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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
X. R. Wang, S. Malang, M. S. Tillack, ARIES Team
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 218-222
Divertor & High Heat Flux Components | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12355
Articles are hosted by Taylor and Francis Online.
This paper considers a combination of ARIES modular finger concept and a design with helium channels in a thick plate. Multiple-jet cooling at a back side of a plasma facing surface is employed in this concept. The plasma facing surface is subdivided into a large number of small hexagonal modules, similar to the EU finger concept. Such a modularization reduces thermal stresses and allows therefore maximum surface heat flux of 10 MW/m2 at least. A solution has been found allowing brazing the fingers made of a W-alloy directly into the W-plate, avoiding in this way the connection of dissimilar materials with largely different thermal expansion coefficients. For an increase in reliability, double walled thimbles are used in the most critical region, providing an additional barrier against leaks of the high pressure helium. Thermal-mechanical calculations confirmed the expected high performance of the concept with the maximum allowable heat flux > 10 MW/m2 with all the components staying in the elastic regime. Extensive analyses of non-linear materials responses, such as plastic deformation (yield) are performed to allow the materials to be pushed beyond 3Sm in order to determine the maximum allowable heat flux can be.