The infiltration behavior and chemical compatibility of molten lead-bismuth eutectic in nuclear graphite at elevated temperature

被引:1
作者
He, Zhao [1 ,2 ,3 ]
Liu, Zhanjun [1 ,2 ]
Marrow, T. James [3 ]
Song, Jinliang [4 ]
机构
[1] Chinese Acad Sci, Inst Coal Chem, Key Lab Carbon Mat, Taiyuan 030001, Peoples R China
[2] Univ Chinese Acad Sci, Ctr Mat Sci & Optoelect Engn, Beijing 100049, Peoples R China
[3] Univ Oxford, Dept Mat, Oxford OX1 3PH, England
[4] Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China
基金
中国国家自然科学基金;
关键词
Compact high temperature reactor; Nuclear graphite; Lead-bismuth eutectic; Infiltration behavior; Barrier property; Chemical compatibility; FLINAK SALT INFILTRATION; FLUORIDE SALT; BARRIER PROPERTY; MICROSTRUCTURE; EXPANSION; IG-110; ALLOY;
D O I
10.1016/j.jnucmat.2021.152921
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Six grades of commercial nuclear graphite of different microstructures (NBG-17, NBG-18, NBG-25, IG-110, NGCT-50 and ZXF-5Q) were infiltrated with molten lead-bismuth eutectic (LBE) at 800 degrees C and a series of pressures to evaluate their barrier property to molten LBE. Molten LBE infiltration caused a decrease of the (002) interlayer spacing and an increase of mean crystallite dimension perpendicular to the (002) diffracting plane. This is ascribed to compressive stress evolution from the infiltration and subsequent solid-state phase transformation of LBE. One representative graphite (IG-110) was immersed in molten LBE at 800 degrees C for 10 0 0 hours and no evidence of corrosion was detected, which has preliminarily verified the chemical stability of graphite in molten LBE. This work indicates that nuclear graphite with small pores has great chance to act as coolant channel material for compact high temperature reactor. (c) 2021 Elsevier B.V. All rights reserved.
引用
收藏
页数:10
相关论文
共 37 条
[11]  
He Z., 2021, J NUCL MATER, P547
[12]  
He Z, 2019, NUCL ENG TECHNOL, V51, P1390
[13]   Fine-grained graphite with super molten salt barrier property produced from filler of natural graphite flake by a liquid-phase mixing process [J].
He, Zhao ;
Liu, Zhanjun ;
Song, Jinliang ;
Lian, Pengfei ;
Guo, Quangui .
CARBON, 2019, 145 :367-377
[14]   Microstructure and properties of fine-grained isotropic graphite based on mixed fillers for application in molten salt breeder reactor [J].
He, Zhao ;
Lian, Pengfei ;
Song, Jinliang ;
Zhang, Dongqing ;
Liu, Zhanjun ;
Guo, Quangui .
JOURNAL OF NUCLEAR MATERIALS, 2018, 511 :318-327
[15]   Improving molten fluoride salt and Xe135 barrier property of nuclear graphite by phenolic resin impregnation process [J].
He, Zhao ;
Lian, Pengfei ;
Song, Yan ;
Liu, Zhanjun ;
Song, Jinliang ;
Zhang, Junpeng ;
Feng, Jing ;
Yan, Xi ;
Guo, Quangui .
JOURNAL OF NUCLEAR MATERIALS, 2018, 499 :79-87
[16]   Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane [J].
He, Zhao ;
Lian, Pengfei ;
Song, Yan ;
Liu, Zhanjun ;
Song, Jinliang ;
Zhang, Junpeng ;
Ren, Xiaobo ;
Feng, Jing ;
Yan, Xi ;
Guo, Quangui ;
Liu, Wenhong .
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, 2018, 38 (02) :453-462
[17]   Molten FLiNaK salt infiltration into degassed nuclear graphite under inert gas pressure [J].
He Zhoutong ;
Gao Lina ;
Qi Wei ;
Zhang Baoliang ;
Wang Xue ;
Song Jinliang ;
He Xiujie ;
Zhang Can ;
Tang Hui ;
Holmes, Rohan ;
Xia Huihao ;
Zhou Xingtai .
CARBON, 2015, 84 :511-518
[18]   Improvement of stacking order in graphite by molten fluoride salt infiltration [J].
He Zhoutong ;
Gao Lina ;
Wang Xue ;
Zhang Baoliang ;
Qi Wei ;
Song Jinliang ;
He Xiujie ;
Zhang Can ;
Tang Hui ;
Xia Huihao ;
Zhou Xingtai .
CARBON, 2014, 72 :304-311
[19]   Porosity analysis of superfine-grain graphite IG-110 and ultrafine-grain graphite T220 [J].
Huang, Qing ;
Tang, Hui .
MATERIALS SCIENCE AND TECHNOLOGY, 2019, 35 (08) :962-968
[20]   Liquid metal embrittlement susceptibility of a high-entropy alloy exposed to oxygen-depleted liquid lead-bismuth eutectic at 250 and 350 °C [J].
Huang, Xi ;
Gong, Xing ;
Song, Min ;
Chen, Jiajun ;
Hu, Feiyu ;
Yin, Yuan ;
Xiao, Jun ;
Wang, Hui ;
Wang, Hao ;
Gong, Haoran ;
Deng, Yangbin ;
Pang, Bo ;
Li, Yongchun .
JOURNAL OF NUCLEAR MATERIALS, 2020, 528