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

Deepak SHARMA; Paritosh CHAUDHURI

doi:10.1088/2058-6272/aab54a

Plasma Science and Technology > 2018 > 20(6): 65604-065604. > DOI: 10.1088/2058-6272/aab54a

Deepak SHARMA, Paritosh CHAUDHURI. Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module[J]. Plasma Science and Technology, 2018, 20(6): 65604-065604. DOI: 10.1088/2058-6272/aab54a

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

Institute for Plasma Research, Bhat, Gandhinagar, Gujarat—382428, India

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Received Date: November 01, 2017

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Abstract

Abstract

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.
- first wall,
- blanket,
- breeder unit,
- thermal hydraulics,
- structural analysis,
- HCCB (helium-cooled ceramic breeder)

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References (13)

References

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