1975•OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)Requires access
Monte Carlo analysis of thermal spectrum averaged measurements of eta of /sup 233/U and /sup 235/U (LWBR Development Program)
M. Goldsmith, John J. Ullo
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Abstract
Since the number of fission neutrons produced per absorption, eta, is crucial to the performance of light water breeder reactors, a reanalysis of measurements of this parameter was undertaken. In the Mn bath experiments, a beam of thermalized neutrons, defined by Cd difference, was allowed to impinge on various fissionable targets. The ratio of the resulting bath activation to that produced when the target is removed is denoted by eta*. Monte Carlo calculations, employing ENDF-4 cross sections, yielded eta*/eta/sub 2200/ ratios for /sup 233/U and /sup 235/U. The Monte Carlo analysis was confirmed by calculating measured quantities used by the experimentalits in their reduction of eta* to eta/sub 2200/. 3 figures, 5 tables. (NSA 32: 18674)