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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.
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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
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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.
T. Eich, A. Werner
Fusion Science and Technology | Volume 53 | Number 3 | April 2008 | Pages 761-779
Technical Paper | doi.org/10.13182/FST08-A1733
Articles are hosted by Taylor and Francis Online.
The heat load due to plasma radiation is estimated for the plasma wall components of the stellarator Wendelstein 7-X (W7-X). A fully three-dimensional Monte Carlo code is used to simulate heating of first-wall components due to photon emission from the plasma. The plasma wall components can be described in a complex way with arbitrary shapes and orientation and flexible numerical representation. The volume radiation distribution is assumed to be described by poloidal symmetric and radially varying one-dimensional profiles aligned to the magnetic flux surfaces. A further example is given by a nonpoloidal symmetric radiation distribution following the five X point regions of the island divertor magnetic structure. Several realistic and artificial radiation profiles are chosen to investigate the local heat loads on an idealized plasma wall. The first detailed technical application of the code is the estimation of the local heat load on the Thomson scattering windows and on the inner surface of several vacuum ports of one half-module of the W7-X plasma vessel.