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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
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.