ENTRY 13964 20210920 14871396400000001 SUBENT 13964001 20210920 14871396400100001 BIB 11 27 1396400100002 INSTITUTE (2FR BRC,1USALAS) 1396400100003 REFERENCE (J,PRL,94,052701,2005) 1396400100004 (C,2004SANTA,1,656,2004) 1396400100005 AUTHOR (T.Ethvignot,M.Devlin,H.Duarte,T.Granier,R.C.Haight, 1396400100006 B.Morillon,R.O.Nelson,J.M.O'Donnell,D.Rochman) 1396400100007 TITLE Neutron Multiplicity in the Fission of 238U and 235U 1396400100008 with Neutrons up to 200 MeV 1396400100009 FACILITY (ACCEL,1USALAS) FIGARO beam line installed at the 1396400100010 Weapons Neutron Research Center at the Los 1396400100011 Alamos Neutron Science Center (LANSCE) 1396400100012 INC-SOURCE (SPALL) Spallation neutron source. 1396400100013 INC-SPECT The incident neutron spectrum was similar to a 1396400100014 Maxwellian distribution with a temperature of about 1396400100015 2 MeV and a high energy tail. 1396400100016 DETECTOR (SCIN) 5 Liquid scintillators EJ213, 12.5 cm in 1396400100017 diameter and 5 cm thick coupled to photo-multiplier 1396400100018 tubes. Efficiency was determined from the analysis 1396400100019 of the energy spectrum around 2.9 MeV incident 1396400100020 neutron energy. 1396400100021 METHOD (TOF) Double time-of-flight measurement. 1396400100022 MONITOR Data were normalized between 1.5 and 28 MeV to 1396400100023 J. Frehaut data obtained from a private communication 1396400100024 HISTORY (20050215C) DR 1396400100025 (20050915A) DR Second reference added 1396400100026 (20061102A) DR "PR" added reactions for subentries 2 1396400100027 to 5 and monitor added 1396400100028 (20210824A) OS. REACTION coding in subs.4,5 updated 1396400100029 ENDBIB 27 0 1396400100030 NOCOMMON 0 0 1396400100031 ENDSUBENT 30 0 1396400199999 SUBENT 13964002 20061102 13421396400200001 BIB 5 10 1396400200002 REACTION (92-U-238(N,F),PR/PAR,NU) 1396400200003 Neutron multiplicity 1396400200004 PART-DET (N) Neutron 1396400200005 SAMPLE 94-layer ionization fission chamber, containing 1396400200006 380 mg of pure U238, 10 cm long. Each layer 1396400200007 consists of a stainless steel backing with 1396400200008 deposits of 2 mg of U238 on both sides. 1396400200009 ERR-ANALYS (DATA-ERR) Statistical and systematic uncertainties 1396400200010 are given together. 1396400200011 STATUS (TABLE) Data received by author in tables. 1396400200012 ENDBIB 10 0 1396400200013 COMMON 2 3 1396400200014 E-MIN E-MAX 1396400200015 MEV MEV 1396400200016 0.8 7.5 1396400200017 ENDCOMMON 3 0 1396400200018 DATA 4 33 1396400200019 EN EN-ERR DATA DATA-ERR 1396400200020 MEV MEV PRT/FIS PRT/FIS 1396400200021 1.70 0.016 2.49 0.408 1396400200022 2.03 0.021 2.79 0.457 1396400200023 2.40 0.027 2.89 0.474 1396400200024 2.83 0.035 2.90 0.474 1396400200025 3.38 0.046 2.98 0.488 1396400200026 4.02 0.060 3.02 0.493 1396400200027 4.78 0.077 3.38 0.552 1396400200028 5.72 0.102 3.32 0.542 1396400200029 6.63 0.127 3.05 0.500 1396400200030 7.53 0.154 3.36 0.550 1396400200031 8.65 0.189 3.43 0.562 1396400200032 10.13 0.241 3.69 0.604 1396400200033 12.31 0.323 4.15 0.679 1396400200034 15.05 0.438 4.30 0.703 1396400200035 18.14 0.580 4.90 0.801 1396400200036 21.64 0.759 5.22 0.853 1396400200037 25.37 0.966 5.60 0.917 1396400200038 29.48 1.214 6.01 0.983 1396400200039 33.86 1.500 6.54 1.070 1396400200040 38.53 1.827 6.97 1.141 1396400200041 43.64 2.211 7.38 1.206 1396400200042 49.29 2.666 7.91 1.293 1396400200043 55.47 3.197 8.16 1.334 1396400200044 62.18 3.815 8.53 1.396 1396400200045 69.63 4.547 8.89 1.455 1396400200046 78.15 5.442 9.26 1.515 1396400200047 87.57 6.502 9.49 1.553 1396400200048 98.25 7.790 10.09 1.651 1396400200049 110.31 9.352 10.35 1.693 1396400200050 124.00 11.261 10.85 1.775 1396400200051 140.05 13.679 11.16 1.825 1396400200052 159.07 16.793 11.76 1.923 1396400200053 181.65 20.834 12.27 2.006 1396400200054 ENDDATA 35 0 1396400200055 ENDSUBENT 54 0 1396400299999 SUBENT 13964003 20061102 13421396400300001 BIB 5 7 1396400300002 REACTION (92-U-235(N,F),PR/PAR,NU) 1396400300003 Neutron multiplicity 1396400300004 PART-DET (N) Neutron 1396400300005 SAMPLE U235 Fission chamber 1396400300006 ERR-ANALYS (DATA-ERR) Statistical and systematic uncertainties 1396400300007 are given together. 1396400300008 STATUS (TABLE) Data received by author in tables. 1396400300009 ENDBIB 7 0 1396400300010 COMMON 2 3 1396400300011 E-MIN E-MAX 1396400300012 MEV MEV 1396400300013 0.8 7.5 1396400300014 ENDCOMMON 3 0 1396400300015 DATA 4 35 1396400300016 EN EN-ERR DATA DATA-ERR 1396400300017 MEV MEV PRT/FIS PRT/FIS 1396400300018 0.412 0.002 2.349 0.353 1396400300019 0.683 0.004 2.266 0.340 1396400300020 0.909 0.006 2.413 0.362 1396400300021 1.128 0.008 2.461 0.369 1396400300022 1.358 0.011 2.446 0.367 1396400300023 1.609 0.015 2.591 0.389 1396400300024 1.882 0.019 2.667 0.400 1396400300025 2.188 0.024 2.673 0.401 1396400300026 2.539 0.030 2.865 0.430 1396400300027 2.970 0.038 2.813 0.422 1396400300028 3.523 0.049 2.835 0.426 1396400300029 4.208 0.064 3.002 0.451 1396400300030 5.021 0.083 3.149 0.473 1396400300031 6.027 0.110 3.217 0.483 1396400300032 6.995 0.137 3.302 0.496 1396400300033 8.008 0.169 3.573 0.537 1396400300034 9.202 0.208 3.749 0.563 1396400300035 10.829 0.266 4.018 0.603 1396400300036 13.087 0.354 4.068 0.611 1396400300037 15.789 0.470 4.558 0.685 1396400300038 19.292 0.637 4.850 0.728 1396400300039 23.579 0.864 5.443 0.818 1396400300040 28.381 1.145 5.935 0.892 1396400300041 33.696 1.488 6.475 0.973 1396400300042 39.656 1.909 6.777 1.018 1396400300043 46.363 2.426 7.334 1.102 1396400300044 53.969 3.065 7.831 1.177 1396400300045 62.705 3.864 8.212 1.234 1396400300046 72.842 4.876 8.782 1.320 1396400300047 84.715 6.172 9.085 1.365 1396400300048 98.635 7.837 9.628 1.447 1396400300049 114.831 9.966 10.064 1.512 1396400300050 134.062 12.754 10.783 1.620 1396400300051 157.673 16.554 11.261 1.692 1396400300052 186.967 21.839 11.821 1.776 1396400300053 ENDDATA 37 0 1396400300054 ENDSUBENT 53 0 1396400399999 SUBENT 13964004 20210920 14871396400400001 BIB 5 10 1396400400002 REACTION (92-U-238(N,F)0-NN-1,PR/PAR,KE) Neutron average energy 1396400400003 and standard deviation. 1396400400004 SAMPLE 94-layer ionization fission chamber, containing 1396400400005 380 mg of pure U238, 10 cm long. Each layer 1396400400006 consists of a stainless steel backing with 1396400400007 deposits of 2 mg of U238 on both sides. 1396400400008 ERR-ANALYS (DATA-ERR) Statistical and systematic uncertainties 1396400400009 are given together. 1396400400010 STATUS (TABLE) Data received by author in tables. 1396400400011 HISTORY (20210824A) REACTION coding corrected 1396400400012 ENDBIB 10 0 1396400400013 COMMON 2 3 1396400400014 E-MIN E-MAX 1396400400015 MEV MEV 1396400400016 0.8 7.5 1396400400017 ENDCOMMON 3 0 1396400400018 DATA 4 33 1396400400019 EN EN-ERR DATA DATA-ERR 1396400400020 MEV MEV MEV MEV 1396400400021 1.703 0.016 1.963 0.083 1396400400022 2.037 0.021 1.905 0.070 1396400400023 2.400 0.027 1.964 0.079 1396400400024 2.839 0.035 1.925 0.067 1396400400025 3.382 0.046 1.974 0.078 1396400400026 4.027 0.060 2.074 0.079 1396400400027 4.787 0.077 2.051 0.078 1396400400028 5.728 0.102 2.101 0.088 1396400400029 6.635 0.127 1.939 0.074 1396400400030 7.536 0.154 1.864 0.067 1396400400031 8.652 0.189 1.842 0.073 1396400400032 10.139 0.241 1.935 0.074 1396400400033 12.315 0.323 1.992 0.075 1396400400034 15.057 0.438 1.979 0.075 1396400400035 18.142 0.580 1.981 0.077 1396400400036 21.647 0.759 2.013 0.076 1396400400037 25.372 0.966 1.997 0.078 1396400400038 29.489 1.214 2.019 0.078 1396400400039 33.867 1.500 2.124 0.082 1396400400040 38.538 1.827 2.109 0.084 1396400400041 43.645 2.211 2.090 0.084 1396400400042 49.298 2.666 2.132 0.087 1396400400043 55.472 3.197 2.189 0.098 1396400400044 62.184 3.815 2.181 0.097 1396400400045 69.637 4.547 2.214 0.107 1396400400046 78.157 5.442 2.284 0.106 1396400400047 87.576 6.502 2.270 0.099 1396400400048 98.259 7.790 2.332 0.101 1396400400049 110.319 9.352 2.327 0.116 1396400400050 124.007 11.261 2.383 0.105 1396400400051 140.054 13.679 2.417 0.124 1396400400052 159.074 16.793 2.411 0.118 1396400400053 181.652 20.834 2.482 0.138 1396400400054 ENDDATA 35 0 1396400400055 ENDSUBENT 54 0 1396400499999 SUBENT 13964005 20210920 14871396400500001 BIB 5 7 1396400500002 REACTION (92-U-235(N,F)0-NN-1,PR/PAR,KE) Neutron average energy 1396400500003 and standard deviation. 1396400500004 SAMPLE U238 Fission chamber 1396400500005 ERR-ANALYS (DATA-ERR) Statistical and systematic uncertainties 1396400500006 are given together. 1396400500007 STATUS (TABLE) Data received by author in tables. 1396400500008 HISTORY (20210824A) REACTION coding corrected 1396400500009 ENDBIB 7 0 1396400500010 COMMON 2 3 1396400500011 E-MIN E-MAX 1396400500012 MEV MEV 1396400500013 0.8 7.5 1396400500014 ENDCOMMON 3 0 1396400500015 DATA 4 35 1396400500016 EN EN-ERR DATA DATA-ERR 1396400500017 MEV MEV MEV MEV 1396400500018 0.412 0.002 2.041 0.080 1396400500019 0.683 0.004 2.073 0.084 1396400500020 0.909 0.006 2.086 0.080 1396400500021 1.128 0.008 2.078 0.084 1396400500022 1.358 0.011 2.071 0.079 1396400500023 1.609 0.015 2.067 0.079 1396400500024 1.882 0.019 2.062 0.078 1396400500025 2.188 0.024 2.118 0.082 1396400500026 2.539 0.030 2.016 0.072 1396400500027 2.970 0.038 2.150 0.089 1396400500028 3.523 0.049 2.102 0.079 1396400500029 4.208 0.064 2.120 0.079 1396400500030 5.021 0.083 2.140 0.091 1396400500031 6.027 0.110 2.186 0.085 1396400500032 6.995 0.137 2.139 0.087 1396400500033 8.008 0.169 2.056 0.080 1396400500034 9.202 0.208 2.105 0.080 1396400500035 10.829 0.266 2.119 0.086 1396400500036 13.087 0.354 2.115 0.081 1396400500037 15.789 0.470 2.087 0.094 1396400500038 19.292 0.637 2.246 0.102 1396400500039 23.579 0.864 2.229 0.094 1396400500040 28.381 1.145 2.276 0.100 1396400500041 33.696 1.488 2.295 0.109 1396400500042 39.656 1.909 2.360 0.122 1396400500043 46.363 2.426 2.360 0.120 1396400500044 53.969 3.065 2.429 0.126 1396400500045 62.705 3.864 2.446 0.129 1396400500046 72.842 4.876 2.547 0.134 1396400500047 84.715 6.172 2.533 0.135 1396400500048 98.635 7.837 2.521 0.138 1396400500049 114.831 9.966 2.560 0.129 1396400500050 134.062 12.754 2.584 0.144 1396400500051 157.673 16.554 2.614 0.137 1396400500052 186.967 21.839 2.623 0.137 1396400500053 ENDDATA 37 0 1396400500054 ENDSUBENT 53 0 1396400599999 ENDENTRY 5 0 1396499999999