MIT LMFBR blanket physics project progress report No. 7, July 1, 1975--September 30, 1976 Page: 30 of 187
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-15-
UC^-fueled, stainless-steel-clad, sodium cooled assembly; two.
measurements were made in a U metal-fueled, carbon-steel-clad,
sodium-chromate-moderated assembly: no difference was evident
between the two groups of data. Likewise no difference was
observed when moderately depleted U-238 foils (170 ppm U-235)
were substitute for the usual-highly depleted foils (18 ppm
U-235); 93$ U-235 in aluminum was used throughout the fission
rate measurements - (gross fission products counted >_ 0.72 Mev).
The absolute, ratio was obtained by thermal-spectrum normaliza-
tion, using simultaneous cadmium-ratio-corrected foil irradia-
tions in the hohlraum which drives the blanket facility's
converter. The quoted results are corrected for the difference
between fast and thermal U-235 fission product yields (multi-
plicative factor of 1.033), and the results, which were
measured inside blanket fuel pins at the center of the blanket,
are also "corrected" to the whole-blanket average using the
factor determine by Wu (1) (multiplicative factor of 1.00).
Supplementary measurements made during these studies
included cadmium ratio measurements for U-238 and U-235 in
both the blanket and the thermal neutron hohlraum, with
results as follows:
Cd Ratio
U-238: blanket 0.99 ± 0.05
hohlraum 7.4 ± 1
1.00 ± 0,05
261 ± 17
U-235:
blanket
hohlraum
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Driscoll, M.J. (ed.). MIT LMFBR blanket physics project progress report No. 7, July 1, 1975--September 30, 1976, report, September 30, 1976; Cambridge, Massachusetts. (https://digital.library.unt.edu/ark:/67531/metadc1065330/m1/30/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.