ENTRY 13642 20211005 149313642 0 1 SUBENT 13642001 20211005 149313642 1 1 BIB 15 29 13642 1 2 INSTITUTE (1USALAS,1USANIS,1USAORL) 13642 1 3 REFERENCE (J,PR/C,49,672,199402) 13642 1 4 AUTHOR (W.E.Parker,J.E.Lynn,G.L.Morgan,P.W.Lisowski, 13642 1 5 A.D.Carlson,N.W.Hill) 13642 1 6 TITLE Intermediate structure in the neutron-induced fission 13642 1 7 cross section of 236U 13642 1 8 FACILITY (LINAC,1USALAS) LAMPF. 13642 1 9 INC-SOURCE (SPALL) LANSCE spallation source. 13642 1 10 INC-SPECT Neutrons moderated to produce a white neutron source. 13642 1 11 SAMPLE 10.16-cm diameter 236U oxide deposited on steel 13642 1 12 foils. Target impurities of 0.3% 235U and 0.9% 233U. 13642 1 13 The two 236U deposits 219.56 and 272.10 microg/cm2. 13642 1 14 METHOD (TOF) 56.18-m flight path. 13642 1 15 MONITOR (5-B-10(N,A)3-LI-7,,SIG) Used to monitor shape of 13642 1 16 neutron beam spectrum. 13642 1 17 Energy scale relative to resonances found in iron 13642 1 18 and aluminum transmission, and in 235U fission. 13642 1 19 DETECTOR (IOCH) Parallel-plate ionization chamber containing 13642 1 20 30% argon and 70% methane gas. 13642 1 21 PART-DET (FF) 13642 1 22 CORRECTION Corrected for target impurities 13642 1 23 STATUS (APRVD) Approved by W.E.Parker, 97/2/28. 13642 1 24 HISTORY (19970207C) 13642 1 25 (20110515A) OS. BIB updates, reaction in sub.3 13642 1 26 corrected 13642 1 27 (20211005A) BP: Updated entry, added doi. Deleted 13642 1 28 subentry 2 (unobtainable data) per an NRDC decision 13642 1 29 for data sets that were published before 2000 (C32 of 13642 1 30 WP2022-01). 13642 1 31 ENDBIB 29 0 13642 1 32 NOCOMMON 0 0 13642 1 33 ENDSUBENT 32 0 13642 199999 NOSUBENT 13642002 20211005 149313642 2 1 SUBENT 13642003 20211005 149313642 3 1 BIB 5 5 13642 3 2 REACTION (92-U-236(N,F),,ARE) 13642 3 3 MONITOR (92-U-235(N,F),,ARE) 13642 3 4 ERR-ANALYS No error given. 13642 3 5 STATUS (TABLE) Table II, page 676. 13642 3 6 HISTORY (20110515A) OS. Reaction changed to are 13642 3 7 ENDBIB 5 0 13642 3 8 COMMON 2 3 13642 3 9 MONIT MONIT-ERR 13642 3 10 B*EV PER-CENT 13642 3 11 246.5 1. 13642 3 12 ENDCOMMON 3 0 13642 3 13 DATA 2 4 13642 3 14 EN-RES DATA 13642 3 15 EV B*EV 13642 3 16 1280. 5.8 13642 3 17 2959. 1.1 13642 3 18 6300. 5.7 13642 3 19 10400. 1.5 13642 3 20 ENDDATA 6 0 13642 3 21 ENDSUBENT 20 0 13642 399999 SUBENT 13642004 20211005 149313642 4 1 BIB 4 6 13642 4 2 REACTION (92-U-236(N,F),,WID) 13642 4 3 ASSUMED (ASSUM1,92-U-236(N,G),,WID) 13642 4 4 (ASSUM2,92-U-236(N,F),,WID) 13642 4 5 ERR-ANALYS (DATA-ERR) Due primarily to error in radiation width. 13642 4 6 Error in resonance energies believed to be <0.5%. 13642 4 7 STATUS (TABLE) Table I, page 676. 13642 4 8 ENDBIB 6 0 13642 4 9 NOCOMMON 0 0 13642 4 10 DATA 7 7 13642 4 11 EN-RES DATA DATA-ERR ASSUM1 ASSUM1-ERR ASSUM2 13642 4 12 ASSUM2-ERR 13642 4 13 EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 13642 4 14 MILLI-EV 13642 4 15 5.45 0.0013 0.0001 24.5 1.0 13642 4 16 13642 4 17 1268.8 0.82 0.3 24. 4. 13642 4 18 13642 4 19 1281.7 7.7 5.0 24. 4. 13642 4 20 13642 4 21 1291.7 0.93 0.11 30.5 4.3 13642 4 22 13642 4 23 2958.9 1.4 0.6 24. 4. 13642 4 24 13642 4 25 6300. 10.8 6. 24. 4. 100.13642 4 26 40. 13642 4 27 10400. 4.6 2.6 24. 4. 100.13642 4 28 40. 13642 4 29 ENDDATA 18 0 13642 4 30 ENDSUBENT 29 0 13642 499999 ENDENTRY 4 0 1364299999999