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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
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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Latest News
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.
D. J. Kowalski, V. J. Esposito
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 536-539
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32363
Articles are hosted by Taylor and Francis Online.
The classical manner of analyzing the loss-of-coolant accident hydraulic loads imposed on a Westinghouse-type steam generator was to assume a primary side outlet break and to assume that the confining structure was rigid. By considering the vertical divider plate to be flexible, it can be shown that the applied hydraulic forces on the divider plate, tubesheet, and tubes are significantly reduced. The assumption of a flexible divider plate requires the interaction of the fluid and structure simultaneously. The MULTIFLEX computer program and system model have the capability of considering this mutual interaction. Results have been obtained showing the reasons why and how the hydraulic loads on the steam generator internals are attenuated.