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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.
L. W. LANG
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 302-310
Technical Papers and Note | doi.org/10.13182/NT68-A27995
Articles are hosted by Taylor and Francis Online.
Uranium-233 is a more efficient fuel in a thermalized flux than either 235U or 239Pu. Its nuclear performance and value to thermal converter reactors would be further enhanced if the 233U were produced free of 232U and if it were used to enrich natural or depleted uranium. Although it has been generally accepted that the fissile isotope produced in the blankets of the fast breeders will be Pu, clean 233U could be produced by charging thorium rather than 238U into the fast reactor blanket. Since the breeding gain does not appear significantly altered, the ultimate decision facing the breeding reactor operator will depend on the comparative revenue from the two fissile isotopes. The value of 233U will exceed that of Pu during early periods of breeding reactor development. As the value of Pu increases, due to fast reactor demand, the worth of 233U will also increase but at a slower rate. If the price of U3O8 is $12/lb, the worth of 233U will exceed that of Plutonium up to $22/g.