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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.
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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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.
C. S. Luby
Nuclear Technology | Volume 3 | Number 12 | December 1967 | Pages 728-736
Technical Paper and Note | doi.org/10.13182/NT67-A27789
Articles are hosted by Taylor and Francis Online.
Irradiation tests to evaluate coated-particle fuels under high temperature, high burnup, and high fast-neutron dose conditions were designed so that the irradiation parameters could be measured and controlled closely. The coated particles used consisted of two-layer (BISO) and threelayer (Triplex) pyrolytic carbon coatings on fuel particles of the carbide or oxide of thorium and/or uranium. In the irradiation experiments, the coated particles were tested at temperatures up to 1900°C, fuel burnups up to 20% fissions per initial heavy metal atom (FIMA), burnup rates up to 20% FIMA per month, and fast-neutron doses up to 2.7 x 1021 n/cm2 (E > 0.18 MeV). Correlations between the irradiation temperatures and other important radiation and materials parameters are presented showing the effects of these parameters on the stability of the BISO and Triplex coated fuel particles. These studies show that the temperature of irradiation is one of the most important parameters influencing coated-particle fuel stability under irradiation. This is believed to be due to the dependence of the fission gas pressure on irradiation temperature and the deleterious effect that an increase in this pressure has on the coating. Thicker coatings are required for high-temperature operation. The studies also demonstrated that coated particles with two- and three-layer pyrolytic-carbon coatings and adequate fuel contents have good stability well beyond the temperatures anticipated in an HTGR.