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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Mahmoud Z. Youssef, Russell Feder, Kelly Thompson, Ian Davis, Gregory Failla
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 718-725
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8993
Articles are hosted by Taylor and Francis Online.
The new feature of the ATTILA 3-D code to calculate dose rates in a given geometry was benchmarked using the dose rate experiments performed at the FNG 14.1 MeV source facility located at ENEA, Frascati, Italy. Two experimental campaigns were performed. Post irradiation measurements were undertaken using Geiger-Müller, TLD, and tissue-equivalent scintillators. Other measurements were also performed during irradiation. ATTILA results were compared to the experimental data and to the results of the MCNP Monte Carlo code published earlier. The calculations were performed through three consecutive steps using the same ATTILA code along with its built-in activation library, FORNAX. The ANSI/ANS6.1.1-77 and ICRP74 Ka flux-to--dose conversion factors were used. Good agreement with the experimental data and the MCNP results was obtained for times >7 d after irradiation in the 1st campaign but large underestimation was found at shorter time steps. Both dose rates and integrated gamma fluxes are largely underestimated (∼20-40%) in the 2nd campaign.
