ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Technology
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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.
Mohamed S. El-Genk, Rajinder M. Kumar, Douglas W. Croucher
Nuclear Technology | Volume 60 | Number 2 | February 1983 | Pages 291-303
Technical Paper | Radiation Effects and Their Relationship to Geological Repository / Nuclear Fuel | doi.org/10.13182/NT83-A33085
Articles are hosted by Taylor and Francis Online.
An analytical model was developed to study the prompt escape of gaseous and volatile fission products present in the fuel-cladding gap of a light water reactor fuel rod following a cladding breach. Key questions include how fast fission gas is released and what mass fraction of the gap gas remains in the failed rod. Analysis shows that only a small mass fraction (∼0.17) of the total gas inventory initially present in the fuel-cladding gap escapes promptly following cladding rupture, regardless of the size of the rupture, when the rod is surrounded by liquid coolant at high pressure (∼6 to 15 MPa). However, during a loss-of-coolant type of accident, where the fuel rod is surrounded mainly by low pressure steam (∼0.1 MPa), a large mass fraction (∼0.95) of the gap gas is found to escape the rod shortly after cladding rupture due to the greater ratio of the initial rod pressure to the coolant pressure.