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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.
N. Scott Cannon, Gary L. Wire
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 50-62
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33302
Articles are hosted by Taylor and Francis Online.
A new simulated transient test capability is introduced that allows controlled biaxial strain-rate (CBSR) tests on fast reactor cladding to be performed at constant test temperatures ranging from 425 to 650°C and constant diametral strain rates between 10−5 and 10−3/s. The CBSR test results from both irradiated and unirradiated 20% cold-worked Type 316 stainless steel are reported. A mathematical expression describing CBSR strengths was developed from tensile data. The CBSR ductility was generally found to be reduced from corresponding tensile results by roughly an order of magnitude. For unirradiated cladding, diametral failure strain was relatively strain-rate independent below 650°C, and at 650°C, failure strains increased with decreasing strain rate. Following fast reactor irradiation at 370 to 680°C cladding, diametral failure strains increased with increasing irradiation temperature. The sensitive diameter measurement apparatus allowed strain determinations showing the importance of anelastic effects at low plastic strains.
