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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
Sang-Yong Lee, Chang-Hwan Ban
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 335-347
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3571
Articles are hosted by Taylor and Francis Online.
Several researchers have endeavored to develop methodologies to extrapolate the uncertainties gathered from reduced-size facilities to the full-size nuclear power plant. They are all based on the general guideline of the code scaling, applicability, and uncertainty (CSAU) method. Although there is an extensive compilation of experimental and theoretical databases and a detailed guide about the best-estimate calculation of loss-of-coolant accidents, these applications are dissimilar to each other. The absence of a procedure to implement the requirement of direct data comparison with integral- and separate-effects tests in determining the code uncertainty is the main cause of the differences. To overcome this problem, a code-accuracy-based uncertainty estimation (CABUE) technique has been developed, in which the code accuracy becomes the measure of the selection of code parameters and the determination of the ranges of them. An application of this technique to a Westinghouse three-loop nuclear power plant has been successfully performed.