Nuclear Analyses of Indian LLCB Test Blanket System in ITER

10th Asia Plasma and Fusion Association Conference

Swami, H.L.^1 ; Shaw, A.K.^1 ; Danani, C.^1 ; Chaudhuri, Paritosh^1

Institute for Plasma Research, Near Indira Bridge, Bhat, Gandhinagar

382 428, India^1

关键词: Equipment maintenance;    Nuclear cross sections;    Nuclear fusion reactors;    Replacement strategy;    Shielding capability;    Test blanket module;    Thermal-hydraulic designs;    Tritium breeding blanket;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/823/1/012066/pdf
DOI  :  10.1088/1742-6596/823/1/012066

来源: IOP

【 摘 要 】

Heading towards the Nuclear Fusion Reactor Program, India is developing Lead Lithium Ceramic Breeder (LLCB) tritium breeding blanket for its future fusion Reactor. A mock-up of the LLCB blanket is proposed to be tested in ITER equatorial port no.2, to ensure the overall performance of blanket in reactor relevant nuclear fusion environment. Nuclear analyses play an important role in LLCB Test Blanket System design & development. It is required for tritium breeding estimation, thermal-hydraulic design, coolants process design, radioactive waste management, equipment maintenance & replacement strategies and nuclear safety. The nuclear behaviour of LLCB test blanket module in ITER is predicated in terms of nuclear responses such as tritium production, nuclear heating, neutron fluxes and radiation damages. Radiation shielding capability of LLCB TBS inside and outside bio-shield was also assessed to fulfill ITER shielding requirements. In order to supports the rad-waste and safety assessment, nuclear activation analyses were carried out and radioactivity data were generated for LLCB TBS components. Nuclear analyses of LLCB TBS are performed using ITER recommended nuclear analyses codes (i.e. MCNP, EASY), nuclear cross section data libraries (i.e. FENDL 2.1, EAF) and neutronic model (ITER C-lite v.l). The paper describes a comprehensive nuclear performance of LLCB TBS in ITER.