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Development of tritium dynamic transport analysis tool for tritium breeding blanket system using Modelica
Fusion Engineering and Design ( IF 1.9 ) Pub Date : 2020-12-01 , DOI: 10.1016/j.fusengdes.2020.112023 Ruyan Li , Xiaoyu Wang , Long Zhang , Jun Wang
Fusion Engineering and Design ( IF 1.9 ) Pub Date : 2020-12-01 , DOI: 10.1016/j.fusengdes.2020.112023 Ruyan Li , Xiaoyu Wang , Long Zhang , Jun Wang
Abstract Demonstration of the engineering feasibility of tritium breeding, including tritium generation, tritium extraction, tritium control and tritium safety is one of the main objectives of ITER Testing Blanket Module (TBM) Program. As one of TBM concepts, the tritium transport assessment of the China Helium Cooled Ceramic Breeder TBM and its ancillary systems (called test blanket system, TBS) is absolutely vital to understand and analyze the dynamic tritium behaviors in the system in detail according to the ITER operation scenario. Considering the requirements of the tritium transport analysis for the HCCB TBS, an integrated dynamic tritium transport analysis tool has been developed by the system simulation language “Modelica”. The multiple dynamic physics effects are considered in the tool, including the aspects impacting the tritium transport, simplified thermal-hydraulics considering only the linear loss and local loss in fluid, 1-d thermal conduction in solid, hydrogen isotope transport in fluid, 1-d tritium permeation in solid, tritium solution and recombination on solid surfaces, tritium desorption from ceramic breeder etc. A simplified model of the HCCB TBS is modeled to verify the functions and accuracy of this tool. The results, such as dynamic change of tritium concentration/partial pressure in fluids, dynamic change of tritium inventory in solids, tritium permeation fluxes etc., have been obtained, which are preliminary verified at various aspects by comparing with analytical and hand calculations.
更新日期：2020-12-01
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