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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
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.
