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Division Spotlight
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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.
K. Petersen, H. Barthels, H. E. Drescher, C. B. Von Der Decken, N. Iniotakis, W. Schenk, R. Schulten
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 306-311
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32331
Articles are hosted by Taylor and Francis Online.
Unrestricted core heatup analysis based on recent experimental investigations of heat, gas, and fission product transport mechanism under ultimate accident conditions proves for the example of the 500-MW(thermal) plant the inherent safety potential of the pebble-bed high-temperature reactor. Under the hypothetical assumptions of depressurization of the primary circuit through a large hole within the prestressed concrete reactor vessel top region and the failure of all heat sinks, including the liner cooling system, the core structure, fuel elements, and consequently the essential fission product barriers remain undamaged. The integrated 137Cs contamination of the containment after depressurization rises only to 1 Ci after 100 h.
