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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.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
David G. Martin
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 304-311
Technical Paper | Fuel | doi.org/10.13182/NT79-A32184
Articles are hosted by Taylor and Francis Online.
The fact that not all coated fuel particles in a batch fail after the same irradiation history is due to manufacturing variations in values of individual particle parameters. Two methods of calculating the failure fraction as a function of burnup in terms of these statistical variations are discussed: (a) a random sampling of particles combined with a simple stress model, and (b) the convolution of the individual variations combined with an advanced stress model. These methods were applied to particles manufactured by two laboratories in support of the U.K. low-enriched fuel cycle high-temperature reactor design. Experimental values of variations in the following parameters were included: kernel diameter and porosity, thickness of buffer, seal, silicon carbide and inner and outer pyrocarbon layers (all assumed to be normally distributed), and the silicon carbide fracture stress (assumed to obey a Weibull distribution). It was concluded that the convolution approach was the more satisfactory method. The results enable one to identify which of the various parameters considered are the most worthwhile for manufacturers to put development effort into so as to reduce their variability. For the particles considered here, these are primarily silicon carbide fracture stress, followed by kernel porosity.