ITER Shield Blanket Design Activities in SWIP

机译：SWIP中的ITER盾牌毯子设计活动

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Design works on ITER shield blanket (BM) started at Southwestern Institute of Physics (SWIP) in the end of 2003 after China joined the ITER negotiation. Two shield blanket modules located in the Neutral Beam (NB) port region were studied at SWIP in cooperation with ITER International Team (IT). One module has a regular shape like the other outboard modules in the normal places. Another module is just besides the NB opening, which has a dog-leg shape and two Beryllium protected surfaces in both NB duct side and main vacuum vessel side. The regular module has the same structure as other regular modules designed by the IT. As the NB port is located at the equatorial level of the tokamak machine, the modules will suffer the highest nuclear heating. Detailed hydraulic and thermal/stress analysis were carried out to optimize the performance and some improvements were made. The special module is configured with 4 FWs, i. e., 3 L- shape FWs in NB duct side and one flat FW in the main vacuum vessel side. The overall structure is compatible with the regular module. The cooling configuration of first L-shape FW, which face both plasma and NB, is also given. Thermal/stress analysis shows that the straight tubes in the vertical part of the FW is feasible, which is in favor of fabrication.

机译：中国参加ITER谈判后，于2003年底开始在西南物理学院（SWIP）进行ITER防护毯（BM）的设计工作。 SWIP与ITER国际团队（IT）合作研究了位于中性束（NB）端口区域的两个屏蔽层模块。一个模块具有正常形状，与其他舷外模块一样。 NB开口旁边还有另一个模块，该模块具有狗腿形形状，并且在NB管道侧和主真空容器侧都有两个铍保护表面。常规模块与IT设计的其他常规模块具有相同的结构。由于NB端口位于托卡马克机的赤道高度，因此模块将遭受最高的核热。进行了详细的液压和热/应力分析以优化性能，并进行了一些改进。特殊模块配置有4个FW，即。例如，在NB导管侧有3个L形FW，在主真空容器侧有1个扁平FW。整体结构与常规模块兼容。还给出了面向等离子体和NB的第一L形FW的冷却配置。热/应力分析表明，FW垂直部分的直管是可行的，这有利于制造。

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《Proceedings of the 9th China-Japan Symposium(CJS-9) on Materials for Advanced for Energy Systems and Fission amp; Fusion Engineering Jointed with CAS-JSPS Core-university Program Seminar on Fusion Materials, System and Design Integration》|2007年|340-346|共7页
会议地点 Guilin(CN);Guilin(CN)
作者
Zhiyong CHANG; rnRong MO; rnHaicheng YANG; rnJie ZHAO;
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J. H. Wu@Southwestern Institute of Physics, P. P. Box 432 Chengdu, 610041, China--F. Zhang@Southwestern Institute of Physics, P. P. Box 432 Chengdu, 610041, China--W. S. Kang@Southwestern Institute of Physics, P. P. Box 432 Chengdu, 610041, China--J. M. Chen@Southwestern Institute of Physics, P. P. Box 432 Chengdu, 610041, China--;

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正文语种 eng
中图分类核燃料及其生产;
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1. ITER Shield Blanket Design Activities at SWIP [J] . ZHANG Fu, KANG Weishan, WU Jihong, 核工业西南物理研究院年报：英文版 . 2006,第001期

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2. Current status of final design and R&D for ITER blanket shield blocks in Korea [J] . M.S. Ha, S.W. Kim, H.C. Jung, Nuclear fusion . 2015,第7期

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3. Heat transfer study for ITER blanket shield block cooling design [J] . Weishan Kang, Tao Yuan, Xiujie Zhang Fusion Engineering and Design . 2014,第2期

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4. ITER Shield Blanket Design Activities in SWIP [C] . China-Japan Symposium(CJS-9) on Materials for Advanced for Energy Systems and Fission Fusion Engineering . 2007

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5. CALCULATIONAL METHODS FOR NUCLEAR HEATING AND NEUTRONICS AND PHOTONICS DESIGN FOR CTR (CONTROLLED THERMONUCLEAR REACTOR) BLANKETS AND SHIELDS. [D] . ABDOU, MOHAMED ABD EL-AZIZ. 1973

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7. Flexible vacuum vessel bolometer camera design in ITER to adapt to the final position of the gaps between Blanket Modules [O] . A. Pataki, D. Hermann, L.C. Ingesson, 2019

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8. US ITER (International Thermonuclear Experimental Reactor) Shield and Blanket Design Activities [R] . Baker, C. C. 1988

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ITER Shield Blanket Design Activities in SWIP

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