LOFA analysis in helium and Pb-Li circuits of LLCB TBM by FE simulation

10th Asia Plasma and Fusion Association Conference

Chaudhuri, Paritosh^1 ; Ranjithkumar, S.^1 ; Sharma, Deepak^1 ; Danani, Chandan^1

Institute for Plasma Research, Bhat, Gandhinagar, Gujarat

382428, India^1

关键词: Accident analysis;    Electricity production;    High-pressure helium;    Safety requirements;    Steady state and transients;    Thermal hydraulics;    Thermal-hydraulic simulations;    Tritium breeding blanket;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/823/1/012016/pdf
DOI  :  10.1088/1742-6596/823/1/012016

来源: IOP

【 摘 要 】

One of the main ITER objectives is to demonstrate the feasibility of the breeding blanket concepts that would lead to tritium self-sufficiency and the extraction of a high-grade heat for electricity production. India has developed the LLCB TBM to be tested in ITER for the validation of design concepts for tritium breeding blankets relevant DEMO and future power reactor. LLCB concept has the unique features of combination of both solid (lithium titanate as packed pebble bed) and liquid breeders (molten lead lithium). India specific IN-RAFMS is the structural material for TBM. The First Wall is actively cooled by high-pressure helium (He) gas [1]. It is important to validate the design of TBM to withstand various loads acting on it including accident analysis like LOCA, LOFA etc. Detailed thermal-hydraulic simulation studies including LOFA in helium and Pb-Li circuits of LLCB TBM have been performed using Finite Element using ANSYS. These analyses will provide important information about the temperature distribution in different materials used in TBM during steady state and transient condition. Thermal-hydraulic safety requirement has also been envisaged for the initiation the FPPS (Fusion Power Shutdown System) during LOFA. All these analysis will be presented in detail in this paper.