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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 Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
Geological work begins on Poland’s first nuclear plant
Project management firm Bechtel started site geological surveys for Poland’s first nuclear power plant project, the company announced on Wednesday.
Bechtel will conduct in-depth geological surveys at the Lubiatowo-Kopalino site in the Pomeranian municipality of Choczewo, in northern Poland. This is a key milestone for the country’s entry into nuclear power production, as the surveys will inform the suitability of the planned site.
Hangbok Choi
Nuclear Technology | Volume 204 | Number 3 | December 2018 | Pages 283-298
Technical Paper | doi.org/10.1080/00295450.2018.1484646
Articles are hosted by Taylor and Francis Online.
The performance of uranium-plutonium mixed carbide fuel was analyzed based on experimental data produced from the Japan Research Reactor No. 2, the Japan Materials Testing Reactor, and the Fast Flux Test Facility irradiation tests during 1983 to 1992. The analysis includes a review of earlier fuel irradiation test results, material property data, and physics models, and a simulation by a finite element method fuel performance code FEMAXI-6GA to predict the historic results. The simulation results were compared to the measured fission gas release, fuel swelling, and dimensional change of the cladding. The simulation results are reasonably consistent with the measurement. However, a few differences between the simulations and measurements were encountered, which are attributed to the lack of detailed experimental conditions, characteristics of fuel materials, material property data, and physics models. Based on sensitivity analyses of the results to experimental conditions and material property data, it is recommended to develop an experimental plan for the systematic measurements of thermal conductivity, including the effect of porosity, impurities, and stoichiometry, fission gas diffusion, and irradiation-induced swelling and densification, supplemented by advanced modeling and simulation techniques to support advanced fuel development in a cost-effective way.