Finite Element Model for the Interaction of Liquid Metals with Reactor Steel

被引：1

作者：

Chikova, O. A. ^{[1
]}

Wang, V. S. ^{[2
]}

Li, S. L. ^{[1
]}

机构：

[1] Ural Fed Univ, Ekaterinburg 620002, Russia

[2] North China Univ Water Resources & Elect Power, Inst Heat Power Engn, Zhengzhou 450011, Peoples R China

来源：

COLLOID JOURNAL | 2024年 / 86卷 / 01期

关键词：

liquid-metal embrittlement; reactor steel; liquid-metal coolants; finite element simulation; mean-field theory; MECHANISMS; EMBRITTLEMENT; PROPAGATION; FATIGUE; SURFACE; LEAD;

D O I：

10.1134/S1061933X23601154

中图分类号：

O64 [物理化学（理论化学）、化学物理学];

学科分类号：

070304 ; 081704 ;

摘要：

The article discusses a model of the interaction between a liquid-metal coolant (Pb, Pb55Bi(e)) and a heat exchanger material (316L steel) in an SVBR-type nuclear reactor cooling device for the case in which the effect of liquid-metal embrittlement cannot be ignored. It is assumed that a crack propagates due to the penetration of the liquid-metal coolant into intergrain boundaries. The free energy of a wetted surface is calculated using the mean-field theory within the formalism of finite element analysis. Tensile stress S (MPa) is determined for the propagation of a crack 50 mu m long from a defect in the form of a 0.15-mm scratch on the surface of the heat exchanger. The calculation is carried out for an operation temperature range of 900-1100 K, when the melt wets the steel. The values of S= 253-358 , and 210 -369 MPa have been obtained for the interaction of Pb55Bi melts and Pb with 316L steel, respectively. The calculation results mean that a heat exchanger with surface defects can be damaged due to the effect of liquid-metal embrittlement.

引用

页码：130 / 137

页数：8

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