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核聚变与等离子体物理 ›› 2015, Vol. 35 ›› Issue (4): 327-333.DOI: 10.16568/j.0254-6086.201504007

• 核聚变工程技术 • 上一篇    下一篇

紧凑型托卡马克聚变实验堆包层设计及中子学分析

缪 鹏1, 2,王苏豪1, 2,张国书2,冯开明2   

  1. (1. 中国科学技术大学,合肥 230027;2. 核工业西南物理研究院,成都 610041)
  • 出版日期:2015-12-15 发布日期:2015-12-15
  • 作者简介:缪鹏(1989-),男,四川绵阳人,硕士研究生,核科学与技术专业。
  • 基金资助:

    国家磁约束核聚变能发展研究专项(2014GB110004)

Blanket design and neutronics analysis for compact tokamak test reactor

MIAO Peng1, 2, WANG Su-hao1, 2, ZHANG Guo-shu2, FENG Kai-ming2   

  1. (1. University of Science and Technology of China, Hefei 230027; 2. Southwestern Institute of Physics, Chengdu 610041)
  • Online:2015-12-15 Published:2015-12-15

摘要:

利用蒙特卡罗粒子输运程序MCNP,对紧凑型托卡马克(CT)聚变实验堆方案进行了三维中子学计算分析,特别是氚增殖比(TBR)计算。包层采用了氦冷固态包层(HCCB Blanket)概念,选用正硅酸锂(Li4SiO4)作为氚增殖剂,铍作为中子倍增剂,低活化铁素体钢为结构材料。给出了不同增殖单元在不同的排列方式下,TBR 随增殖单元厚度的变化情况,得到了满足氚自持条件下的初步优化的包层设计方案,给出了相关中子壁负载、能量沉积和功率密度的相关特性结果,为后续热工水力和相关设计分析提供了数据支持。

关键词: HCCB 包层, 氚增殖比, 中子学分析

Abstract:

Using Monte Carlo particle transport code MCNP, the 3D neutronics analysis as well as TBR calculation for high power compact tokamak (CT) test reactor were done. The structure design for helium cooling ceramic breeder (HCCB) blanket was carried out with Li4SiO4, Be and the low activated ferrite steel as the tritium breeder, neutron multiplier and structural material respectively. The variation of TBR vs the breeding unit thickness was simulated, under different breeding unit with different structure arrangement. The preliminary optimum design of blanket with tritium self-sufficiency was obtained. The related characteristics of neutron wall loading, energy deposit and power density was given, as supplies data support for the thermal hydraulics and related design and analysis in next step.

Key words: HCCB blanket, TBR, Neutronics analysis

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