中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
New designs of target and cooling scheme for water cooled divertor in DEMO

文献类型:期刊论文

作者Qian, X. Y.1,2; Peng, X. B.3; Song, Y. T.3; Mao, X.3; Liu, P.3; Song, W.3; Huang, J. J.1; Lu, P.3,4; Wang, L.3; Meng, L. Y.3,5
刊名NUCLEAR FUSION
出版日期2021-03-01
卷号61
ISSN号0029-5515
关键词DEMO divertor water cooled target cooling circuit structural design thermal-hydraulics
DOI10.1088/1741-4326/abd148
通讯作者Peng, X. B.(pengxb@ipp.ac.cn) ; Song, Y. T.(songyt@ipp.ac.cn)
英文摘要Developing a robust and reliable divertor with an adequate heat removal capability is one of the most crucial issues for the realization of DEMO. Although lots of designs and technologies have been accumulated for the water cooled divertor and a full tungsten water cooled divertor for ITER has been successfully developed, there is still a gap to catch up the requirements of DEMO mainly because of the neutron irradiation. For the purpose of putting forward a feasible proposal of the divertor for DEMO concept in a short to medium term, new designs for the target and cooling circuit have been explored in this article. According to the distribution characteristics of heat load and neutron irradiation damage on the divertor and the unique properties of materials, CuCrZr and RAFM are chosen as the heat sink material for the plasma facing unit (PFU) at strike zone and other zone respectively, which is named 'dual PFUs'. A single coolant circuit is applied to both PFUs and a new design ideology of the cooling scheme has been developed. To assess the performance of the designs, corresponding thermal and structural response for the PFUs and thermal-hydraulics analysis for the cooling circuit had been performed. The property of CuCrZr in neutron irradiation environment is the main limitation for the performance of the target. And the new design for cooling circuit can effectively reduce the pressure drop without any negative impact on the divertor by rationally allocating the coolant through outer vertical target to inner vertical target and dome.
WOS关键词RESEARCH-AND-DEVELOPMENT ; ITER ; PROGRESS ; CORROSION ; TUNGSTEN ; EROSION
资助项目Youth Innovation Promotion Association of CAS[2020441] ; National Natural Science Foundation of China[11922513] ; National Natural Science Foundation of China[11705234] ; National Key Research and Development Program of China[2017YFE0301300] ; AHNSF[1808085J07] ; Shenzhen Clean Energy Research Institute
WOS研究方向Physics
语种英语
出版者IOP PUBLISHING LTD
WOS记录号WOS:000612010000001
资助机构Youth Innovation Promotion Association of CAS ; National Natural Science Foundation of China ; National Key Research and Development Program of China ; AHNSF ; Shenzhen Clean Energy Research Institute
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/119707]  
专题中国科学院合肥物质科学研究院
通讯作者Peng, X. B.; Song, Y. T.
作者单位1.Shenzhen Univ, Coll Phys & Optoelect Engn, Shenzhen 518060, Peoples R China
2.Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China
3.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
4.Hefei Comprehens Natl Sci Ctr, Inst Energy, Hefei 230031, Peoples R China
5.Univ Sci & Technol China, Hefei 230026, Peoples R China
推荐引用方式
GB/T 7714
Qian, X. Y.,Peng, X. B.,Song, Y. T.,et al. New designs of target and cooling scheme for water cooled divertor in DEMO[J]. NUCLEAR FUSION,2021,61.
APA Qian, X. Y..,Peng, X. B..,Song, Y. T..,Mao, X..,Liu, P..,...&Meng, L. Y..(2021).New designs of target and cooling scheme for water cooled divertor in DEMO.NUCLEAR FUSION,61.
MLA Qian, X. Y.,et al."New designs of target and cooling scheme for water cooled divertor in DEMO".NUCLEAR FUSION 61(2021).

入库方式: OAI收割

来源:合肥物质科学研究院

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