ENTRY 10574 20040702 00001057400000001 SUBENT 10574001 20040702 00001057400100001 BIB 12 21 1057400100002 INSTITUTE (1USALRL,1USANBS) 1057400100003 REFERENCE (J,PR/C,13,195,197601) 1057400100004 AUTHOR (R.E.Howe,T.W.Phillips,C.D.Bowman) 1057400100005 TITLE Prompt fission neutrons from eV resonances in 235U: 1057400100006 Measurement and correlation with other fission 1057400100007 properties. 1057400100008 FACILITY (LINAC,1USALRL) LLL linear electron accelerator 1057400100009 INC-SOURCE (SPALL) Electrons on tantalum target. 1057400100010 METHOD (TOF,COINC) Time-of-flight, coincidence in fission 1057400100011 chamber and neutron detector 1057400100012 DETECTOR (FISCH) Fission ionization chamber for detection of 1057400100013 fission events. 1057400100014 (SCIN) Proton-recoil scintillators. 1057400100015 MONITOR (92-U-235(N,F),,NU,,REL/AV) Average nu over incident 1057400100016 neutron energies from 0.52 to 114. eV. 1057400100017 CORRECTION Data were corrected for dead-time and background. 1057400100018 STATUS No reply to author proof. 1057400100019 HISTORY (19760128C) 1057400100020 (19830914A) Converted to REACTION formalism 1057400100021 (19910829A) BIB update 1057400100022 (20040702A) Updated to new date formats, lower case. 1057400100023 ENDBIB 21 0 1057400100024 NOCOMMON 0 0 1057400100025 ENDSUBENT 24 0 1057400199999 SUBENT 10574002 20040702 00001057400200001 BIB 4 6 1057400200002 REACTION (92-U-235(N,F),PR,NU,,RES/REL) Average over resonance. 1057400200003 ERR-ANALYS (ERR-S) Statistical uncertainty. 1057400200004 FLAG (1.) Doublet 1057400200005 HISTORY (19780130A) ISO-QUANT corrected 1057400200006 (19860825A) REACTION, data corrected. 1057400200007 (19910829A) REACTION, data corrected 1057400200008 ENDBIB 6 0 1057400200009 NOCOMMON 0 0 1057400200010 DATA 6 56 1057400200011 EN-RES EN-RES-MIN EN-RES-MAX DATA ERR-S FLAG 1057400200012 EV EV EV ARB-UNITS ARB-UNITS NO-DIM 1057400200013 1.14 1.0018 0.0014 1057400200014 2.03 1.0023 0.0047 1057400200015 2.84 0.992 0.013 1057400200016 3.14 1.0028 0.0032 1057400200017 3.61 1.0019 0.0030 1057400200018 4.84 0.9874 0.0079 1057400200019 6.21 1.0045 0.0071 1057400200020 6.39 1.0007 0.0031 1057400200021 7.08 1.0016 0.0034 1057400200022 8.78 1.0039 0.0012 1057400200023 9.28 1.0024 0.0083 1057400200024 10.2 0.9961 0.0059 1057400200025 11.7 0.9935 0.0043 1057400200026 12.4 0.9964 0.0019 1057400200027 12.8 1.0026 0.0063 1057400200028 14.0 14.5 0.9955 0.0023 1. 1057400200029 15.4 0.9941 0.0042 1057400200030 16.1 0.9884 0.0044 1057400200031 16.7 0.9941 0.0036 1057400200032 18.0 0.9997 0.0035 1057400200033 19.3 0.9972 0.0014 1057400200034 21.1 1.0005 0.0028 1057400200035 22.9 0.9953 0.0048 1057400200036 23.4 23.6 1.0005 0.0031 1. 1057400200037 24.2 0.9969 0.0051 1057400200038 25.2 25.6 1.0010 0.0027 1. 1057400200039 26.5 1.0040 0.0039 1057400200040 27.8 1.0020 0.0043 1057400200041 28.4 1.005 0.013 1057400200042 29.6 1.0017 0.0095 1057400200043 30.6 30.9 0.9962 0.0050 1. 1057400200044 32.1 0.9984 0.0030 1057400200045 33.5 0.9967 0.0037 1057400200046 34.4 34.8 1.0024 0.0065 1. 1057400200047 35.2 1.0013 0.0020 1057400200048 39.4 0.9985 0.0033 1057400200049 41.3 42.75 0.9987 0.0035 1057400200050 43.4 45.85 0.9972 0.0030 1057400200051 47.0 47.0 1.0015 0.0039 1. 1057400200052 48.0 49.44 1.0003 0.0033 1057400200053 50.5 52.24 0.9984 0.0019 1057400200054 55.1 56.53 0.9996 0.0018 1057400200055 57.8 58.73 0.9930 0.0033 1057400200056 59.8 61.24 0.9918 0.0039 1057400200057 63.6 64.3 0.9950 0.0057 1. 1057400200058 65.8 67.33 1.0126 0.0085 1057400200059 69.3 72.95 1.0005 0.0024 1057400200060 74.6 76.74 0.9978 0.0034 1057400200061 82.7 85.05 0.9994 0.0034 1057400200062 88.8 0.9992 0.0048 1057400200063 89.8 93.26 0.9996 0.0037 1057400200064 94.1 99.66 0.9997 0.0038 1057400200065 100.4 111.717 0.9988 0.0028 1057400200066 113.6 118.75 0.9928 0.0033 1057400200067 122.0 0.9930 0.0043 1057400200068 123.6 128.28 0.9993 0.0037 1057400200069 ENDDATA 58 0 1057400200070 ENDSUBENT 69 0 1057400299999 SUBENT 10574003 20040702 00001057400300001 BIB 3 4 1057400300002 REACTION (92-U-235(N,F),,NU,,REL/AV) 1057400300003 ANALYSIS Data given relative to average nu value over incident 1057400300004 neutron energies from 0.52 to 114. eV. 1057400300005 ERR-ANALYS No information on uncertainties. 1057400300006 ENDBIB 4 0 1057400300007 COMMON 1 3 1057400300008 DATA-ERR 1057400300009 ARB-UNITS 1057400300010 0.0016 1057400300011 ENDCOMMON 3 0 1057400300012 DATA 3 20 1057400300013 EN-MIN EN-MAX DATA 1057400300014 EV EV ARB-UNITS 1057400300015 0.52 0.76 1.0051 1057400300016 0.77 1.06 1.0052 1057400300017 1.07 1.43 0.9983 1057400300018 1.44 3.52 1.0007 1057400300019 3.53 6.92 0.9997 1057400300020 6.93 8.78 1.0028 1057400300021 8.79 9.02 1.0056 1057400300022 9.03 12.2 1.0006 1057400300023 12.3 14.0 0.9969 1057400300024 14.1 18.6 0.9960 1057400300025 18.7 19.5 0.9968 1057400300026 19.6 23.7 0.9975 1057400300027 23.8 28.7 1.0018 1057400300028 28.8 35.0 0.9995 1057400300029 35.1 41.5 1.0009 1057400300030 41.6 50.8 0.9995 1057400300031 50.9 56.1 0.9988 1057400300032 56.2 65.4 0.9953 1057400300033 65.5 84.2 1.0004 1057400300034 84.3 114. 0.9988 1057400300035 ENDDATA 22 0 1057400300036 ENDSUBENT 35 0 1057400399999 ENDENTRY 3 0 1057499999999