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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
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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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.
Enrico Lorenzini, Pier Giacomo Sola, Marco Spiga
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 180-184
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33314
Articles are hosted by Taylor and Francis Online.
A simple model is applied for the analysis of radiative heat transfer in a pressurized water reactor fuel assembly during steady state and under a loss-of-coolant accident. The method includes a matrix calculation of view factors, performed dividing the bundle into unit cells composed by portions of fuel rods and by a coolant subchannel. The cells are correlated considering imaginary faces among them, and the pertinent equations are simultaneously solved for the whole assembly. Some results are related for various values of the heat flux in different operational and accidental conditions.
