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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
M. T. Morgan, A. P. Malinauskas
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 457-464
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31905
Articles are hosted by Taylor and Francis Online.
Theoretical and experimental aspects of cesium release from Biso-coated high-temperature gas-cooled reactor fuel particles are reviewed. Three types of transport are considered: diffusion through the pyrolytic carbon (PyC) coatings under conditions of a constant source potential, transport due to a continuously depleting source, and diffusion from a depleting source following constant source potential transport. Analysis of all of the release data obtained in this laboratory yields the following relations for the diffusion coefficient DCs characteristic of cesium transport through PyC coatings:For coatings deposited from propylene or propane at ∼1250°C (1523 K):and far coatings deposited from methane at ∼2000°C (2273 K):where T is the absolute temperature.
