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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.
Vincent P. Manno
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 281-288
Technical Paper | Fuel | doi.org/10.13182/NT80-A32474
Articles are hosted by Taylor and Francis Online.
The current regulatory requirement that peak cladding temperatures (PCTs) never exceed 1204°C (2200°F) at any time during a loss-of-coolant accident (LOCA) is frequently the most limiting factor in setting core peaking factor limits. Of the many plant specific characteristics involved in predicting a fuel rod’s thermal response to a LOCA, the containment or “back” pressure plays a significant role, especially in pressure suppression pressurized water reactor (PWR) containments. The back pressure effect is studied by comparing the predicted PCT histories at back pressure levels of 138, 155, 172, and 207 kN/m2 (20, 22.5, 25.0, and 30 psia). A typical four-loop PWR with 15 × 15 fuel assemblies is analyzed. The analysis is performed using an in-house LOCA code named HEATUP-R/AEP, which calculates fuel thermal response during core reflood. In addition to temperature, the reflood rates, exit qualities, and cladding oxidation rates are studied. Results show significant increases in PCTs at lower pressure due to enhanced steam binding in the coolant loops.