ENTRY 12369 20131029 13981236900000001
SUBENT 12369001 20131029 13981236900100001
BIB 6 13 1236900100002
TITLE Search for Structure in the Fast-Neutron Interaction 1236900100003
with U-235 1236900100004
AUTHOR (A.B.Smith,J.F.Whalen) 1236900100005
REFERENCE (J,PRL,16,525,1966) 1236900100006
#doi:10.1103/PhysRevLett.16.525 1236900100007
INSTITUTE (1USAANL) 1236900100008
FACILITY (VDG,1USAANL) 1236900100009
HISTORY (19761006C) 1236900100010
(19820519A) Converted to reaction formalism 1236900100011
(20131029A) BP: Updated to new date formats,lower 1236900100012
case. Corrections according last EXFOR rules and Dict. 1236900100013
Digitized Figs. 1-2, corrected reaction string and 1236900100014
updated the BIB section. 1236900100015
ENDBIB 13 0 1236900100016
NOCOMMON 0 0 1236900100017
ENDSUBENT 16 0 1236900199999
SUBENT 12369002 20131029 13981236900200001
BIB 6 21 1236900200002
REACTION (92-U-235(N,SCT)92-U-235,PAR,SIG) 1236900200003
METHOD (TOF) The first type of measurement employed fast 1236900200004
time-of-flight techniques to determine the 1236900200005
differential elastic-scattering cross sections of 1236900200006
U-235 at 10-keV intervals for 0.4 to 0.6 MeV. 1236900200007
Measurements were made at 8 angles between 25 and 150 1236900200008
deg with incident-neutron resolution of 20 keV and 1236900200009
scattered-neutron resolutions of 25 keV. All measured 1236900200010
neutrons within the scattered resolution function 1236900200011
were considered due to elastic processes. 1236900200012
MONITOR (6-C-12(N,SCT)6-C-12,,SIG) 1236900200013
ANALYSIS (4PI1A) The measured values were normalized to the 1236900200014
known differential scattering cross sections of 1236900200015
carbon, corrected for multiple scattering, and 1236900200016
expressed as a Legendre expansion. 1236900200017
ERR-ANALYS (DATA-ERR) The indicated errors represent relative 1236900200018
experimental uncertainties and do not include 1236900200019
possible systematic effects due to the normalization. 1236900200020
STATUS (CURVE) Fig.2, page 526. 1236900200021
(COREL,10233002) Data presented by the author without 1236900200022
energy dependent uncertainty 1236900200023
ENDBIB 21 0 1236900200024
COMMON 1 3 1236900200025
Q-VAL-MIN 1236900200026
KEV 1236900200027
-25. 1236900200028
ENDCOMMON 3 0 1236900200029
DATA 4 20 1236900200030
EN EN-ERR DATA DATA-ERR 1236900200031
MEV MEV B B 1236900200032
0.401 0.009 5.653 0.239 1236900200033
0.420 0.009 5.535 0.239 1236900200034
0.430 0.008 5.728 0.225 1236900200035
0.441 0.009 5.627 0.211 1236900200036
0.451 0.009 5.413 0.239 1236900200037
0.460 0.008 5.762 0.253 1236900200038
0.471 0.006 5.773 0.267 1236900200039
0.480 0.008 5.658 0.253 1236900200040
0.491 0.006 5.795 0.253 1236900200041
0.501 0.008 5.821 0.253 1236900200042
0.510 0.008 5.649 0.253 1236900200043
0.521 0.009 5.815 0.267 1236900200044
0.530 0.007 5.742 0.253 1236900200045
0.540 0.008 5.837 0.239 1236900200046
0.550 0.010 5.637 0.253 1236900200047
0.560 0.008 5.634 0.239 1236900200048
0.570 0.008 5.435 0.239 1236900200049
0.581 0.006 5.418 0.239 1236900200050
0.590 0.007 5.387 0.253 1236900200051
0.600 0.009 5.299 0.239 1236900200052
ENDDATA 22 0 1236900200053
ENDSUBENT 52 0 1236900299999
SUBENT 12369003 20131029 13981236900300001
BIB 5 21 1236900300002
REACTION (92-U-235(N,F),,SIG) 1236900300003
MONITOR (92-U-235(N,F),,SIG) 1236900300004
Arbitrarily normalized to 1.25 B at 0.4 MeV. 1236900300005
METHOD The second experiment determined the relative fission 1236900300006
cross section of U-235 from 0.36 to 0.65 MeV. The 1236900300007
measurements were made with an automated facility 1236900300008
including digital computer control of a Van de Graaff 1236900300009
accelerator and all requisite experimental equipment. 1236900300010
The facility was programmed to determine the ratio of 1236900300011
the response of a U-235 fission counter to that of a 1236900300012
long counter with a preset statistical uncertainty 1236900300013
and at specified neutron energies. The facility was 1236900300014
programmed to determine the ratio of the response of 1236900300015
a U-235 fission counter to that of a long counter 1236900300016
with a preset statistical uncertainty and at 1236900300017
specified neutron energies. The incident resolution 1236900300018
was <=15 keV and measurements were made at 5-keV 1236900300019
intervals throughout the incident energy range. 1236900300020
Neutron emission angle was 15 degrees. 1236900300021
ERR-ANALYS (ERR-S) Counting statistics was 3 percent. 1236900300022
STATUS (CURVE) Fig.1 (B), page 526. 1236900300023
ENDBIB 21 0 1236900300024
COMMON 3 3 1236900300025
EN-NRM MONIT ERR-S 1236900300026
MEV B PER-CENT 1236900300027
0.4 1.25 3.0 1236900300028
ENDCOMMON 3 0 1236900300029
DATA 2 66 1236900300030
EN DATA 1236900300031
MEV B 1236900300032
0.380 1.288 1236900300033
0.385 1.214 1236900300034
0.389 1.243 1236900300035
0.391 1.212 1236900300036
0.395 1.242 1236900300037
0.396 1.190 1236900300038
0.400 1.241 1236900300039
0.401 1.220 1236900300040
0.405 1.230 1236900300041
0.410 1.146 1236900300042
0.412 1.198 1236900300043
0.415 1.239 1236900300044
0.420 1.197 1236900300045
0.425 1.217 1236900300046
0.430 1.206 1236900300047
0.435 1.174 1236900300048
0.440 1.267 1236900300049
0.445 1.224 1236900300050
0.450 1.349 1236900300051
0.451 1.265 1236900300052
0.455 1.285 1236900300053
0.460 1.285 1236900300054
0.462 1.274 1236900300055
0.465 1.232 1236900300056
0.470 1.262 1236900300057
0.475 1.241 1236900300058
0.480 1.250 1236900300059
0.485 1.177 1236900300060
0.490 1.270 1236900300061
0.495 1.186 1236900300062
0.500 1.237 1236900300063
0.505 1.216 1236900300064
0.510 1.194 1236900300065
0.516 1.204 1236900300066
0.520 1.276 1236900300067
0.521 1.234 1236900300068
0.525 1.275 1236900300069
0.529 1.202 1236900300070
0.530 1.160 1236900300071
0.535 1.190 1236900300072
0.540 1.200 1236900300073
0.545 1.262 1236900300074
0.549 1.178 1236900300075
0.555 1.167 1236900300076
0.559 1.208 1236900300077
0.560 1.145 1236900300078
0.565 1.196 1236900300079
0.570 1.227 1236900300080
0.575 1.268 1236900300081
0.580 1.246 1236900300082
0.584 1.246 1236900300083
0.590 1.193 1236900300084
0.595 1.223 1236900300085
0.599 1.233 1236900300086
0.605 1.191 1236900300087
0.610 1.169 1236900300088
0.614 1.189 1236900300089
0.619 1.157 1236900300090
0.626 1.135 1236900300091
0.629 1.187 1236900300092
0.634 1.207 1236900300093
0.639 1.175 1236900300094
0.644 1.226 1236900300095
0.650 1.163 1236900300096
0.655 1.214 1236900300097
0.657 1.214 1236900300098
ENDDATA 68 0 1236900300099
ENDSUBENT 98 0 1236900399999
SUBENT 12369004 20131127 13981236900400001
BIB 6 21 1236900400002
REACTION (92-U-235(N,F),,SIG) 1236900400003
MONITOR Arbitrarily normalized to 1.25 B at 0.4 MeV. 1236900400004
METHOD The second experiment determined the relative fission 1236900400005
cross section of U-235 from 0.36 to 0.65 MeV. The 1236900400006
measurements were made with an automated facility 1236900400007
including digital computer control of a Van de Graaff 1236900400008
accelerator and all requisite experimental equipment. 1236900400009
The facility was programmed to determine the ratio of 1236900400010
the response of a U-235 fission counter to that of a 1236900400011
long counter with a preset statistical uncertainty 1236900400012
and at specified neutron energies. The facility was 1236900400013
programmed to determine the ratio of the response of 1236900400014
a U-235 fission counter to that of a long counter 1236900400015
with a preset statistical uncertainty and at 1236900400016
specified neutron energies. The incident resolution 1236900400017
was <=15 keV and measurements were made at 5-keV 1236900400018
intervals throughout the incident energy range. 1236900400019
Neutron emission angle was 0 degrees. 1236900400020
ERR-ANALYS (ERR-S) Counting statistics was 2 percent. 1236900400021
STATUS (CURVE) Fig.1 (C), page 526. 1236900400022
HISTORY (20131127C) 1236900400023
ENDBIB 21 0 1236900400024
COMMON 3 3 1236900400025
EN-NRM MONIT ERR-S 1236900400026
MEV B PER-CENT 1236900400027
0.4 1.25 2.0 1236900400028
ENDCOMMON 3 0 1236900400029
DATA 2 56 1236900400030
EN DATA 1236900400031
MEV B 1236900400032
0.379 1.165 1236900400033
0.385 1.202 1236900400034
0.389 1.202 1236900400035
0.395 1.201 1236900400036
0.400 1.177 1236900400037
0.405 1.188 1236900400038
0.409 1.187 1236900400039
0.414 1.244 1236900400040
0.419 1.197 1236900400041
0.425 1.220 1236900400042
0.429 1.242 1236900400043
0.434 1.276 1236900400044
0.440 1.287 1236900400045
0.445 1.286 1236900400046
0.450 1.297 1236900400047
0.455 1.285 1236900400048
0.460 1.249 1236900400049
0.465 1.260 1236900400050
0.470 1.248 1236900400051
0.475 1.212 1236900400052
0.480 1.223 1236900400053
0.485 1.257 1236900400054
0.490 1.268 1236900400055
0.495 1.279 1236900400056
0.499 1.243 1236900400057
0.505 1.219 1236900400058
0.509 1.242 1236900400059
0.514 1.229 1236900400060
0.520 1.205 1236900400061
0.525 1.193 1236900400062
0.530 1.250 1236900400063
0.534 1.203 1236900400064
0.540 1.260 1236900400065
0.545 1.202 1236900400066
0.550 1.259 1236900400067
0.555 1.270 1236900400068
0.560 1.234 1236900400069
0.565 1.176 1236900400070
0.570 1.268 1236900400071
0.574 1.267 1236900400072
0.580 1.196 1236900400073
0.586 1.196 1236900400074
0.590 1.265 1236900400075
0.595 1.241 1236900400076
0.600 1.170 1236900400077
0.605 1.181 1236900400078
0.610 1.227 1236900400079
0.616 1.180 1236900400080
0.621 1.202 1236900400081
0.626 1.190 1236900400082
0.630 1.247 1236900400083
0.636 1.177 1236900400084
0.641 1.164 1236900400085
0.645 1.222 1236900400086
0.650 1.221 1236900400087
0.655 1.244 1236900400088
ENDDATA 58 0 1236900400089
ENDSUBENT 88 0 1236900499999
ENDENTRY 4 0 1236999999999