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