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Neutronics analyzation of helium cooled solid breeder blanket in a fusion reactor
Jia Xiaobo ; Yang Yongwei ; Zhou Zhiwei ; Jing Xingqing
2010-05-10 ; 2010-05-10
关键词Practical/ fusion reactor blankets fusion reactor theory Monte Carlo methods neutron flux neutron sources nuclear engineering computing tritium handling/ neutronics analyzation helium cooled solid breeder blanket fusion reactor neutron fluxes neutron multiplier layers D shape torus global reactor model fusion neutron source distribution tritium breeding performance nuclear heat generation Monte Carlo N-Particle transport code peak nuclear heating density/ A2852F Fusion reactor materials A2820 Neutron physics A2852J Fusion reactor theory and design A2925D Neutron sources
中文摘要The neutron fluxes in the preliminary design of the helium cooled solid breeder blanket of a fusion solid breeder reactor were analyzed for various arrangements of the tritium breeder and neutron multiplier layers. A 20 degrees symmetric D shape torus global reactor model was used for the calculations with the fusion neutron source distribution treated discretely. The tritium breeding performance and the nuclear heat generation in the blanket were evaluated by using Monte Carlo N-Particle transport code. The results show that the global tritium breeding ratio reaches 1.247 with the peak nuclear heating density located along the equator of the blanket module. The tritium production can be designed to be self-consistent in the fusion reactor.
语种中文 ; 中文
出版者Tsinghua Univ. Press ; China
内容类型期刊论文
源URL[http://hdl.handle.net/123456789/22906]  
专题清华大学
推荐引用方式
GB/T 7714
Jia Xiaobo,Yang Yongwei,Zhou Zhiwei,et al. Neutronics analyzation of helium cooled solid breeder blanket in a fusion reactor[J],2010, 2010.
APA Jia Xiaobo,Yang Yongwei,Zhou Zhiwei,&Jing Xingqing.(2010).Neutronics analyzation of helium cooled solid breeder blanket in a fusion reactor..
MLA Jia Xiaobo,et al."Neutronics analyzation of helium cooled solid breeder blanket in a fusion reactor".(2010).
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