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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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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.
S. J. Piet, M. S. Kazimi, L. M. Lidsky
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 533-538
Environment and Safety | doi.org/10.13182/FST83-A22918
Articles are hosted by Taylor and Francis Online.
The FUSECRAC code, a modification of the CRAC code, was developed to estimate public health effects from released fusion radioactivity both for safety studies and for comparison of the hazards associated with candidate structural materials. This paper summarizes the key motivations, problems, and results of the FUSECRAC comparison. The evolving CRAC code is a product of the Reactor Safety Study and represents the state of the art in fission accident consequence assessments. It was found that potential public health effects from accidental releases of 316 SS are two orders of magnitude higher than from V-15Cr-5Ti or TZM per unit volume of activated first wall released. The probabilities for releases among these materials were not addressed here.
