ENTRY 14536 20190515 14511453600000001 SUBENT 14536001 20190515 14511453600100001 BIB 11 24 1453600100002 TITLE Delayed neutron emission measurements for fast 1453600100003 fission of U-235, Np-237, Am-243 1453600100004 AUTHOR (W.Charlton,T.Parish,S.Raman,N.Shinohara,M.Andoh) 1453600100005 INSTITUTE (1USATAM,1USAORL,2JPNJAE) 1453600100006 REFERENCE (C,97TRIEST,1,491,1997) 1453600100007 #NSR: 1997CHZV 1453600100008 FACILITY (REAC,1USATAM) Triga reactor with a very fast 1453600100009 pneumatic transfer system 1453600100010 INC-SOURCE Fast fission neutron spectrum in a pool-type reactor 1453600100011 using a fast flux irradiation device. This device was 1453600100012 characterized using a foil activation technique. 1453600100013 DETECTOR (BF3) 10B-F3 proportional counter. The detector array 1453600100014 was calibrated using a energy response function, 1453600100015 calculated by the MCNP code. This response function was1453600100016 used to adjust the measured efficiency of the array for1453600100017 the Cf-252 calibration source to that expected for 1453600100018 delay neutron. 1453600100019 ANALYSIS Yields and decay constants were acquired from the 1453600100020 measured emission rates using a graphical stripping 1453600100021 procedure, then they were improved using a least 1453600100022 squares technique. 1453600100023 CORRECTION Corrected for detector dead-time 1453600100024 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1453600100025 HISTORY (20190515C) OG. 1453600100026 ENDBIB 24 0 1453600100027 COMMON 1 3 1453600100028 EN-DUMMY 1453600100029 MEV 1453600100030 1.5 1453600100031 ENDCOMMON 3 0 1453600100032 ENDSUBENT 31 0 1453600199999 SUBENT 14536002 20190515 14511453600200001 BIB 3 5 1453600200002 REACTION (92-U-235(N,F),DL/GRP,NU,,FST) 1453600200003 ANALYSIS Delayed neutrons in 7-groups presented. Data for 7-th 1453600200004 group determined using a calculational technique is 1453600200005 equal (0.048 +- 0.012) PC/FIS 1453600200006 STATUS (TABLE) Table I in main ref. 1453600200007 ENDBIB 5 0 1453600200008 NOCOMMON 0 0 1453600200009 DATA 4 6 1453600200010 DCNST DCNST-ERR DATA DATA-ERR 1453600200011 1/SEC 1/SEC PC/FIS PC/FIS 1453600200012 0.0125 0.0002 0.053 0.002 1453600200013 0.0283 0.0004 0.222 0.011 1453600200014 0.0419 0.0005 0.182 0.009 1453600200015 0.158 0.002 0.435 0.017 1453600200016 0.321 0.004 0.429 0.018 1453600200017 0.973 0.017 0.301 0.015 1453600200018 ENDDATA 8 0 1453600200019 ENDSUBENT 18 0 1453600299999 SUBENT 14536003 20190515 14511453600300001 BIB 3 5 1453600300002 REACTION (93-NP-237(N,F),DL/GRP,NU,,FST) 1453600300003 ANALYSIS Delayed neutrons in 7-groups presented. Data for 7-th 1453600300004 group determined using a calculational technique is 1453600300005 equal (0.027 +- 0.007) PC/FIS 1453600300006 STATUS (TABLE) Table I in main ref. 1453600300007 ENDBIB 5 0 1453600300008 NOCOMMON 0 0 1453600300009 DATA 4 6 1453600300010 DCNST DCNST-ERR DATA DATA-ERR 1453600300011 1/SEC 1/SEC PC/FIS PC/FIS 1453600300012 0.0124 0.0003 0.035 0.002 1453600300013 0.0283 0.0007 0.183 0.012 1453600300014 0.0407 0.0008 0.107 0.005 1453600300015 0.165 0.002 0.366 0.021 1453600300016 0.419 0.006 0.325 0.016 1453600300017 0.835 0.030 0.100 0.016 1453600300018 ENDDATA 8 0 1453600300019 ENDSUBENT 18 0 1453600399999 SUBENT 14536004 20190515 14511453600400001 BIB 3 5 1453600400002 REACTION (95-AM-243(N,F),DL/GRP,NU,,FST) 1453600400003 ANALYSIS Delayed neutrons in 7-groups presented. Data for 7-th 1453600400004 group determined using a calculational technique is 1453600400005 equal (0.025 +- 0.006) PC/FIS 1453600400006 STATUS (TABLE) Table I in main ref. 1453600400007 ENDBIB 5 0 1453600400008 NOCOMMON 0 0 1453600400009 DATA 4 6 1453600400010 DCNST DCNST-ERR DATA DATA-ERR 1453600400011 1/SEC 1/SEC PC/FIS PC/FIS 1453600400012 0.0124 0.0004 0.014 0.004 1453600400013 0.0283 0.0009 0.174 0.009 1453600400014 0.0419 0.0009 0.053 0.004 1453600400015 0.145 0.002 0.203 0.012 1453600400016 0.395 0.006 0.285 0.013 1453600400017 1.49 0.04 0.109 0.011 1453600400018 ENDDATA 8 0 1453600400019 ENDSUBENT 18 0 1453600499999 SUBENT 14536005 20190515 14511453600500001 BIB 2 2 1453600500002 REACTION (92-U-235(N,F),DL,NU,,FST) 1453600500003 STATUS (TABLE) Text in main ref. 1453600500004 ENDBIB 2 0 1453600500005 NOCOMMON 0 0 1453600500006 DATA 2 1 1453600500007 DATA DATA-ERR 1453600500008 PC/FIS PC/FIS 1453600500009 1.67 0.08 1453600500010 ENDDATA 3 0 1453600500011 ENDSUBENT 10 0 1453600599999 SUBENT 14536006 20190515 14511453600600001 BIB 2 2 1453600600002 REACTION (93-NP-237(N,F),DL,NU,,FST) 1453600600003 STATUS (TABLE) Text in main ref. 1453600600004 ENDBIB 2 0 1453600600005 NOCOMMON 0 0 1453600600006 DATA 2 1 1453600600007 DATA DATA-ERR 1453600600008 PC/FIS PC/FIS 1453600600009 1.14 0.07 1453600600010 ENDDATA 3 0 1453600600011 ENDSUBENT 10 0 1453600699999 SUBENT 14536007 20190515 14511453600700001 BIB 2 2 1453600700002 REACTION (95-AM-243(N,F),DL,NU,,FST) 1453600700003 STATUS (TABLE) Text in main ref. 1453600700004 ENDBIB 2 0 1453600700005 NOCOMMON 0 0 1453600700006 DATA 2 1 1453600700007 DATA DATA-ERR 1453600700008 PC/FIS PC/FIS 1453600700009 0.86 0.05 1453600700010 ENDDATA 3 0 1453600700011 ENDSUBENT 10 0 1453600799999 ENDENTRY 7 0 1453699999999