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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
S. Isomura, K. Suzuki, M. Shibuya
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 518-523
Tritium Processing | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25185
Articles are hosted by Taylor and Francis Online.
In order to recover tritium from light water, research and development was carried out concerning a tritium separation process based on the principle of hydrogen-water isotopic exchange reaction. The performance and durability of unit operations for the process were studied. A pilot plant having a capacity of 1 m3/year (3.6 L/day) was designed and fabricated based on the results of the tests and studies. Using this plant, tritiated water could be concentrated to the order of a magnitude of 104. Furthermore, the effect of the various operating conditions on the tritium concentration factor was calculated by applying a data analysis program for the pilot plant. This study offered the prospect of a practical application of the process by the hydrogen vapor isotopic exchange reaction to recovery of tritium from light water.
