ENTRY            30753   20090908                             31413075300000001 
SUBENT        30753001   20090908                             31413075300100001 
BIB                 15         86                                 3075300100002 
TITLE      Measurement of the 235-U/238-U fission cross section   3075300100003 
           ratio in the 235-U fission neutron spectrum            3075300100004 
AUTHOR     (D.Azimi-Garakani,M.Bagheri-Darbandi)                  3075300100005 
INSTITUTE  (3IRNTEH)                                              3075300100006 
REFERENCE  (R,INDC(IRN)-003,198306)                               3075300100007 
FACILITY   (REAC,3IRNTEH)                                         3075300100008 
INC-SOURCE The neutrons originated from the reactor core are      3075300100009 
           slowed down in a graphite thermal column and collimated3075300100010 
           The collimated neutron beam impinges on a 235-U fission3075300100011 
           plate and produces fast fission neutrons which are used3075300100012 
           as source to hit the sample                            3075300100013 
SAMPLE     Six fissionable deposits were used as samples.The      3075300100014 
           deposits were 20-mm-diam vacuum evaporated on backings 3075300100015 
           of 32 mm diam polished platinum 0.125 mm thick.The mass3075300100016 
           assay of the deposits is as follows:                   3075300100017 
           Foil            Principal   Mass of                    3075300100018 
           identification  isotope     principal isotope          3075300100019 
           UT-51           235-U       79.7  +- 0.4               3075300100020 
           UT-52           235-U       264.8 +- 1.3               3075300100021 
           UT-53           235-U       729.5 +- 4.0               3075300100022 
           UT-81           238-U       81.9  +- 2.5               3075300100023 
           UT-82           238-U       276.1 +- 8.3               3075300100024 
           UT-83           238-U       777.0 +- 23.0              3075300100025 
           The isotopic concentration of the deposits UT-51,UT-52 3075300100026 
           and UT-53 is as follows                                3075300100027 
                         1.179 % of 234-U                         3075300100028 
                        93.197 % of 235-U                         3075300100029 
                         0.250 % of 236-U                         3075300100030 
                         5.435 % of 238-U                         3075300100031 
           The isotopic concentration of the deposits UT-81,UT-82 3075300100032 
           and UT-83 is as follows                                3075300100033 
                         0.005 % of 235-U                         3075300100034 
                        99.995 % of 238-U                         3075300100035 
INC-SPECT  The incident-projectile beam is a product of the       3075300100036 
           reaction 235-U(n,f) as explained under INC-SOURCE      3075300100037 
DETECTOR   (TRD) 12 Makrofol solid state nuclear track            3075300100038 
           detectors were used. Six of the Makrofol films were    3075300100039 
           0.025 mm thick (thin films) and the rest were 0.06 mm  3075300100040 
           thick (thick  films)                                   3075300100041 
METHOD     The 235-U/238-U fission cross section ratio was        3075300100042 
           measured in the fast neutron field using Makrofol      3075300100043 
           solid state nuclear track detectors.The track detectors3075300100044 
           were irradiated with the UT enriched and depleted      3075300100045 
           deposits, and after the etching they were counted by an3075300100046 
           optical microscope                                     3075300100047 
CORRECTION The corrections applied to the isotopic fission rates  3075300100048 
           include the absorption of fission fragments in the     3075300100049 
           deposits, fission in other isotopes where the          3075300100050 
           corrections are 0.9863 and 0.9998 for 235-U and 238-U  3075300100051 
           respectively,neutron scattering and absorption and flux3075300100052 
           perturbation caused by the hydrogen in the Makrofol    3075300100053 
ERR-ANALYS (DATA-ERR) The combined uncertainty ascribed to the    3075300100054 
           observed number of tracks per unit area arises from    3075300100055 
           the possible sources of systematic errors which are    3075300100056 
           track counting statistics,background,exposure          3075300100057 
           timing,irradiation positioning,imperfect contact       3075300100058 
           between deposit and the solid state nuclear track      3075300100059 
           detector,radial uniformity of the fission sources      3075300100060 
           and calibration of the microscope field of view.       3075300100061 
           Other possible systematic errors such as integrity     3075300100062 
           of the deposits,flux perturbation by the specimen      3075300100063 
           holder, track overlap, variation of track density      3075300100064 
           with etching time and temperature and uncertainty      3075300100065 
           in the etchant concentration are all assumed to be     3075300100066 
           negligible. The uncertainties assigned to the          3075300100067 
           235-U/238-U fission ratios include uncertainties in    3075300100068 
           mass per unit area(mass assay errors, deposit area),   3075300100069 
           uncertainties in corrections  (see under correction)   3075300100070 
           and uncertainties in count ratios                      3075300100071 
COMMENT    The following values of the 235-U/238-U fission cross  3075300100072 
           section ratio show that there is no significant        3075300100073 
           difference with the thin and the thick films.          3075300100074 
           Detector       Foil             235-U/238-U fission    3075300100075 
                          identification   cross section ratio    3075300100076 
           Thin Makrofol  UT-51/UT-81      3.78 +- 0.3            3075300100077 
           Thin Makrofol  UT-52/UT-82      3.48 +- 0.2            3075300100078 
           Thin Makrofol  UT-53/UT-83      4.15 +- 0.23           3075300100079 
           Thick Makrofol  UT-51/UT-81      3.79 +- 0.32          3075300100080 
           Thick Makrofol UT-52/UT-82      3.70 +- 0.19           3075300100081 
           Thick Makrofol UT-53/UT-83      4.10 +- 0.2            3075300100082 
           The average 235-U/238-U fission cross section ratio is 3075300100083 
                              3.83 +- 0.25                        3075300100084 
STATUS     (TABLE) Data averaged taken from Table V, page 7 in    3075300100085 
           report INDC(IRN)-003, 1983                             3075300100086 
HISTORY    (19870715C)MR-                                         3075300100087 
           (20090725A) SD:Updated to new date formats,lower case. 3075300100088 
ENDBIB              86          0                                 3075300100089 
COMMON               1          3                                 3075300100090 
EN-DUMMY                                                          3075300100091 
MEV                                                               3075300100092 
1.5                                                               3075300100093 
ENDCOMMON            3          0                                 3075300100094 
ENDSUBENT           93          0                                 3075300199999 
SUBENT        30753002   20090908                             31413075300200001 
BIB                  1          1                                 3075300200002 
REACTION   ((92-U-235(N,F),,SIG,,SPA)/(92-U-238(N,F),,SIG,,SPA))  3075300200003 
ENDBIB               1          0                                 3075300200004 
NOCOMMON             0          0                                 3075300200005 
DATA                 2          1                                 3075300200006 
DATA       DATA-ERR                                               3075300200007 
NO-DIM     NO-DIM                                                 3075300200008 
3.83       0.25                                                   3075300200009 
ENDDATA              3          0                                 3075300200010 
ENDSUBENT            9          0                                 3075300299999 
ENDENTRY             2          0                                 3075399999999