Exploring the engineering limit of heat flux of a W/RAFM divertor target for fusion reactors | |
Mao, X.1; Fursdon, M.2; Chang, X. B.3; Zhang, J. W.3; Liu, P.1; Ellwood, G.2; Qian, X. Y.3; Qin, S. J.1; Peng, X. B.1; Barrett, T. R.2 | |
刊名 | NUCLEAR FUSION
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2018-06-01 | |
卷号 | 58期号:6页码:13 |
关键词 | reactor divertor plasma facing unit heat transfer coefficient thermo-mechanical stress fatigue life Bree diagram |
ISSN号 | 0029-5515 |
DOI | 10.1088/1741-4326/aabb64 |
英文摘要 | The design and development of a fusion reactor divertor plasma facing component (PFC) is one of the many challenging issues on the road to commercial use of fusion energy. The divertor PFC is expected to exhaust steady state heat loads in the region of 10 MW m(-2) while keeping temperatures and thermo-mechanical stresses in its structure within the allowable limits. For ITER (International Thermo-Nuclear Experimental Reactor) a water cooled W/CuCrZr divertor PFC concept has been developed. However, this concept is not necessarily assured for use in future fusion reactors mainly because the neutron radiation dose would be at least an order magnitude higher, resulting in limited thermo-mechanical performance and considerably more activated waste products. In the present study, a water cooled divertor PFC using reduced activation ferritic-martensitic (RAFM) steel as the heat sink pipe has been designed with pressurised water reactor-like cooling conditions (pressure of 15.5 MPa, velocity of 10-20 m s(-1) and temperature of 300 degrees C). The PFC is made up of a number of rectangular tungsten tiles, each with an inner circular hole (so-called monoblocks), joined onto a RAFM steel pipe with copper interlayers. The thermo-mechanical performance of the PFC has been studied in detail. The heal transfer coefficient between the RAFM pipe inner surface and the water was calculated using published correlations. Geometric parameters and water velocity were optimized with finite element (FE) thermal analysis, to achieve acceptable temperatures in the structure given the target exhaust heat load of 10 MW m(-2). Under this heat load and the optimised thermal design parameters, the structure of the PFC was further assessed by mechanical analysis. We find that under these conditions the RAFM steel pipe experiences cyclic plasticity, and fails the common linear elastic ratchetting (3 Sm) rule. Nevertheless, the designed W/RAFM divertor PFIT can withstand 10 MW m(-2) heat load, albeit with a fatigue life of approximately 0.55 years based on the expected operation scenario of a prototype or test reactor. This study extends the state of knowledge of the technological limit of a divertor based on a RAFM steel pipe structure. |
资助项目 | Innovative Program of Development Foundation of Hefei Center for Physical Science and Technology[2016FXCX009] ; National Natural Science Foundation of China[11505230] ; National Natural Science Foundation of China[11705234] ; National Magnetic Confinement Fusion Science Program of China[2015GB107001] ; RCUK Energy Programme[EP/P012450/1] |
WOS关键词 | HELIUM-COOLED DIVERTOR ; POWER-PLANT ; RECENT PROGRESS ; CLAM STEEL ; DESIGN ; DEMO ; FLOW |
WOS研究方向 | Physics |
语种 | 英语 |
出版者 | IOP PUBLISHING LTD |
WOS记录号 | WOS:000431049700001 |
内容类型 | 期刊论文 |
源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/35261] ![]() |
专题 | 合肥物质科学研究院_中科院等离子体物理研究所 |
通讯作者 | Peng, X. B. |
作者单位 | 1.Chinese Acad Sci, Inst Plasma Phys, Shushanhu Rd 350, Hefei 230031, Anhui, Peoples R China 2.Culham Sci Ctr, CCFE, Abingdon OX14 3DB, Oxon, England 3.Univ Sci & Technol China, Sch Nucl Sci & Technol, Jinzhai Rd 96, Hefei 230026, Anhui, Peoples R China |
推荐引用方式 GB/T 7714 | Mao, X.,Fursdon, M.,Chang, X. B.,et al. Exploring the engineering limit of heat flux of a W/RAFM divertor target for fusion reactors[J]. NUCLEAR FUSION,2018,58(6):13. |
APA | Mao, X..,Fursdon, M..,Chang, X. B..,Zhang, J. W..,Liu, P..,...&Liu, P..(2018).Exploring the engineering limit of heat flux of a W/RAFM divertor target for fusion reactors.NUCLEAR FUSION,58(6),13. |
MLA | Mao, X.,et al."Exploring the engineering limit of heat flux of a W/RAFM divertor target for fusion reactors".NUCLEAR FUSION 58.6(2018):13. |
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