ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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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Apr 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
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.
C. M. Walter, P. G. Shewmon, J. P. Bacca
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 38-44
Technical Paper | Fuel | doi.org/10.13182/NT71-A30900
Articles are hosted by Taylor and Francis Online.
A metallic fuel-element modeling code (BEMOD) has been developed to describe the irradiation behavior of EBR-II driver fuels. BEMOD has been applied to both the present Mark LA and the advanced Mark II driver fuels. Good agreement on cladding diameter changes as a function of burnup is obtained between calculations and measurements on irradiated fuel elements. At a reactor power of 50 MW(th), the code calculations indicate that the Mark IA element is capable of about 3.5 at.% before a cladding ΔD/D of 2% is expected, while the Mark II design should be capable of about twice that burnup before a similar cladding ΔD/D is attained. The increase in reactor power to 62.5 MW(th) appears to have no appreciable effect on the above values.
