期刊文献+

ITER第一壁、偏滤器靶板和壁的热负荷计算 被引量:1

Power Flux Calculation of First Wall, Divertor Plate and Wall of ITER
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摘要 ITER-FEAT是国际热核聚变实验堆设计,除了继续演示聚变物理和D-T燃烧的科学可行性外,更重要的是为了演示包层整体组合、氚增殖、氚回收、氚泄漏等工程问题。在设计包层时,需要进行中子学计算得到氚增殖率、辐射损伤率、活化放射性强度、磁体及其屏蔽厚度的计算、核加热产生率和冷却系统设计和安排的必要数据,而这一切都必须先知道第一壁和偏滤器靶板的中子壁负荷(即中子功率通量)和热负荷;为此作了必要的先行准备计算工作。 ITER-FEAT is the design of international thermonuclear experimental reactor. Except for to demonstrate scientific feasibility of fusion physics and D-T reaction, it is more important that it will demonstrate the technology of blanket, tritium breeding, tritium recovery and tritium leak. When blanket is designed, some necessary data, including tritium breeding ratio, irradiation damage ratio, intensity of activation radiation, magnet and thickness of shield, can be get through neutronics calculation. All of that must base on heat load and neutron power flux of first wall and divertor plate. So, the preparative calculation is prformed for that.
出处 《科学技术与工程》 2004年第9期772-774,共3页 Science Technology and Engineering
基金 国家自然科学基金(40172101)资助
关键词 ITER第一壁 偏滤器 热负荷 中子功率通量 ITER first wall divertor heat load neutron power flux
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参考文献4

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同被引文献15

  • 1康伟山,潘传杰,许增裕.液态金属自由表面在聚变堆中的运用研究[J].科学技术与工程,2006,6(6):731-738. 被引量:6
  • 2Martin G, Lipa M. Li3: first step studies of a liquid lithium limiter [J]. Fusion Engineering and Design, 2002, 61-62: 237-243.
  • 3Igor E L, Alexey V V. Experience and technical issues of liquid lithium application as plasma facing material in tokamaks [J]. Fusion Engineering and Design, 2010, 85: 924-929.
  • 4邓柏权,黄锦华,严建成.流动液态锂第一壁的物理可行性研究[R].北京:中国核科技报告,2002,66-70.
  • 5Whyte D G, Evans T E, Wong C P, et al. Experimental observations of lithium as a plasma-facing surface in the DIII-D tokamak divertor [J]. Fusion Engineering and Design, 2004, 72: 133-147.
  • 6Majeski R, Boaz M, Hoffrnan D, et al. CDX-U operation with a large area liquid lithium limiter [J]. J. Nucl. Mater., 2003, 313-316: 625-629.
  • 7Robert Kaita, Laura Berzak, Dennis Boyle, et al. Experiments with liquid metal walls: status of the lithium tokamak experiment [J]. Fusion Engineering and Design, 2010, 85: 874-881.
  • 8Brooks J N, Rognlien T D, Ruzic D N, et al. Erosion/redeposition analysis of lithium-based liquid surface divertors [J]. J. Nucl. Mater., 2001, 290-293: 185-190.
  • 9Allain J P, Nieto M, Coventry M D, et al. Studies of liquid-metal erosion and free surface flowing liquid lithium retention of helium at the University of Illinois [J]. Fusion Engineering and Design, 2004, 72:93-110.
  • 10Khripunov B I, Petrov V B, Shapkin V V, et al. Experimental study of lithium target under high power load [J]. J. Nucl. Mater., 2001, 290-293: 201-205.

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