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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
K. Isobe, H. Imaizumi, T. Hayashi, S. Konishi, M. Nishi
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 988-992
Purification and Chemical Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22732
Articles are hosted by Taylor and Francis Online.
A Fuel cleanup system (FCU) that recovers fusion fuel (tritium and deuterium) from plasma exhaust mixture gas has been developed and demonstrated at the Tritium Process Laboratory (TPL) of Japan Atomic Energy Research Institute (JAERI). We have proposed a new closed loop FCU system built up by connecting the tubular reservoir tank, the electrolytic reactor and a palladium diffuser. In the electrolytic reactor, methane and water are converted at the same time by electrochemical reaction in gas phase oxidation and reduction to liberate hydrogen isotope as a form of elemental hydrogen. The long tubular reservoir tank that is designed to store and transfer the products gas in plug flow prevents from mixing with reactants for the successive repeat processing. With this tank, high overall decontamination factor of system can be obtained by small number of circulation. As the demonstration test, mixture gas consist of hydrogen isotopes, methane and He were processed in the closed loop FCU. The electrolytic reactor and the tubular reservoir tank worked as designed successfully, and the entire loop exhibited efficient impurity processing performance. The concentration of methane was observed to decrease sharply in every processing by the electrolytic reactor from 2.3% to less than 12ppm finally.