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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.
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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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. G. Clemmer, R. F. Malecha, I. T. Dudley
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 83-92
Tritium | doi.org/10.13182/FST83-A22849
Articles are hosted by Taylor and Francis Online.
The TRIO-01 experiment is a comprehensive test of in-situ tritium recovery from a miniaturized solid breeder blanket assembly. Other solid breeder blanket performance factors such as thermal hydraulics, tritium permeation, and gas phase chemistry will be tested as well. The capsule assembly is irradiated in the A2 core position of the Oak Ridge Research Reactor (ORR). Tritium release and recovery is tested by passing a He sweep gas through the solid breeder capsule measuring and collecting the tritium in the sweep stream. The TRIO-01 experiment has extensive on-line monitoring including sweep gas analysis, temperatures, neutron flux, and tritium permeation.
