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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.
Sungjin Kwon, Kihak Im, Jong Sung Park
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 737-746
Technical Note | doi.org/10.1080/15361055.2017.1350479
Articles are hosted by Taylor and Francis Online.
A pressurized water cooling divertor target applying the tungsten monoblock type has been primarily considered in the Korean fusion demonstration reactor (K-DEMO). The target peak heat flux locally concentrated around the striking point was set to 10 MW/m2 in K-DEMO divertor system. In a previous study [Im et al., IEEE Trans. Plasma Sci., Vol. 44, p. 2493 (2016)] the thermomechanical analyses for a high heat flux unit of K-DEMO divertor target applying reduced activation ferritic martensitic (RAFM) steel as heat sink material were carried out to verify the thermal and mechanical stabilities. The results of the thermomechanical analyses showed that the stabilities of the divertor target design applying the derived design parameters were close to the allowable limits, since the thickness of RAFM coolant tube was too thin due to the low thermal conductivity of RAFM steel. The aim of this study is to propose the structurally modified divertor concept switching the flowing path of coolant from poloidal direction to toroidal direction. By changing the flow direction, the design and material could be independently selected by the local intensity of the heat flux. The CuCrZr and RAFM steel were employed to the peak heat flux region and the non-peak heat flux region as a heat sink material, respectively. The effects of the modified concept were assessed by performing thermohydraulic analyses. The result showed that the modified concept more efficiently dissipated the heat flux compared to the conventional concept.