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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
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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.
A.G. Heics, W.T. Shmayda
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 1030-1034
Material; Storage and Processing | doi.org/10.13182/FST92-A29887
Articles are hosted by Taylor and Francis Online.
Zirconium cobalt (ZrCo) is being evaluated as an alternative to uranium for tritium storage. The pumping speed and pressure-composition-temperature isotherm profiles for the ZrCo hydrogen and tritium systems were measured to determine isotopic differences and the effect of He-3 induced aging on ZrCo performance. Hydrogen is pumped by ZrCo at a slightly faster rate than tritium under identical test conditions. The ZrCo/H2 system has a slightly lower equilibrium pressure compared to the ZrCo/T2 system at corresponding compositions. Aging ZrCo with tritium for 57 days appears to have no noticeable effect on the tritium pumping speed relative to virgin ZrCo.
