Effect of different description of neutron source models on neutronics calculation of CFETR

Qi LIU; Kun XU; Mingzhun LEI; Yuntao SONG

doi:10.11889/j.0253-3219.2017.hjs.40.020604

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Effect of different description of neutron source models on neutronics calculation of CFETR

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Effect of different description of neutron source models on neutronics calculation of CFETR
- NUCLEAR TECHNIQUES Vol. 40, Issue 2, Article number: 020604(2017)
- 作者机构：
  
  1.中国科学技术大学合肥 230031
  2.中国科学院等离子体物理研究所合肥 230031
- 作者简介：
- 基金信息：
  
  National Magnetic Confinement Fusion Energy Development Research Project
- DOI：10.11889/j.0253-3219.2017.hjs.40.020604
  CLC： TL613
- Received：24 October 2016，
  
  Revised：30 November 2016，
  
  Published：10 February 2017
- 稿件说明：
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Qi LIU, Kun XU, Mingzhun LEI, et al. Effect of different description of neutron source models on neutronics calculation of CFETR[J]. Nuclear techniques, 2017, 40(2): 020604
DOI：

Qi LIU, Kun XU, Mingzhun LEI, et al. Effect of different description of neutron source models on neutronics calculation of CFETR[J]. Nuclear techniques, 2017, 40(2): 020604 DOI： 10.11889/j.0253-3219.2017.hjs.40.020604.

摘要

在托卡马克实验装置中，D-T聚变反应释放出的14 MeV高能中子，与周围部件接触会引起包层材料活化、热负载过高等一系列问题，因此在包层设计和优化过程中，相关的中子学计算显得尤为重要。为了研究不同描述的中子源模型对中国聚变工程实验堆（China Fusion Engineering Test Reactor，CFETR）中子学计算的影响，使用基于蒙特卡罗方法的MCNP（Monte Carlo N Particle Transport Code）程序来模拟中子输运过程，分别计算点源、均匀体源、基于L、H、A模约束的中子源模型对不同中子学计算的影响。结果表明，不同描述的中子源模型对氚增殖比影响较小，对中子壁负载和功率密度分布影响比较明显。

Abstract

Background

In Tokamak experiment device

the 14-MeV high-energy neutrons which D-T fusion reaction releases may cause a series of problems such as material activation

high thermal loading and so on when they contact surrounding parts

so the relative neutronics calculation in the process of blanket design and optimization is particularly important.

Purpose

This study aims to analyze the effect of point source

uniform source

neutron source based on L-mode

H-mode

A-mode respectively on different neutronics calculation.

Methods

Using MCNP (Monte Carlo N Particle Transport Code) program based on the Monte Carlo method the neutron transport process is simulated and the effect of different neutron source models is calculated.

Results

Different descriptions of neutron source models have less influence on tritium breeding ratio

but obvious effects on neutron wall loading and power density distribution.

Conclusion

Therefore

proper neutron source model should be applied to calculate different neutronics.

关键词

Keywords

references

X-5 Monte Carlo Team. MCNP-a general Monte Carlo N-particle transport code[R]. LA-UR-03-1987, US: Los Alamos National Laboratory, 2003.

Trkov A. FENDL-2.1: update of an evaluated nuclear data library for fusion applications[EB/OL]. Nuclear Energy Agency, (2004-12). http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/39/079/39079681.pdf?r=1 http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/39/079/39079681.pdf?r=1 .

Y T Song , S T Wu , J G Li , . Concept design of CFETR tokamak machine . IEEE Transactions on Plasma Science , 2014 . 42 ( 3 ): 503 - 509 . DOI: 10.1109/TPS.2014.2299277 http://doi.org/10.1109/TPS.2014.2299277 .

Fischer U. Fusion neutronics[R]. Germany: Karlsruhe Institute of Technology, 2012.

Y Chen , U Fischer , P Pereslavtsev , . The EU power plant conceptual study-neutronic design analyses for near term and advanced reactor models . Wissenschaftliche Berichte Fzka , 2003 . 6763 13 http://s3.amazonaws.com/zanran_storage/bibliothek.fzk.de/ContentPages/18828675.pdf .

C Fausser , A L Puma , F Gabriel , . Tokamak DT neutron source models for different plasma physics confinement modes . Fusion Engineering and Design , 2012 . 87 ( s5-6 ): 787 - 792 . DOI: 10.1016/j.fusengdes.2012.02.025 http://doi.org/10.1016/j.fusengdes.2012.02.025 .

Y Chen , Y Wu . Effect of fusion neutron source numerical models on neutron wall loading in a D-D tokamak device . Plasma Science and Technology , 2003 . 5 ( 2 ): 1749 - 1754 . DOI: 10.1088/1009-0630/5/2/011 http://doi.org/10.1088/1009-0630/5/2/011 .

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