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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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Nuclear Science and Engineering
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Nuclear Technology
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.
K. Miya , T. Rizawa , K. Someya, A. Minato, T. Tone
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 233-238
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40050
Articles are hosted by Taylor and Francis Online.
Ferritic stainless steel(HT-9) is a prospective candidate for a first wall material of a fusion reactor. It experiences magnetic stress due to magnetization in magnetic field. A ferromagnetic cantilever of mild steel was provided to carry out a test on magnetomechanical behavior and to compare with theoretical prediction. The theoretical prediction was made for an infinitely wide beam plate and magnetic stiffness was taken into account. Field distribution of the finite specimen is very different from one of an infinite specimen. It is made clear that deformation is proportional to the squared field for smaller applied field while linear with the field for larger one.
