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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
V. K. Dhir, W. E. Kastenberg, D. W. Varela
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 447-452
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32352
Articles are hosted by Taylor and Francis Online.
Generally, the blockages that may form in the reactor core when molten fuel is ejected into the coolant channels during a transient overpower accident can be divided into two categories. The first type of blockage forms when semi-molten fuel particles hit a wire wrap and freeze on the wire wrap, whereas the second type of blockage forms when solid or semi-solid particles get stuck in the coolant channels. The thermal-hydraulic analysis of these proposed blockages indicates that under certain specific conditions, the blockages can lead to melting of the wire wrap and cladding and also to in-channel voiding. The second type of blockage, if formed as a plug, may remelt before being quenched by subcooled or saturated sodium.