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NUCLEAR FUSION AND PLASMA PHYSICS ›› 2020, Vol. 40 ›› Issue (3): 275-282.DOI: 10.16568/j.0254-6086.202003013

• Nuclear Fusion Engineering and Technology • Previous Articles     Next Articles

Neutronics analyses of water-cooled ceramic breeder blanket for the updated CFETR model

LI Xia1, 2, MA Xue-bin3, LU Peng3, ZHENG Yu1, 2, XU Kun1, LIU Song-lin1   

  1. (1. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031; 2. University of Science and Technology of China, Hefei 230026; 3. Shenzhen University, Shenzhen 518060)
  • Received:2019-01-11 Revised:2019-12-05 Online:2020-09-15 Published:2020-09-16

CFETR水冷陶瓷增殖剂包层中子学分析

李 夏1, 2,马学斌3,卢 棚3,郑 俞1, 2,徐 坤1,刘松林*1   

  1. (1. 中国科学院等离子体物理研究所,合肥 230031;2. 中国科学技术大学,合肥 230026;3. 深圳大学,深圳 518060)
  • 作者简介:李夏(1993-),男,安徽六安人,硕士研究生,研究方向为聚变堆中子学。
  • 基金资助:
    国家重点研发计划(2017YFE0300503)

Abstract: Based on a three-dimensional water-cooled ceramic breeder (WCCB) blanket model for the China Fusion Engineering Test Reactor (CFETR), neutronics analyses are performed by utilizing the MCNP5 code and the IAEA Fusion Evaluated Nuclear Data Library FENDL2.1. The results include neutron wall loading (NWL), tritium breeding ratio (TBR), nuclear heating power and radiation damage under 200MW, 500MW, 1.0GW, 1.5GW fusion power. The results show that the neutronics analyses of WCCB meet the design requirements of CFETR.

Key words: CFETR, WCCB blanket, Neutronics calculations

摘要: 基于中国聚变工程实验堆(CFETR)水冷陶瓷增殖剂(WCCB)三维中子学模型,应用蒙特卡罗输运程序MCNP5和IAEA聚变评价核数据库FENDL2.1,完成了WCCB中子学性能分析。研究了在200MW、500MW、1.0GW、1.5GW聚变功率下中子壁载荷(NWL)、氚增殖率(TBR)、核热沉积以及包层材料的辐照损伤。结果显示,目前WCCB包层核分析结果满足CFETR设计要求。

关键词: CFETR, 水冷包层, 中子学计算

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