Study on the Organization and Properties of Zirconium Alloy Cladding Tubes for Nuclear Power Generation

HAN Xiaorui; LIU Bo; WANG Zhigang; YU Hongsheng; MI Wenjun; ZHANG Xuewei; WANG Yunbo; PAN Shengqiang

doi:10.7512/j.issn.1001-2303.2025.06.18

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Study on the Organization and Properties of Zirconium Alloy Cladding Tubes for Nuclear Power Generation
Vol. 55, Issue 6, Pages: 132-139(2025)
Received：04 March 2025，

Revised：2025-04-28，

Published：20 June 2025
DOI： 10.7512/j.issn.1001-2303.2025.06.18
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韩晓瑞，刘博，王志刚，等.锆合金包壳管材料的组织与性能研究［J］.电焊机，2025，55（6）：132-139. DOI： 10.7512/j.issn.1001-2303.2025.06.18.

HAN Xiaorui, LIU Bo, WANG Zhigang, et al.Study on the Organization and Properties of Zirconium Alloy Cladding Tubes for Nuclear Power Generation[J].Electric Welding Machine, 2025, 55(6): 132-139. DOI： 10.7512/j.issn.1001-2303.2025.06.18.

摘要

锆合金包壳管作为关键的核用结构材料，其性能与组织结构对核反应堆的安全性及使用寿命具有重要意义。本研究通过电感耦合等离子体发射光谱仪/质谱仪、扫描电子显微镜、显微硬度计及光学三维轮廓仪等设备对进口锆合金、国产锆合金及国产新型锆合金的化学成分、组织性能及端面质量进行分析研究。结果表明：国产新型锆合金内部的Fe和Sn元素与进口锆合金及国产锆合金相比较高；三种锆合金晶粒细小均匀；第二相主要为Zr-Nb-Fe相，进口锆合金相比国产两种合金的第二相粒子分布较为均匀、细小；国产锆合金的抗拉强度和硬度与其余两种合金相比较高，断后伸长率低于其余两种合金。进口锆合金的端面粗糙度优于其余两种国产锆合金。以上研究有望为锆合金包壳管材料后续的焊缝成形质量控制、接头缺陷形成机理分析以及焊接工艺参数优化提供理论依据。

Abstract

Zirconium alloy cladding tubes

as key nuclear structural materials

are of great significance for the safety and service life of nuclear reactors due to their properties and organization. In this paper

the chemical composition

organizational properties and endface quality of imported zirconium alloys

domestic zirconium alloys and domestic new zirconium alloys are analyzed and studied by inductively coupled plasma emission spectrometer/mass spectrometer

scanning electron microscope

microhardness tester

and optical three-dimensional profilometer and other equipments. The results show that: the internal Fe and Sn elements of the new domestic zirconium alloys are higher than those of the imported zirconium alloys and domestic zirconium alloys; the grains of the three types of zirconium alloys are fine and uniform; the second phase is mainly the Zr-Nb-Fe phase

and the distribution of particles of the imported zirconium alloys compared to the domestic two types of zirconium alloys is more uniform and fine; the tensile strength and hardness of the domestic zirconium alloys are higher than the remaining two types of alloys

and the elongation at break is lower than that of the remaining two types of alloys. The tensile strength and hardness of domestic zirconium alloy are higher than the other two alloys

and the elongation after break is lower than the other two alloys. The end face roughness of imported zirconium alloys is better than that of the remaining two domestic zirconium alloys. The above study is expected to provide theoretical basis for the subsequent quality control of weld formation

analysis of joint defect formation mechanism and optimization of welding process parameters for zirconium alloy casing pipe materials.

关键词

Keywords

references

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