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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
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.