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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
H. Y. Khater, L. J. Wittenberg
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1584-1588
Fusion Power Plants and Economics | doi.org/10.13182/FST96-A11963177
Articles are hosted by Taylor and Francis Online.
LIBRA-SP is a 1000 MWe light ion beam power reactor design study. The reactor structure is made of a low activation ferritic steel and uses LiPb as a breeder. The total activities in the blanket and reflector at shutdown are 721 MCi and 924 MCi, respectively. Hands-on maintenance is impossible anywhere inside the reactor chamber. The biological dose rates near the diode are too high at all times following shutdown allowing only for remote maintenance. The blanket and reflector could qualify for disposal as Class C low level waste. The dose to the maximally exposed individual in the vicinity of the reactor site due to the routine release of tritium is about 2.39 mrem/yr. Ten hours after a loss of coolant accident, the reflector produces a whole body (WB) early dose at the site boundary of 253 mrem. The blanket would produce a WB early dose of 8.91 rem. The potential off-site dose produced by the mobilization of LiPb during an accident is 142 mrem. A 100% release of the vulnerable tritium inventory present in the containment at any moment results in a WB early dose of 459 mrem. Release of the vulnerable tritium inventories present in the target factory and fuel reprocessing facility during an accident would result in WB early doses of 1.3 and 0.95 rem, respectively.