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Division Spotlight
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
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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Latest News
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.
John A. Palmer, C. J. Bridgman, D. M. Verrelli
Nuclear Technology | Volume 2 | Number 2 | April 1966 | Pages 81-88
Technical Paper | doi.org/10.13182/NT66-A27484
Articles are hosted by Taylor and Francis Online.
A method is described that predicts the kinetic response of a circulating-water-cooled and -moderated reactor to large changes in reactivity. This response is displayed in the form of time histories of power, peak fuel plate temperature, energy, reactivity, and period. The validity of the method is verified by the agreement of calculated and experimental data when it is applied directly to the SPERT-IV reactor. The general applicability and usefulness of the method are illustrated by the analysis of the Air Force Nuclear Engineering Test Reactor. A comparison with SPERT-IV, a parametric study, and an accident evaluation are shown as sample results.
