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托卡马克聚变中子源的数值模型研究

徐坤 叶民友 宋云涛 雷明准 毛世峰 刘旭峰

原子能科学技术2017,Vol.51Issue(8):1345-1350,6.
原子能科学技术2017,Vol.51Issue(8):1345-1350,6.DOI:10.7538/yzk.2017.51.08.1345

托卡马克聚变中子源的数值模型研究

Numerical Model of Tokamak D-D/D-T Fusion Neutron Source

徐坤 1叶民友 1宋云涛 2雷明准 2毛世峰 1刘旭峰2

作者信息

  • 1. 中国科学技术大学 核科学技术学院,安徽 合肥 230026
  • 2. 中国科学院 等离子体物理研究所,安徽 合肥 230031
  • 折叠

摘要

Abstract

In Tokamak fusion neutronics,the fusion neutron source description is one of the initial inputs,which affects the neutronics analysis result.Based on the study of fusion neutron source model used in ITER and EU DEMO,a numerical model that uses a set of formulae to describe the L&H-mode plasma D-D/D-T fusion neutron source was addressed.Within the framework of engineering design platform for China Fusion Engineering Test Reactor(CFETR),source card generator(SCG)was developed to solve the numerical model utilizing Monte Carlo method,by which a set of plasma physics parameters were read and the SDEF card for MCNP code was produced.On the basis of neutronics analysis on CFETR with helium cooled pebble bed blanket,neutron wall loading,the tritium breeding ratio and global energy multiplication factor resulting from the SCG-produced SDEF card are of differences at 2.02%,0.18%and 0.23%,respectively,compared with those resulting from EU DEMO source subroutine in L-mode D-T fusion scenario.This numerical model of Tokamak D-D/D-T fusion neutron source and the SCG can be used in the neutronics calculation of CFETR.

关键词

聚变堆/托卡马克/蒙特卡罗方法/聚变中子学

Key words

fusion reactor/Tokamak/Monte Carlo method/fusion neutronics

分类

能源科技

引用本文复制引用

徐坤,叶民友,宋云涛,雷明准,毛世峰,刘旭峰..托卡马克聚变中子源的数值模型研究[J].原子能科学技术,2017,51(8):1345-1350,6.

基金项目

国家磁约束核聚变研究专项资助(2014GB110000) (2014GB110000)

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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