data set (100 eV to 70 keV) 1063600100012 SAMPLE 235U deposited in 10 layers (2.7 mg/cm2 thick in total)1063600100013 241Pu deposited in 8 layers (1.4 mg/cm2 thick in total)1063600100014 with impurities of 239Pu (1.4%), 240Pu (0.2%), 1063600100015 242Pu (0.1%), 241Am (1.8%). 1063600100016 DETECTOR (FISCH) 235U and 241Pu deposited on both sides of the 1063600100017 positive and negative electrodes 1063600100018 (GLASD) 6Li glass scintillators: 1063600100019 - natLi glass scintillator in low energy run 1063600100020 - 95% 6Li glass scintillator in high energy run 1063600100021 CORRECTION Corrected for 1063600100022 - 239Pu fission (with ENDF/B-IV) 1063600100023 - background, 1063600100024 - fission chamber absorption, 1063600100025 - Li glass scattering and absorption, 1063600100026 - dead time, 1063600100027 - scattering in the Al foils of the fission chamber, 1063600100028 STATUS (APRVD) Approved by author, 1976/12/14 1063600100029 HISTORY (19761004C) 1063600100030 (19770105U) BIB update converted to REACTION formalism 1063600100031 (19840917A) BIB corrections. 1063600100032 (20080812A) Converted to new data formats, lower case. 1063600100033 BIB updates. Error heading updates. 1063600100034 (20201129A) On. Important alteration in 002. 1063600100035 ENDBIB 33 0 1063600100036 NOCOMMON 0 0 1063600100037 ENDSUBENT 36 0 1063600199999 SUBENT 10636002 20201129 14751063600200001 BIB 6 19 1063600200002 REACTION 1((94-PU-241(N,F),,SIG)/(3-LI-6(N,T)2-HE-4,,SIG)) 1063600200003 2(94-PU-241(N,F),,SIG) 1063600200004 MONITOR The high energy data set was normalized to the low 1063600200005 energy data set in the region of overlap. 1063600200006 2((MONIT)94-PU-241(N,F),,SIG) 1063600200007 absolute normalization at thermal 1063600200008 (3-LI-6(N,T)2-HE-4,,SIG) 1063600200009 shape normalization with ENDF/B-IV 1063600200010 MONIT-REF 2((MONIT),H.D.Lemmel,C,75WASH,1,286,1975) 1063600200011 ERR-ANALYS (ERR-S) Statistical uncertainty (standard deviation). 1063600200012 (ERR-SYS) Systematic error (root-mean-square). 1063600200013 Systematic error below 100 eV primarily due to 1063600200014 thermal-neutron cross section uncertainty. Above 100 1063600200015 eV error is mainly due to overlap normalization 1063600200016 (1.2%), flux background error, and 6Li cross section 1063600200017 error (3% at 50 keV). 1063600200018 STATUS (TABLE) Table I of Nucl.Sci.Eng.63(1977)149 1063600200019 HISTORY (19831102A) BIB, DATA headings corrected. 1063600200020 (20201129A) On. EN-NRM and MONIT added. 1063600200021 ENDBIB 19 0 1063600200022 COMMON 3 3 1063600200023 EN-NRM-MIN2EN-NRM-MAX2MONIT 2 1063600200024 EV EV B 1063600200025 0.0203 0.0303 1015. 1063600200026 ENDCOMMON 3 0 1063600200027 DATA 6 30 1063600200028 EN-MIN EN-MAX DATA 1DATA 2ERR-S ERR-SYS 1063600200029 KEV KEV NO-DIM B PER-CENT PER-CENT 1063600200030 0.008 0.009 4.700 239.1 1.2 1.4 1063600200031 0.009 0.012 2.071 97.7 1.0 1.4 1063600200032 0.012 0.020 4.217 161.7 1.0 1.4 1063600200033 0.020 0.030 2.724 78.9 2.3 1.4 1063600200034 0.030 0.044 1.655 41.2 1.9 1.4 1063600200035 0.044 0.055 1.351 28.9 3.4 1.4 1063600200036 0.070 0.100 2.391 38.6 2.2 1.4 1063600200037 0.100 0.200 2.015 24.1 1.3 3.4 1063600200038 0.200 0.300 2.606 24.8 1.0 2.6 1063600200039 0.300 0.400 2.654 21.2 1.2 2.3 1063600200040 0.400 0.500 2.582 18.2 1.2 2.1 1063600200041 0.500 0.600 2.431 15.5 1.3 2.0 1063600200042 0.600 0.800 1.941 11.0 1.2 2.0 1063600200043 0.800 1.0 2.137 10.6 1.2 2.0 1063600200044 1.0 1.5 2.269 9.65 0.9 2.0 1063600200045 1.5 2.0 2.328 8.34 1.1 2.0 1063600200046 2.0 2.25 2.179 7.04 2.3 2.0 1063600200047 3.5 4.5 2.344 5.54 1.7 2.0 1063600200048 4.5 5.5 2.352 4.96 1.4 2.0 1063600200049 6.1 6.5 2.334 4.39 2.1 2.0 1063600200050 6.5 7.5 2.281 4.08 1.5 2.0 1063600200051 7.5 8.5 2.209 3.68 1.6 2.0 1063600200052 8.5 10.0 2.292 3.56 1.4 2.0 1063600200053 10.0 15.0 2.364 3.20 0.8 2.0 1063600200054 15.0 20.0 2.478 2.84 1.0 2.1 1063600200055 20.0 25.0 2.602 2.67 1.0 2.5 1063600200056 25.0 30.0 2.727 2.57 1.1 2.9 1063600200057 40.0 50.0 2.947 2.28 1.5 3.2 1063600200058 50.0 60.0 2.956 2.15 1.2 3.7 1063600200059 60.0 70.0 3.031 2.11 1.0 3.6 1063600200060 ENDDATA 32 0 1063600200061 ENDSUBENT 60 0 1063600299999 ENDENTRY 2 0 1063699999999