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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
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.
H. Zhang, A. Ying, M. Abdou
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 651-656
Test Blanket, Fuel Cycle, and Breeding | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST12-579
Articles are hosted by Taylor and Francis Online.
A SiC-based flow channel insert (FCI) is used as an electrical and thermal insulator in the Dual Coolant Lead Lithium (DCLL) blanket. To reduce the stress of the FCI structural material, the pressure equalization slot (PES) is implemented in the FCI wall. However, the PES affects the tritium transfer behavior and loss rate. Therefore it is important to examine the tritium loss rate and ensure it remains below an allowable limit. In the present study, we analyze tritium transport and quantify the tritium loss rate in a front duct of the DCLL-type outboard blanket where PbLi moves poloidally. Three types of poloidal ducts have been considered: one without the PES, one with the PES in the wall parallel to the magnetic field and one with the PES in the wall perpendicular to the magnetic field. Tritium concentration fields are obtained by solving a fully 3-D problem with appropriate boundary conditions at various interfaces. Results show a high tritium concentration at the location of reversed flow when a PES was located in the wall parallel to the field. Furthermore, when any PES was introduced, the PES changed the velocity profiles and thus changed the tritium concentrations in the core and gaps, which increases the tritium losses from 1.244% to 1.413% under the calculation conditions.