组件型熔盐堆燃料组件的设计研究

薛春; 张海青; 朱智勇; 林俊

doi:10.11889/j.0253-3219.2016.hjs.39.090602

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组件型熔盐堆燃料组件的设计研究

核能科学与工程 | 更新时间：2021-05-24

- 组件型熔盐堆燃料组件的设计研究
- Design of fuel assembly for molten-salt-cooled reactors
- 核技术 2016年39卷第9期文章编号：090602
- 作者机构：
  
  1.中国科学院上海应用物理研究所嘉定园区上海 201800
  2.中国科学院大学北京 100049
- 作者简介：
  
  [ "薛春,男,1989年出生,2012年毕业于中国矿业大学,现为博士研究生,研究领域为反应堆物理", "XUE Chun, male, born in 1989, graduated from China University of Mining and Technology in 2012, doctoral student, focusing on reactor physics" ]
  张海青,E-mail:zhanghaiqing@sinap.ac.cn ZHANG Haiqing,E-mail:zhanghaiqing@sinap.ac.cn.
  朱智勇,E-mail:zhuzhiyong@sinap.ac.cn ZHU Zhiyong, E-mail:zhuzhiyong@sinap.ac.cn.
- 基金信息：
  
  中国科学院战略先导科技专项(No.XDA02030200)
- DOI：10.11889/j.0253-3219.2016.hjs.39.090602
  中图分类号： TL32
- 收稿日期：2016-05-27，
  
  修回日期：2016-07-19，
  
  纸质出版日期：2016-09
- 稿件说明：
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薛春, 张海青, 朱智勇, 等. 组件型熔盐堆燃料组件的设计研究[J]. 核技术, 2016,39(9):090602

Chun XUE, Haiqing ZHANG, Zhiyong ZHU, et al. Design of fuel assembly for molten-salt-cooled reactors[J]. Nuclear techniques, 2016, 39(9): 090602
薛春, 张海青, 朱智勇, 等. 组件型熔盐堆燃料组件的设计研究[J]. 核技术, 2016,39(9):090602 DOI： 10.11889/j.0253-3219.2016.hjs.39.090602.

Chun XUE, Haiqing ZHANG, Zhiyong ZHU, et al. Design of fuel assembly for molten-salt-cooled reactors[J]. Nuclear techniques, 2016, 39(9): 090602 DOI： 10.11889/j.0253-3219.2016.hjs.39.090602.

摘要

熔盐堆是第四代核反应堆的六种构型之一，具有良好的经济性和固有安全性。以球形包覆颗粒燃料元件为基本单元设计了可用于熔盐冷却高温堆的燃料组件，并在此燃料组件模型下构建了组件型熔盐堆堆芯，研究了组件容器材料的种类、密度、厚度以及球形燃料元件中包覆颗粒填充率、FLiBe熔盐中

Li富集度对无限介质增殖因数

inf

、冷却剂反应性温度系数（Reactivity Temperature Coefficient

RTC）、排空反应性（Void Reactivity

VR）的影响。结果表明，作为组件材料，碳材料明显优于碳化硅材料；提高包覆颗粒（Tristructural Isotropic

TRISO）填充率、

Li富集度有利于提高堆芯的中子经济性和安全性。

Abstract

Background

Molten salt reactor(MSR)

a fourth generation reactor

possesses good economy and inherent safety properties.By using the fuel assembly in molten-salt-cooled reactor

it is expected that the fuel load and release can be easier and reliable

which is similar to that widely used in LWR(Light Water Reactor).

Purpose

Based on spherical TRISO(Tristructural Isotropic)coated particle fuel elements

this study aims to design a fuel assembly model for the high-temperature molten-salt-cooled reactor.

Methods

The MCNP(A Monte Carlo N-Particle Transport Code)is employed to investigate the feasibility and behavior of the fuel assembly by analyzing the infinite multiplication factor

inf

the reactivity temperature coefficient(RTC)and the void reactivity(VR)of the FLiBe coolant as a function of the composition

density and wall thickness of the assembly material

the TRISO coated particles packing factor and the enrichment of

Li in FLiBe salt.

Results and Conclusion

The results show that carbon-based materials are significantly better than silicon-carbide-based materials for fuel assembly.Increasing the TRISO packing factor and enrichment of

Li helps to improve neutron economy and security properties of the reactor.

关键词

Keywords

references

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