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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.
R. C. Noyes, P. K. Doherty, S. A. Caspersson, N. Hanus, D. W. Stuteville
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 460-471
Technical Paper | Fuel | doi.org/10.13182/NT75-A24446
Articles are hosted by Taylor and Francis Online.
A study to determine the optimum pin diameter for carbide fuel in a liquid-metal fast breeder reactor was made. Several subsidiary parameters, including coolant velocity, burnup, and properties of the clad and subassembly duct material, were studied for their effect on the optimum pin diameter. The materials used in the analysis were Type 316 stainless steel and a high strength, low swelling material capable of operation to a damage fluence of 3.6 × 1023 n/cm2. Using doubling time and fuel cycle cost as the basis for judgment, an optimum pin outer diameter (o.d.) range of 0.37 to 0.40 in. was found for both the near-term and advanced structural materials. Because of practical limits of the Fast Test Reactor testing, an o.d. of 0.37 in. is recommended. The optimum pin diameter was found to be independent of fuel burnup. From a doubling time point of view, no incentive was found for development of carbide fuel with a burnup greater than 80 to 90 MWd/kg.
