核石墨与熔盐相容性测试装置设计与实验

唐辉; 贺周同; 张灿; 汪雪; 夏汇浩

doi:10.11889/j.0253-3219.2018.hjs.41.070605

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核石墨与熔盐相容性测试装置设计与实验

核能科学与工程 | 更新时间：2021-05-19

- 核石墨与熔盐相容性测试装置设计与实验
- Equipment design and experiment of compatibility test of nuclear graphite and molten salt
- 核技术 2018年41卷第7期文章编号：070605
- 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：
  
  [ "唐辉, 男, 1986年出生, 2012年于上海交通大学获硕士学位, 现为博士研究生, 从事石墨材料与熔盐相容性评估", "TANG Hui, male, born in 1986, graduated from Shanghai Jiao Tong University with a master's degree in 2012, doctoral student, engaged in evaluation of compatibility of graphite materials and molten salt" ]
  夏汇浩, E-mail:xiahuihao@sinap.ac.cn XIA Huihao, E-mail: xiahuihao@sinap.ac.cn
- 基金信息：
  
  国家自然科学基金(11305240);国家自然科学基金(51602336)
- DOI：10.11889/j.0253-3219.2018.hjs.41.070605
  中图分类号： TL342
- 收稿日期：2018-01-26，
  
  修回日期：2018-03-13，
  
  纸质出版日期：2018-07-10
- 稿件说明：
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唐辉, 贺周同, 张灿, 等. 核石墨与熔盐相容性测试装置设计与实验[J]. 核技术, 2018,41(7):070605

Hui TANG, Zhoutong HE, Can ZHANG, et al. Equipment design and experiment of compatibility test of nuclear graphite and molten salt[J]. Nuclear techniques, 2018, 41(7): 070605
唐辉, 贺周同, 张灿, 等. 核石墨与熔盐相容性测试装置设计与实验[J]. 核技术, 2018,41(7):070605 DOI： 10.11889/j.0253-3219.2018.hjs.41.070605.

Hui TANG, Zhoutong HE, Can ZHANG, et al. Equipment design and experiment of compatibility test of nuclear graphite and molten salt[J]. Nuclear techniques, 2018, 41(7): 070605 DOI： 10.11889/j.0253-3219.2018.hjs.41.070605.

摘要

钍基熔盐堆（Thorium Molten Salt Reactor，TMSR）是以核石墨为反射体及慢化体、2LiF-BeF

（FLiBe）熔盐为主冷却剂的反应堆。在TMSR中，核石墨直接与熔盐接触。由于石墨的多孔特性，熔盐有可能渗入石墨的孔隙中，引发其力学、热学性能的变化。研究熔盐在TMSR环境下是否渗入候选核石墨及其浸渗量，对于反应堆的运行安全至关重要。基于自行研制的熔盐浸渗实验装置，采用静态熔盐浸渗试验方法，测试TMSR候选核石墨T220在不同压强下的熔盐浸渗量，并研究了温度、时间对T220、NBG-18及IG-110石墨材料熔盐浸渗行为的影响。研究结果表明：T220石墨的临界浸渗压强介于600~700 kPa之间，这说明在TMSR工况下（

500 kPa）该石墨不发生FLiBe熔盐浸渗。温度（600℃和700℃）及时间（20~2000 h）对三个牌号石墨熔盐浸渗行为影响不大。

Abstract

Background

Thorium molten salt reactor (TMSR) is a nuclear fission reactor using nuclear graphite as neutron reflector and moderator and molten 2LiF-BeF

(FLiBe) salt as primary coolant. In TMSR

graphite is directly in contact with the molten salt. Given the porous nature of graphite

molten salt may penetrate into its pores in molten salt reactor environments

which may change graphite's thermal and mechanical properties.

Purpose

This study aims to verify whether the FLiBe salt penetrates into candidate nuclear graphite and to test the amount of infiltrated molten salt

which is of vital importance to the safety in operation of the reactor.

Methods

An equipment used for static infiltration tests was developed to investigate the infiltration rate of molten FLiBe salt into graphite materials under different pressures. Effects of temperature and duration on the molten salt infiltration behaviors of graphite materials were also studied.

Results

The threshold pressure for FLiBe salt infiltration for TMSR candidate graphite T220 was between 600 kPa and 700 kPa at 700℃. The higher the infiltration pressure

the greater the infiltration rate

while the increase amplitude decreased gradually. The infiltration rate of three grades of graphite after infiltration tests in different temperatures (600℃ and 700℃) and durations (20~2000 h) showed no significant difference.

Conclusion

FLiBe salt could not penetrate into graphite T220 in TMSR environments (< 500 kPa). Both factors of temperature and duration had little effects on infiltration behaviors of graphite materials.

关键词

Keywords

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