Preliminary Three-Dimension Neutronics Design And Analysis Of Helium-Cooled Blanket For A Multi-Functional Experimental Fusion-Fission Hybrid Reactor

FDS-MFX , a multi-functional experimental fusion-fission hybrid reactor based on viable fusion and fission technologies, mainly is utilized to test construction and operation technologies of demonstration hybrid reactor(FDS-SFB), and as a experimental platform, also can provide a good experimental and verification environment for the future technology development of pure fusion reactor. FDS-MFX will carry out three-stage tests successively, in which pure tritium breeding blanket, uranium-fueled helium-cooled blanket and spent-fuel-fueled helium-cooled blanket are utilized respectively. Uranium-fueled helium-cooled blanket include two experimental sub-phases, in first experimental sub-phase, natural uranium is used as the fission fuel to preliminarily verify the construction and operation technologies of demonstration hybrid reactor. In second experimental sub-phase, a high power density that is similar to that of demonstration hybrid reactor should be achieved so that further studies could be conducted in terms neutronics physics, thermal-hydraulics and safety et al to verify blanket relevant technologies of demonstration hybrid reactor.This thesis created FDS-MFX blanket three-dimensional neutronics model with Monte Carlo Automatic Modeling program (MCAM) and conducted a preliminary three-dimensional neutronics design and analysis for two experimental sub-phases of uranium-fueled helium-cooled blanket with multi-functional neutronics simulation system (VisualBUS). In second experimental sub-phase, the design of local high enriched uranium modules was used. Besides, the optimizing calculation and analysis was conducted on the 4 typical layouts of these high enriched modules, one design was chosen as typical reference design, whose maximum average power density(PDmax) was 100MW/m3, 235U loaded mass was about 1 ton and tritium breeding ratio (TBR) was 1.05. the typical reference design can simulate high power density,high neutron flux environment of the demonstration hybrid reactor blanket by using use less high-enriched uranium fuel, thus this design was economical because construction cost was reduced.Based on the typical reference design mentioned above, a preliminary analysis was conducted concerning the radiation damage in blanket first wall materials. the analysis showed that radiation damage in first wall material is only 12.5 dpa, which was affordable,when after its full power operation life end. Then preliminary studies were done to analyze the activation properties of blanket materials, such as radioactivity,decay heat and contact dose rate et al, so to provide preliminary references and advices for FDS-MFX's safety design and waste manage.