Preliminary neutronics analyses of China Dual-Functional Lithium-Lead (DFLL) test blanket module for CFETR

Abstract

China Fusion Engineering Test Reactor (CFETR), as one of the option fusion reactors in China, has been proposed to fill the gap between ITER and fusion DEMO plant. In order to evaluate the neutronics performance in the framework of National Magnetic Confinement Fusion Science Program of China, the neutronics analyses of the detailed model of CFETR with China dual-functional lithium lead (DFLL) test blanket module (TBM) were carried out with the Super Multi-functional Calculation Program for Nuclear Design Safety Evaluation (SuperMC) and JEFF-3.2 nuclear data library. To meet the self-sufficiency target of CFETR, the tritium breeding ratio has been improved to 1.2. Meanwhile, the nuclear heating result showed a potential for energy multiplication factor improvement. From this previous study, an optimized model was proposed to improve the shielding performance and the results showed that the DFLL-TBM with the optimized model could meet the tritium self-sufficiency target and radiation design requirements.