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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.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
Fusion Science and Technology
A review of workforce trends in the nuclear community
The nuclear community is undergoing a moment of unprecedented interest and growth not seen in decades. The passage of the bipartisan Infrastructure Investment and Jobs Act and the Inflation Reduction Act are providing a multitude of new funding opportunities for the nuclear community, and not just the current fleet. A mix of technologies and reactor types are being evaluated and deployed, with Vogtle Units 3 and 4 coming on line later this year, the Advanced Reactor Demonstration Projects of X-energy and TerraPower, and NuScale’s work with Utah Associated Municipal Power Systems to build a first-of-a-kind small modular reactor, making this is an exciting time to join the nuclear workforce.
A. Khodak, Y. Zhai, W. Wang, R. Feder, G. Loesser, D. Johnson
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 271-277
Technical Paper | doi.org/10.1080/15361055.2017.1330638
Articles are hosted by Taylor and Francis Online.
As part of the diagnostic port plug assembly, the ITER Diagnostic Shield Module (DSM) is designed to provide mechanical support and the plasma shielding while allowing access to plasma diagnostics. Thermal and hydraulic analysis of the DSM was performed using a conjugate heat transfer approach, in which heat transfer was resolved in both solid and liquid parts, and simultaneously, fluid dynamics analysis was performed only in the liquid part. ITER Diagnostic First Wall (DFW) and cooling tubing were also included in the analysis. This allowed direct modeling of the interface between DSM and DFW, and also direct assessment of the coolant flow distribution between the parts of DSM and DFW to ensure DSM design meets the DFW cooling requirements. Design of the DSM included voids filled with Boron Carbide pellets, allowing weight reduction while keeping shielding capability of the DSM. These voids were modeled as a continuous solid with smeared material properties using analytical relation for thermal conductivity. Results of the analysis lead to design modifications improving heat transfer efficiency of the DSM. Effect of design modifications on thermal performance as well as effect of Boron Carbide will be presented.