US plans and strategy for ITER blanket testing
US plans and strategy for ITER blanket testing
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DOI：
10.13182/fst05-a732
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发表时间：
2005-04-01
影响因子：
0.9
通讯作者：
Malang, S
中科院分区：
文献类型：
--
作者：
Abdou, M;Sze, D;Malang, S
在综合聚变环境中测试一揽子概念是热核实验堆的主要目标之一。综合测试模块将在热核实验堆运行的第一天插入热核实验堆，并将提供关于D-T循环聚变可行性的第一批实验数据。随着美国重新加入热核实验堆，美国社会决定大力参与热核实验堆测试包层模块(TBM)计划。美国的ITER-TBM战略已经演变为强调国际合作。根据过去十年来自美国和世界计划的新研发结果，启动了一项研究，以选择美国ITER-TBM的两个全面选项。这项研究由等离子体室社区与材料、PFC、安全和物理学社区合作领导。这项研究的重点是评估候选一揽子概念的关键可行性问题，并与建模和实验的研发密切相关。问题的例子包括MHD绝缘体、碳化硅插件的可行性和与PbLi的兼容性、氚渗透、MHD对热传递的影响、固体增殖“温度窗口”和热力学，以及熔盐的化学控制。美国ITER-TBM选择了双冷却液液体增殖和氦冷却固体增殖包层概念。
Testing blanket concepts in the integrated fusion environment is one of the principal objectives of ITER. Blanket test modules will be inserted in ITER ftom Day 1 of its operation and will provide the first experimental data on the feasibility of the D-T cycle for fusion. With the US rejoining ITER, the US community has decided to have strong participation in the ITER Test Blanket Module (TBM) Program. A US strategy for ITER-TBM has evolved that emphasizes international collaboration. A study was initiated to select the two blanket options for the US ITER-TBM in light of new R&D results from the US and world programs over the past decade. The study is led by the Plasma Chamber community in partnership with the Materials, PFC, Safety, and physics communities. The study focuses on assessment of the critical feasibility issues for candidate blanket concepts and it is strongly coupled to R&D of modeling and experiments. Examples of issues are MHD insulators, SiC insert viability and compatibility with PbLi, tritium permeation, MHD effects on heat transfer, solid breeder "temperature window" and thermomechanics, and chemistry control of molten salts. A dual coolant liquid breeder and a helium-cooled solid breeder blanket concept have been selected for the US ITER-TBM.