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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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.
Taihyeop Lho, Yong-Sup Choi, HyonJae Park
Fusion Science and Technology | Volume 63 | Number 1 | May 2013 | Pages 106-110
doi.org/10.13182/FST13-A16882
Articles are hosted by Taylor and Francis Online.
Hydrogen solubility of FLiNaK (LiF 46.5 mol% + NaF 11.5% + KF 42 mol%) were investigated with hydrogen plasma interaction. To use molten salt as liquid wall for fusion device, tritium retention property of the molten salt should be studied. Although there have been some reports on hydrogen solubility of FLiNaK, retention property of FLiNaK with hydrogen plasma interaction has not been reported yet. Hydrogen outgassing of molten FLiNaK was measured with RGA after interaction of hydrogen plasma. Hydrogen partial pressure of the RGA was calibrated with an H2 mass flow controller of 5sccm. Hydrogen plasma was generated with 500W ECR source and the molten FLiNaK was contained with heated crucible of diameter of 46mm and depth of 40mm. By measuring hydrogen ion density near the surface of FLiNaK, we evaluated dose of hydrogen to the FLiNaK and calculated retention percentage with measured outgassing amount of hydrogen. Compared to Henry's law, plasma-interacted-FLiNaK showed significantly large amount of hydrogen retention such as 10000 times.