ENTRY 30974 20090912 3097400000001
SUBENT 30974001 20090915 20100105 3097400100001
BIB 15 59 3097400100002
TITLE Measurement of absolute fission rate of natural 3097400100003
depleted uranium and thorium and microscopic cross 3097400100004
section ratios in the radial beam of the RA3. 3097400100005
AUTHOR (M.Bovisio de Ricabarra,L.Cohen de Porto,D.Walsman, 3097400100006
G.H.Ricabarra) 3097400100007
INSTITUTE (3ARGCNE) 3097400100008
REFERENCE (C,88MITO,,123,198806) 3097400100009
FACILITY (REAC,3ARGCNE) 3097400100010
SAMPLE 100 - 200 microgram/cm**2 thin deposits of natural- 3097400100011
and depleted-uranium-(23ppm U-235) oxide (U3O8) and 3097400100012
thorium-232 oxide (ThO2) were prepared by molecular 3097400100013
plating on polished aluminium disks as to ensure 3097400100014
adequate deposit uniformity. The masses were deter- 3097400100015
mined by alpha-counting assay (uranium) and gamma- 3097400100016
counting assay (thorium). 3097400100017
Indium-115: no further details are given of this 3097400100018
sample. 3097400100019
DETECTOR (FISCH,TRD,D4PI,GELI) A miniature fission chamber 3097400100020
and a solid-state nuclear track detector (SSNTD) for 3097400100021
fission fragment counting, a 4Pi-beta proportional 3097400100022
gas flow counter for determining the beta activity of 3097400100023
Mn-56 and a GeLi detector for measuring the gamma 3097400100024
activities of Mn-56 and In-115-m. The aluminium 3097400100025
electroplated deposit is the grounded kathode plate of 3097400100026
the fission chamber. In the SSNTD measurements the 3097400100027
deposits are placed in close contact with the mica 3097400100028
disks between a aluminium back plate and a ring holder.3097400100029
METHOD (EXTB,ACTIV) External beam irradiation of SSNTD and 3097400100030
fission chamber, activation measurement of the 3097400100031
In-115(n,n)In-115-m reaction relative to Mn monitor. 3097400100032
INC-SOURCE (REAC) Radial neutron beam of the RA3 research reactor 3097400100033
PART-DET (FF) 3097400100034
ANALYSIS (DECAY) For In-115(n,n)In-115-m reaction. 3097400100035
From the experimentally determined fission-rate 3097400100036
ratios: depleted uranium/natural uranium and 3097400100037
thorium-232/depleted uranium, and the In-115-m/Mn-56 3097400100038
cross section ratios the ratios presented in subents 3097400100039
002 - 005 were obtained. 3097400100040
CORRECTION Corrections have been made for fission fragment self- 3097400100041
absorption in the deposits, flux perturbation in 3097400100042
the neutron beam and ssntd stack absorption. 3097400100043
ERR-ANALYS (ERR-T) Errors are obtained by quadrature sum of 3097400100044
independent error components: 3097400100045
1) Statistics of fission product counting and 3097400100046
systematic errors in fission fragment absorption 3097400100047
corrections, the same for alphas in uranium mass 3097400100048
assay. 3097400100049
2) Statistics of gamma counting uncertainty 3097400100050
and self-absorption for thorium mass assay. 3097400100051
3) Statistics of gamma counting errors and gamma 3097400100052
efficiency calibrations for In-115-m/Mn56 ratio. 3097400100053
HISTORY (19920127C) HW 3097400100054
(19930922A) HW.-Status altered and 'Monitor' removed in3097400100055
sub 001, data in sub 002 corrected, sub 003 altered, 3097400100056
'Inc-spect' moved from sub 001 to sub 002 - 005.- 3097400100057
(19940308U) HW.-Correction in Decay-data of subent 002.3097400100058
(20090912A) SD:Updated to new date formats,lower case. 3097400100059
STATUS (TABLE) Data are taken from Tables 7 and 8 of Conf. on 3097400100060
Nuclear Data for Sci. and Technol.,Mito,1988,p.123. 3097400100061
ENDBIB 59 0 3097400100062
NOCOMMON 0 0 3097400100063
ENDSUBENT 62 0 3097400199999
SUBENT 30974002 20090915 20100105 3097400200001
BIB 4 12 3097400200002
REACTION ((49-IN-115(N,INL)49-IN-115-M,,SIG,,SPA)/ 3097400200003
(25-MN-55(N,G)25-MN-56,,SIG,,SPA)) 3097400200004
DECAY-DATA (25-MN-56,2.5785HR,DG,847.,.989) 3097400200005
(49-IN-115-M,4.486HR,DG,336.) 3097400200006
INC-SPECT The neutron beam was assumed to have a Maxwellian 3097400200007
thermal component, a 1/E epithermal region and a fast 3097400200008
region with a neutron fission shape (200keV