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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Hilbert Christensen
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 165-174
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT98-A2916
Articles are hosted by Taylor and Francis Online.
Calculations of UO2-fuel corrosion and gas production from radiolysis of water have been carried out. The calculations simulated conditions of spent-fuel leaching experiments carried out within a European Union project. In some of these experiments, carried out by Forschungszentrum Karlsruhe, a fuel pellet was exposed in deionized water for 200 days, and fuel alteration and gas production rates were measured. A radiolysis model, developed previously, was used to calculate the oxidation of UO2 caused by water radiolysis products. The calculated fuel alteration rate was 2.2 × 10-8 mol UO2(g U)-1day-1, about three times higher than the experimental rate, 6.3 × 10-9 mol UO2(g U)-1day-1.The fair agreement between calculated and experimental corrosion rates shows that the model may be used for prediction of corrosion behavior of spent fuel in the repository. The calculated gas generation rates were 2 × 10-8 and 1 × 10-8 mol(g U)-1day-1 for hydrogen and oxygen, respectively, about six times lower than the experimental values.