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[en] Based on Fusion Experimental Breeder (FEB) engineering outline design, a dynamic subsystem model is constructed for tritium fuel cycle system. A computer simulation code-SWITRIM has been developed to simulate the tritium fuel cycle system. The tritium inventories in 10 subsystems are calculated during one year operation period

[en] A computer code ISOGFN-III and its associated data library BULIB have been developed for fusion-fission hybrid reactor burnup calculations. These are used to calculate burnup of a Tokamak commercial hybrid reactor (TCB). The code and library are introduced brielfy, and burnup calculation results are given

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[en] The effect of radial distribution of U-233 has been studied. The support ratio has been optimized by adjusting Li-6 enrichment and blanket arrangment. Satisfactory results are obtained. As the distribtuion of produced U-233 is flattened, the zonal charge and discharge of fuel are unnecessary. Tritium breeding ratio T and support ratio N reach to 1.11 and 14 respectively. The enginerring safety and environmental performance are improved

[en] As a fusion breeder, one of the most important figure is support ratio which reflects the economic and fuel production performance of the system to a great extent. In this paper, the support ratio is calculated by using one dimension transport program ANISN and optimized by adjusting ⁶Li enrichment and blanket arrangement. The radial distribution of producted U-233 is also taken into account. Measures are taken for better blanket design, and satisfactory results are obtained. Tritium breeding ratio T reaches 1.11 and the support ratio is enhanced from 11 to 14. The engineering, safety and environment performance are improved

[en] Utilizing present available experimental data on alpha removal, time-dependent thermal alpha accumulation rates have been calculated assuming that the alpha particles follow classical local prompt thermalization. Allowable effective alpha particle confinement time for FEB normal operation has been assessed from the power balance and alpha particle balance equations. The result is fairly consistent with that calculated directly from the experimental database. Helium poisoning effects are also discussed. Numerical studies on the pumping efficiency of helium removal have been obtained using a 2-D Monte-Carlo technique to simulate helium transport in the vicinity of divertor target plate. Some geometrical parameters and divertor plasma parameters sensitive to the pumping efficiency have been studied

[en] A computer code ISOGEN-III and its associated data library BULIB have been developed for fusion-fission hybrid reactor burnup calculations. These are used to calcuate burnup of a tokamak commercial hybrid reactor. The code and library are introduced briefly, and burnup calculation results are given