期刊文献+

国际热核聚变堆实验增殖包层模块设计 被引量:3

Overview of international thermonuclear experimental reactor test blanket module design
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摘要 为了验证国际热核聚变堆(ITER)的产氚和能量获取等性能,各国分别提出了不同的实验增殖模块(TBM)设计方案。其总体功能相同,但具体技术路线有区别,不同之处包括冷却剂选择、产氚材料选择、中子倍增剂选择、产氚区布置形式、面向等离子体材料选择、结构材料选择等方面。通过对各TBM方案进行比较分析,评价了各自的优缺点,提出了未来先进产氚包层方案的设计建议。 The Test Blanket Module(TBM)Program has come into the engineering stage with the advance of the ITER project,and the basic TBM design of each ITER member has been fixed.All the TBMs share the same overall objectives,but differ in detailed designs,such as the coolant,tritium breeder,neutron multiplier,plasma facing components material and structural material,etc.The choices of the TBM designs are compared,the advantages and disadvantages of different choices are analyzed.
出处 《强激光与粒子束》 EI CAS CSCD 北大核心 2015年第1期254-258,共5页 High Power Laser and Particle Beams
基金 国家磁约束核聚变能研究专项(2012GB106001)
关键词 热核反应堆 实验增殖包层 材料 物理热工 international thermonuclear experimental reactor test blanket module materials neutronic-hydraulic
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参考文献25

  • 1Giancarli L M. Overview of the ITER TBM program[J]. Fusion Engineering and Design, 2012, 87(5/6) : 395-402. 被引量:1
  • 2Rene R A. Overview of the design and R&D of the ITER blanket system[J]. Fusion Engineering and Design, 2012, 87(5/6) : 769-776. 被引量:1
  • 3Zmitko M, Poitevin Y. Development and qualification of functional materials for the EU test blanket modules: Strategy and R and D activi ties[J]. Journal of Nuclear Materials, 2011,417 (1/3): 678- 683. 被引量:1
  • 4Ying A. Status and perspective of the R&D on ceramic breeder materials for testing in ITER[J]. Journal of Nuclear Materials, 2007, 367/ 370(1): 1281 -1286. 被引量:1
  • 5Nishitani T. Recent progress in blanket materials development in the broader approach activities[J]. Journal of Nuclear Materials, 2011, 417(1/3) : 1331-1335. 被引量:1
  • 6Uchida M. Elementary development of beryllide pebble fabrication by rotating electrode method[J]. Fusion Engineering and Design, 2003, 69(1/4) : 491-493. 被引量:1
  • 7Tobita K. Search for reality of solid breeder blanket for DEMO[J]. Fusion Engineering and Design, 2010, 85(7/9) : 1342-1347. 被引量:1
  • 8Muroga T. Neutronics investigation into lithium/vanadium test blanket modules[J]. Fusion Science and Technology, 2005, 47 (3) : 540- 543. 被引量:1
  • 9Aiello G. HCLL TBM design status and development[J]. Fusion Engineering and Design, 2011, 85(9/11): 2129- 2134. 被引量:1
  • 10Wong C P C. An overview of dual coolant Pb-17Li breeder first wall and blanket[J]. Fusion Engineering and Design, 2006, 81(1/7) : 461- 467. 被引量:1

二级参考文献23

  • 1Sawan M E , et al. Physics and technology conditions for attaining tritium self-sufficiency for the DT fuel cycle [J].Fusion Engineering and Design, 2006, 81:1131- 1144. 被引量:1
  • 2Abdou M, Void E, Gung C, Youssef M, Shin K. Deuteriumtritium fuel self-sufficiency in fusion reactors[J]. Fusion Technology, 1986,9 : 250-285. 被引量:1
  • 3Billone Michael C, et al. Status of beryllium development for fusion applications[R], presented at the Third International Symposium on Fusion Nuclear Technology. University of California at Los Angeles, 1994. 被引量:1
  • 4Pint B A, et al. Liquid metal compatibility issues for test blanket modules[J].Fusion Engineering and Design, 2006, 81: 901-908. 被引量:1
  • 5Norajitra P, et al. The EU advanced lead lithium blanket concept using SiCf/SiC flow channel inserts as electrical and thermal insulators[J]. Fusion Engineering and Design , 2001,58-59:629-634. 被引量:1
  • 6Moriyama H, et al. Molten salts in fusion nuclear technology[J]. Fusion Engineering and Design, 1998, 39- 40: 627-637. 被引量:1
  • 7Kulsartov T V, et al. Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 (out-of- pile tests)[J].Fusion Engineering and Design, 2006, 81: 701-705. 被引量:1
  • 8Reimann J, Hermsmeyer S. Thermal conductivity of compressed ceramic breeder pebble beds[J].Fusion Engineering and Design, 2002, 61-62:345-351. 被引量:1
  • 9Muroga T, et al. Blanket neutronics of Li/vanadium-alloy and Flibe/vanadium-alloy systems for FFHR[J]. Fusion Engineering and Design, 2006, 81:1203-1209. 被引量:1
  • 10Maisonnier D, et al. Power plant conceptual studies in Europe[J]. Nuclear Fusion, 2007,47:1524-1532. 被引量:1

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