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