A SURVEY AND EVALUATION OF U$sup 233$ FISSION YIELD DATA Page: 9 of 39
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A SURVEY AND EVALUATION OF U233 FISSION YIELD DATA
R. L. Ferguson G. D. O'Kelley-
A survey of the pertinent literature was made to
- ascertain the status of data on U233 fission-product yields.
The various experimental determinations were evaluated, and
the most recent mass-spectrometric results were used as a
basis for deriving a set of preferred yields. These yields
were compared with values reported in two other recent com-
pilations, and for yields > l%, the three sets agreed with
each other to an average precision of < 5%. It was con-
cluded that recent measurements have somewhat improved the
reliability of U233 fission yield data, but some recommen-
dations for additional experimental work were made. This
report was prepared from an internal memorandum (CF-62-3-71)
previously given limited distribution.
Because of the importance of the thorium-uranium cycle in the
breeder reactor concept, it is desirable to determine accurately the prop-
erties of U233 which affect its use as a reactor fuel. In particular,
estimation of the effects of fission-product poisoning, evaluation of
problems connected with the chemical reprocessing of irradiated fuel,
and calculation of shielding requirements demand accurate values for the
yields of the various fission products.
Compilations of fission-product yields from thermal-neutron
fission of U233 have been made by several authors (1-6). Recently,
Katcoff (7) reviewed all data available in late 1960 and revised the
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Ferguson, R.L. & O'Kelley, G.D. A SURVEY AND EVALUATION OF U$sup 233$ FISSION YIELD DATA, report, July 13, 1962; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc1056944/m1/9/: accessed April 23, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.