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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
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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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
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.