ENTRY 10144 20001211 00001014400000001 SUBENT 10144001 20001211 00001014400100001 BIB 11 29 1014400100002 INSTITUTE (1USABNL) 1014400100003 REFERENCE (J,NSE,44,173,197105) 1014400100004 AUTHOR (J.F.CONANT,P.F.PALMEDO) 1014400100005 TITLE Measurement of the Delayed-nEUTRON Fractions for 1014400100006 Thermal Fission of Uranium-235, Plutonium-239 and 1014400100007 Uranium-233 1014400100008 FACILITY (REAC) 100-kW Brookhaven Neutron Source Reactor II 1014400100009 (NSR II). 1014400100010 METHOD Measured prompt plus delayed neutron production from 1014400100011 source in beam. Terminated beam and counted delayed 1014400100012 neutrons for either 40 or 80 sec. boral shutter. 1014400100013 DETECTOR (LONGC) Five-chamber He3 long counter virtually 1014400100014 identical to one described in Nucl.Instr.Methods 72, 1014400100015 161 (1969). Chambers 30.5-cm long and connected in 1014400100016 parallel. 1014400100017 (FISCH) Two spiral fission chambers used as beam 1014400100018 intensity monitors. 1014400100019 CORRECTION Net correction for room scattered neutrons 1.1%, with 1014400100020 uncertainty of 0.4%. Correction for detector response 1014400100021 difference between fission spectrum and delayed- 1014400100022 neutron spectrum 2.9%, with an uncertainty of 2%. 1014400100023 ERR-ANALYS (DATA-ERR) Data errors are estimates of accuracy as 1014400100024 standard deviations. 1014400100025 STATUS (APRVD) Approved by author. 1014400100026 Data taken from reference. 1014400100027 HISTORY (19710618C) 1014400100028 (19820527A) Converted to REACTION formalism 1014400100029 (19820602A) BIB correction. 1014400100030 (20001211A) Converted to new date formats, lower case. 1014400100031 ENDBIB 29 0 1014400100032 NOCOMMON 0 0 1014400100033 ENDSUBENT 32 0 1014400199999 SUBENT 10144002 20001211 00001014400200001 BIB 3 6 1014400200002 REACTION ((92-U-235(N,F),DL,NU,,MXW)/ 1014400200003 (92-U-235(N,F),,NU,,MXW)) 1014400200004 SAMPLE Thin foil, 15.8x11.4x0.010-cm. composition (weight-%): 1014400200005 U235 (93.2), U238 (6.8). 1014400200006 ERR-ANALYS Intrinsic error 2.0%. Error in delayed-neutron 1014400200007 precursor half-life and relative yield 4.0%. 1014400200008 ENDBIB 6 0 1014400200009 NOCOMMON 0 0 1014400200010 DATA 3 1 1014400200011 EN-DUMMY DATA DATA-ERR 1014400200012 EV NO-DIM NO-DIM 1014400200013 0.0253 0.0065 0.0003 1014400200014 ENDDATA 3 0 1014400200015 ENDSUBENT 14 0 1014400299999 SUBENT 10144003 20001211 00001014400300001 BIB 3 6 1014400300002 REACTION ((94-PU-239(N,F),DL,NU,,MXW)/ 1014400300003 (94-PU-239(N,F),,NU,,MXW)) 1014400300004 SAMPLE Thin foil, 15.2x10.2x0.0025-cm. composition (weight-%):1014400300005 Pu239 (99.12), Pu240 (0.87), Pu241 (0.01). 1014400300006 ERR-ANALYS Intrinsic error 2.0%. Error in delayed-neutron 1014400300007 precursor half-life and relative yield 10.6%. 1014400300008 ENDBIB 6 0 1014400300009 NOCOMMON 0 0 1014400300010 DATA 3 1 1014400300011 EN-DUMMY DATA DATA-ERR 1014400300012 EV NO-DIM NO-DIM 1014400300013 0.0253 0.0023 0.0002 1014400300014 ENDDATA 3 0 1014400300015 ENDSUBENT 14 0 1014400399999 SUBENT 10144004 20001211 00001014400400001 BIB 3 7 1014400400002 REACTION ((92-U-233(N,F),DL,NU,,MXW)/ 1014400400003 (92-U-233(N,F),,NU,,MXW)) 1014400400004 SAMPLE Thin foil, 15.2x10.2x0.0038-cm. composition (weight-%):1014400400005 U233 (97.51), U238 (1.37), U234 (1.04), U235 (0.008), 1014400400006 U236 (0.001), U232 (6ppm). 1014400400007 ERR-ANALYS Intrinsic error 2.0%. Error in delayed-neutron 1014400400008 precursor half-life and relative yield 2.7%. 1014400400009 ENDBIB 7 0 1014400400010 NOCOMMON 0 0 1014400400011 DATA 3 1 1014400400012 EN-DUMMY DATA DATA-ERR 1014400400013 EV NO-DIM NO-DIM 1014400400014 0.0253 0.0027 0.0001 1014400400015 ENDDATA 3 0 1014400400016 ENDSUBENT 15 0 1014400499999 ENDENTRY 4 0 1014499999999