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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.
Carol A. Sege, Saul Strauch, Ronald P. Omberg, Irving Spiewak
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 144-149
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Reactor | doi.org/10.13182/NT79-A32144
Articles are hosted by Taylor and Francis Online.
We performed a scenario evaluation that delineates the potential role of denatured uranium/ thorium-fueled reactors, including breeders, in symbiotic systems. In this study, reactors fueled with plutonium were built in secure centers, while reactors at dispersed sites were fueled with natural, lowenriched, or denatured uranium (12% 233U or 20% 235U in 238 U) The installed nuclear capacity is assumed to be 350 MW(electric) in the year 2000, with a net increase of 15 GW(electric)/yr permitted through the year 2050. The U.S. Department of Energy Division of Uranium Resources and Enrichment projected the two bounding cases of uranium recoverable at a marginal cost of $160/lb U3O8 or less used in this study. The marginal cost of $160/lb U3O8 occurs at 3 million short tons (ST) for the high-cost supply and at 6 million ST for the intermediate-cost supply. For the assumed high-cost U3O8 supply (3 million ST U3O8), thermal recycle with denatured light water reactors (LWRs) will achieve the same incremental increase in maximum achievable nuclear capacity as U/Pu recycle in LWRs [∼200 GW(electric) more than once-through cycles]. Introduction of a breeder is required for the system to achieve the projected nuclear demand [1100 GW(electric) in 2049]. For all denatured systems, including those with breeders, a significantly larger fraction of the installed capacity can be located at dispersed sites, compared with U/Pu systems. For the assumed intermediate-cost U3O8 supply (6 million ST U3O8), thermal recycle with advanced converters will permit projected nuclear demand to be met for both the Pu/U and denatured uranium-thorium cycles.