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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
Herbert Reutler, Günter H. Lohnert
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 22-30
Technical Paper | Fission Reactor | doi.org/10.13182/NT83-A33228
Articles are hosted by Taylor and Francis Online.
Nearly all problems encountered in large High-temperature reactor power plants with respect to design and safety are related to the mere physical size of a larger reactor core. Our analyses show that it is feasible to subdivide a larger reactor core into modular units, analogous to the common practice of using several smaller units instead of one large unit. In connecting several modular reactor units in series,a larger power output can be obtained by merely using simple technical designs,in addition to utilizing the favorable safety characteristics of small pebble-bed cores.It can be shown that for these cores such classical safety devices as shutdown systems and decay heat removal systems lose their dominance in respect to risk evaluations.