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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
A. Kenigsberg, D. Hasan, E. Elias
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 219-224
Technical Paper | Reactor | doi.org/10.13182/NT80-A32525
Articles are hosted by Taylor and Francis Online.
A hypothetical accident is analyzed, in which an external (outof-plant) natural or man-made event causes a loss-of-coolant accident after penetrating the containment wall The computer codes CONTEMPT and RELAP4 have been used to study the containment thermal-hydraulic behavior during the accident. The radioactive materials outflow rate is calculated for a wide range of anticipated breach sizes, assuming perfect mixing in the air-steam-water mixture in the containment building. Typically, there is only a low pressure buildup in the initially breached containment. Therefore, the calculated fission product release rate is lower than the predicted rate in case the containment fractures in a later phase of the accident.