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contributor authorCheng, Jie
contributor authorWu, Yingwei
contributor authorSu, G. H.
contributor authorQiu, Suizheng
contributor authorTian, Wenxi
date accessioned2019-09-18T09:05:41Z
date available2019-09-18T09:05:41Z
date copyright7/19/2019 12:00:00 AM
date issued2019
identifier issn2332-8983
identifier otherners_005_04_041302
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4258789
description abstractChina Fusion Engineering Test Reactor (CFETR) is a test tokamak reactor being designed in China to bridge the gap between International Thermonuclear Experimental Reactor (ITER) and future fusion power plant. As one of the candidates, a water-cooled solid breeder blanket based on pressurized water and supercritical water conditions were proposed. In the concept, multiplying layers separated by three breeding layers were designed and optimized for higher tritium breeding ratio (TBR) and uniform heat distribution. This blanket adopts the Li2TiO3 lithium ceramic pebbles as the breeder, while beryllium pebbles as the neutron multiplier. In this paper, the thermal and fluid dynamic analyses of the optimized blanket on both water conditions were performed by numerical simulation, to discuss thermo-hydraulic performance of the blanket using pressurized water/supercritical water as its coolant. At first, the neutronic analysis was performed and based on the typical outboard equatorial blanket. Then, thermal and fluid dynamic analysis of the 3D model was carried out by CFX with fluid–solid coupling approach. It was found that the blanket can be effectively cooled on both water conditions, certified the feasibility of the blanket design with pressurized/supercritical water conditions. It indicated that supercritical water blanket had smaller safety margin than pressurized water blanket, but supercritical water blanket would lead to higher outlet temperature, thermal conductivity, and heat exchange efficiency also. In addition, the beryllium fraction was considered as one of the dominant factor, which leading a higher TBR in our simulations.
publisherAmerican Society of Mechanical Engineers (ASME)
titleNeutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR
typeJournal Paper
journal volume5
journal issue4
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4042364
journal fristpage41302
journal lastpage041302-7
treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 004
contenttypeFulltext


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