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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
Yoshiaki Oka, Shigehiro An, Hiroyuki Hashikura, Shun-ichi Miyasaka, Kinji Koyama
Nuclear Science and Engineering | Volume 79 | Number 3 | November 1981 | Pages 308-315
Technical Note | doi.org/10.13182/NSE81-A19407
Articles are hosted by Taylor and Francis Online.
Neutron reaction rates were measured by activation foils and thermoluminescent detectors through 180-cm-thick sodium shields and also through the layers of a 6-cm-thick iron plate and the sodium shields. A tightly coupled source shield configuration was constructed with the fast neutron reactor YAYOI as a source. Analysis of the experiments was made by using the DOT 3.5 code with 13-group neutron cross sections from the ENDF/B-IV library. Bondarenko-type self-shielding factors were included. The source condition for the analysis was determined by an iteration method from the experimental result at the reactor-shield interface and the initial estimate that was obtained from the core criticality calculation. The calculated neutron distributions in the shields agree with the experiments within ∼25% for the penetration through 180-cm-thick sodium. The shapes of the spatial distributions of the reaction rates in the shields show rather good agreement with the experiment.