Neutronics Comparison Analysis of the Water Cooled Ceramics Breeding  Blanket for CFETR

LI Jia (李佳); ZHANG Xiaokang (张小康); GAO Fangfang (高芳芳); PU Yong (蒲勇)

doi:10.1088/1009-0630/18/2/14

Plasma Science and Technology > 2016 > 18(2): 179-183. > DOI: 10.1088/1009-0630/18/2/14

LI Jia (李佳), ZHANG Xiaokang (张小康), GAO Fangfang (高芳芳), PU Yong (蒲勇). Neutronics Comparison Analysis of the Water Cooled Ceramics Breeding Blanket for CFETR[J]. Plasma Science and Technology, 2016, 18(2): 179-183. DOI: 10.1088/1009-0630/18/2/14

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Neutronics Comparison Analysis of the Water Cooled Ceramics Breeding Blanket for CFETR

1School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230027, China 2Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China

Funds: supported by the National Special Project for Magnetic Confined Nuclear Fusion Energy (Nos. 2013GB108004, 2014GB122000, and 2014GB119000), and National Natural Science Foundation of China (No. 11175207)

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Received Date: January 05, 2015

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Abstract

Abstract

China Fusion Engineering Test Reactor (CFETR) is an ITER-like fusion engineering test reactor that is intended to fill the scientific and technical gaps between ITER and DEMO. One of the main missions of CFETR is to achieve a tritium breeding ratio that is no less than 1.2 to ensure tritium self-sufficiency. A concept design for a water cooled ceramics breeding blanket (WCCB) is presented based on a scheme with the breeder and the multiplier located in separate panels for CFETR. Based on this concept, a one-dimensional (1D) radial built breeding blanket was first designed, and then several three-dimensional models were developed with various neutron source definitions and breeding blanket module arrangements based on the 1D radial build. A set of nuclear analyses have been carried out to compare the differences in neutronics characteristics given by different calculation models, addressing neutron wall loading (NWL), tritium breeding ratio (TBR), fast neutron flux on inboard side and nuclear heating deposition on main in-vessel components. The impact of differences in modeling on the nuclear performance has been analyzed and summarized regarding the WCCB concept design.
- CFETR,
- blanket,
- neutronics modeling,
- nuclear performance

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References (1)

References

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