Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module

被引:0
|
作者
Deepak SHARMA [1 ]
Paritosh CHAUDHURI [1 ]
机构
[1] Institute for Plasma Research
关键词
first wall; blanket; breeder unit; thermal hydraulics; structural analysis; HCCB(helium-cooled ceramic breeder);
D O I
暂无
中图分类号
TL64 [热核反应堆(聚变堆)];
学科分类号
082701 ;
摘要
The Indian test blanket module(TBM) program in ITER is one of the major steps in the Indian fusion reactor program for carrying out the R&D activities in the critical areas like design of tritium breeding blankets relevant to future Indian fusion devices(ITER relevant and DEMO).The Indian Lead–Lithium Cooled Ceramic Breeder(LLCB) blanket concept is one of the Indian DEMO relevant TBM,to be tested in ITER as a part of the TBM program.Helium-Cooled Ceramic Breeder(HCCB) is an alternative blanket concept that consists of lithium titanate(Li2TiO3) as ceramic breeder(CB) material in the form of packed pebble beds and beryllium as the neutron multiplier.Specifically,attentions are given to the optimization of first wall coolant channel design and size of breeder unit module considering coolant pressure and thermal loads for the proposed Indian HCCB blanket based on ITER relevant TBM and loading conditions.These analyses will help proceeding further in designing blankets for loads relevant to the future fusion device.
引用
收藏
页码:204 / 214
页数:11
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