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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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
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.
R.-D. Penzhorn, M. Glugla
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1345-1348
Tritium Technology | doi.org/10.13182/FST86-A24917
Articles are hosted by Taylor and Francis Online.
Based on experimental results of the catalytic decomposition of ammonia and methane into the elements, a three step process is under development for D, T recycling of the effluent gas of the main fusion reactor exhaust gas purification system. The process is designed for operation at comparatively low temperatures in order to minimize tritium permeation losses. A reduction in solid radioactive waste is achieved by the employment of catalytic cracking reactions. The high purity D, T produced may be fed directly into the isotope separation system. By process optimization sufficiently high decontamination factors of the waste gas seem possible.