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Reaction rates in a uranium pile surrounding a 14-MeV neutron source: calculations of the Weale experiment

Journal Article · · Nucl. Sci. Eng.; (United States)
OSTI ID:7247701
To validate the neutronics analysis of hybrid fusion-fission reactor blankets, calculations were made of an experiment by Weale et al., where a 14-MeV neutron source was surrounded by a natural uranium metal pile. The evaluated nuclear data libraries, ENDL and ENDF/B, were used. The calculated parameters were found to be in closer agreement for present versions of these libraries than for preceding versions; however, there were still 15 percent differences in the /sup 235/U(n,f) and /sup 238/U(n,f) reaction rates. The present version of ENDL gives the results that are the closest to the experimental values for these reactions. For the /sup 238/U(n,..gamma..) reaction, the calculations with the ENDF/B libraries are closer to the measured values. Both the ENDL and ENDF/B evaluations, however, fail to calculate correctly the neutron leakage or derived values for the /sup 238/U(n,2n) and /sup 238/U(n,3n) reaction rates. The spatial variations of the /sup 235/U(n,f), /sup 238/U(n,..gamma..), /sup 238/U(n,f), and /sup 239/Pu(n,f) reaction rates show that the penetration of high-energy neutrons in the pile is better described by the calculation with ENDL, which gives a greater penetration. The effects of resonance self-shielding were investigated and found to require a much smaller correction than the differences between calculations with different data libraries.
Research Organization:
Univ. of California, Livermore
OSTI ID:
7247701
Journal Information:
Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 61:1; ISSN NSENA
Country of Publication:
United States
Language:
English