ENTRY 14570 20200421 14881457000000001 SUBENT 14570001 20200421 14881457000100001 BIB 10 37 1457000100002 TITLE Expansion of the surrogate method to measure the 1457000100003 prompt fission neutron multiplicity for 241Pu 1457000100004 AUTHOR (O.A.Akindele,B.S.Alan,J.T.Burke,R.J.Casperson, 1457000100005 R.O.Hughes,J.D.Koglin,K.Kolos,E.B.Norman,S.Ota, 1457000100006 A.Saastamoinen) 1457000100007 INSTITUTE (1USAUCX,1USALRL,1USATAM) 1457000100008 REFERENCE (J,PR/C,99,054601,2019) 1457000100009 FACILITY (CYCLO,1USATAM) Experiment was performed at the Texas 1457000100010 A&M University Cyclotron Institute 1457000100011 SAMPLE (94-PU-238,ENR=0.00003) 1457000100012 (94-PU-239,ENR=0.00005) 1457000100013 (94-PU-240,ENR=0.00021) 1457000100014 (94-PU-241,ENR=0.00006) 1457000100015 (94-PU-242,ENR=0.99952) 1457000100016 (94-PU-240,ENR=0.00021) 1457000100017 (95-AM-241,ENR=0.00013) Target was made by 1457000100018 electroplating of 242Pu onto 100 mu-g/cm2 thick 1457000100019 natural carbon backing. Target thickness was 1457000100020 140 mu-g/cm2. 1457000100021 DETECTOR (TELES,SI,SI) Scattered alpha particles were detected 1457000100022 using dE-E silicon telescope located downstream of the 1457000100023 242Pu target. 1457000100024 (SI) Another Si detector was located upstream of the 1457000100025 target to identify fission events. 1457000100026 (SCIN) A large cylindrical tank containing 2.2 tons 1457000100027 of EJ-335 liquid scintillator was used to detect 1457000100028 neutrons. Tank was segmented into four quadrants. 1457000100029 Neutron detection efficiency was determined to be 1457000100030 (50.81+-0.15)% 1457000100031 METHOD Surrogate method was used. Reaction 1457000100032 n + 241Pu -> 242Pu* -> FL + FH + nu*N 1457000100033 was replaced by reaction 1457000100034 a + 242Pu -> 242Pu* + a' -> FL + FH + nu*N 1457000100035 (a' -> inelastically scattered alpha particle) 1457000100036 assuming Bohr independence hypothesis 1457000100037 ANALYSIS (SURGT) 1457000100038 HISTORY (20200421C) Compiled by S.H. 1457000100039 ENDBIB 37 0 1457000100040 NOCOMMON 0 0 1457000100041 ENDSUBENT 40 0 1457000199999 SUBENT 14570002 20200421 14881457000200001 BIB 3 8 1457000200002 REACTION (94-PU-241(N,F),,NU) 1457000200003 Average neutron multiplicity for 241Pu(n,f) reaction 1457000200004 ERR-ANALYS (ERR-T) Total uncertainties 1457000200005 (ERR-1) Uncertainty in neutron detection efficiency 1457000200006 (ERR-2) Additional systematic uncertainty due to energy1457000200007 dependence of neutron detection efficiency 1457000200008 STATUS (TABLE) Data presented in fig. 7 of the reference 1457000200009 sent by author O.A.A. 1457000200010 ENDBIB 8 0 1457000200011 COMMON 3 3 1457000200012 EN-ERR ERR-1 ERR-2 1457000200013 MEV PER-CENT PER-CENT 1457000200014 0.25 0.15 1. 1457000200015 ENDCOMMON 3 0 1457000200016 DATA 3 41 1457000200017 EN DATA ERR-T 1457000200018 MEV PRT/FIS PRT/FIS 1457000200019 0.0 2.90 0.118 1457000200020 0.5 2.92 0.094 1457000200021 1.0 2.88 0.100 1457000200022 1.5 3.17 0.112 1457000200023 2.0 3.09 0.108 1457000200024 2.5 3.16 0.111 1457000200025 3.0 3.25 0.117 1457000200026 3.5 3.37 0.124 1457000200027 4.0 3.43 0.126 1457000200028 4.5 3.49 0.128 1457000200029 5.0 3.54 0.134 1457000200030 5.5 3.72 0.142 1457000200031 6.0 3.70 0.142 1457000200032 6.5 3.85 0.146 1457000200033 7.0 3.85 0.145 1457000200034 7.5 4.17 0.149 1457000200035 8.0 4.05 0.141 1457000200036 8.5 4.05 0.142 1457000200037 9.0 4.16 0.147 1457000200038 9.5 4.19 0.150 1457000200039 10.0 4.30 0.155 1457000200040 10.5 4.26 0.155 1457000200041 11.0 4.54 0.164 1457000200042 11.5 4.46 0.166 1457000200043 12.0 4.46 0.171 1457000200044 12.5 4.51 0.174 1457000200045 13.0 4.64 0.178 1457000200046 13.5 4.70 0.180 1457000200047 14.0 4.83 0.177 1457000200048 14.5 4.85 0.182 1457000200049 15.0 4.82 0.182 1457000200050 15.5 5.05 0.183 1457000200051 16.0 4.95 0.189 1457000200052 16.5 5.00 0.184 1457000200053 17.0 5.19 0.191 1457000200054 17.5 5.18 0.194 1457000200055 18.0 5.27 0.194 1457000200056 18.5 5.06 0.191 1457000200057 19.0 5.22 0.195 1457000200058 19.5 5.39 0.199 1457000200059 20.0 5.46 0.207 1457000200060 ENDDATA 43 0 1457000200061 ENDSUBENT 60 0 1457000299999 ENDENTRY 2 0 1457099999999