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 |
DOI | 10.1088/1741-4326/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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