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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
D.J. Senor, D.J. Trimble, G.E. Youngblood, G.A. Newsome, J.L. Brimhall, J.J. Woods
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 956-968
Fusion Materials | doi.org/10.13182/FST96-A11963061
Articles are hosted by Taylor and Francis Online.
A variety of SiC-Based fibers were characterized by measuring their length, density, and tensile strength in the unirradiated, thermal annealed, and irradiated conditions. The irradiation was conducted in the EBR-II to a dose of 43 dpa-SiC (185 EFPD) at a nominal irradiation temperature of 1000°C. The annealed specimens were held at 1010°C for 165 days to approximately duplicate the thermal exposure of the irradiated specimens. In general, the results of this study indicate the fibers that perform best in an irradiation environment are those that approach stoichiometric and crystalline SiC. Hi-Nicalon exhibited negligible densification, accompanied by an increase in tensile strength after irradiation. Nicalon CG possessed a higher tensile strength than Hi-Nicalon in the unirradiated condition, but was significantly weakened in the annealed and irradiated conditions. In addition, Nicalon CG exhibited unacceptable irradiation-induced shrinkage. While the irradiation stability of Hi-Nicalon was promising, other fibers with compositions closer to stoichiometric SiC may perform even better. This potential was suggested by the MER99 fiber, which displayed excellent dimensional stability. The principal drawback for the fully crystalline and stoichiometric fibers such as MER99 and Crystalline SiC is their low strength and flexibility caused by high flaw concentrations.