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LiPb自冷混合堆包层中子学研究
引用本文:游承伦.LiPb自冷混合堆包层中子学研究[J].核科学与工程,1994(3).
作者姓名:游承伦
作者单位:核工业西南物理研究院
摘    要:研究了LiPb自冷托卡马克混合堆包层的中子学性能;第一壁材料和厚度对中子学性能的影响;Pb和Be的中子增益性能以及包层中功率密度和239Pu的分布,并对中子学性能进行了优化。当聚变功率为200MW,运行因子为0.3时,除氚自给外,每年可生产239Pu130kg。

关 键 词:产氚率,裂变燃料产生率,能量增益

NEUTRONICS SUTDY FOR A LiPb SELF-COOLED BREEDER BLANKET
YOU CHENGLUN.NEUTRONICS SUTDY FOR A LiPb SELF-COOLED BREEDER BLANKET[J].Chinese Journal of Nuclear Science and Engineering,1994(3).
Authors:YOU CHENGLUN
Affiliation:Southwestern Institute of Physics
Abstract:The neutronics performances for a Lipb self-cooled tokamak breeder blanket are studied to take account of the resonance energy and space self shielding effects. The effects of the first wall materials and thicknesses on the neutronics performances, neutron multiplication performances of Lead and Beryllium, distributions of power density and Pu-239 in the blanket are also studied.On the other hand, the optimization for neutronics performance has also been carried out. The results show that an annual production rate of 130 kg Pu-239 can be achieved for fusion power of 200 MW and availability of 0. 3 while breaking even in tritium.
Keywords:tritium breeding ratio fission fuel production ratio energy multiplication
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