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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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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.
G. D. Bazinet, W. F. Brehm, M. G. Down, D. K. Matlock
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 718-723
Materials Engineering | doi.org/10.13182/FST83-A22944
Articles are hosted by Taylor and Francis Online.
The corrosion behavior of selected materials in a liquid lithium environment was studied in support of system-and component designs for the Fusion Materials Irradiation Test (FMIT) Facility. Testing conditions ranged from ∼ 3700 to ∼ 6500 hours of exposure to flowing lithium at temperatures from 230° to 270°C and static lithium at temperatures from 200° to 500°C. Principal areas of investigation included lithium corrosion/erosion effects on FMIT lithium system baseline and candidate materials. Material coupons and full-size prototypic components were evaluated to determine corrosion rates, fatigue crack growth rates, structural compatibility, and component acceptability for the lithium system. Based on the results of these studies, concerns regarding system materials and component designs were satisfactorily resolved to support a 20-year design life requirement for the FMIT lithium system.
