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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.
C. V. Parks, P. J. Maudlin
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 38-53
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32752
Articles are hosted by Taylor and Francis Online.
A recently proposed sensitivity technique called differential sensitivity theory is applied to the neu-tronic/thermal-hydraulic fast reactor safety code MELT-IIIB. This application centers on the develop ment and solution of the appropriate adjoint and sensitivity equations, resulting in an adjoint version of the MELT code called MELTADJ. Proper inte gration of the forward MELT solution with the corresponding adjoint MELTADJ solution formally yields sensitivity information for all input parameters. Two transients in the Fast Flux Test Facility were investigated by performing input parameter sensi tivity analyses. Sensitivities obtained via MELTADJ are compared with those from MELT recalculations using perturbed input. These investigations indicate sufficiently good agreement between differential sensitivity theory and recalculation to validate the development of MELTADJ.