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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.
Nobuyuki M. Masaki, Takakuni Hirabayashi, Masakatsu Saeki
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1337-1342
Tritium Technology | doi.org/10.13182/FST89-A39874
Articles are hosted by Taylor and Francis Online.
Behavior of sorption of tritium on surfaces of stainless steel, aluminum and borosilicate glass has been studied using gaseous tritium with high specific activity and the newly obtained knowledge has been applied to chemical and thermal decontamination of tritium-sorbing materials. The behavior depends on a character of surface of each material. The total amount of sorbed-tritium is evaluated as a function of time of exposure to gaseous tritium. The depth-profile of sorbed-tritium is obtained by chemical etching method. From these results, practical samples of stainless steel were decontaminated. The vacuum-bakeout for 21, hours at 773 K and dissolution by dilute (5%) HCl for 2 hours enable us to obtain the decontamination factor of 200.
