弯曲和热处理对爆炸焊接平板型导流靶CuCrZr/ 316l界面的影响

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Siqing Feng , Xuebing Peng , Peng Liu , Wei Song , Xin Mao , Xinyuan Qian , Zhihong Liu
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引用次数: 0

摘要

铜合金在暂堵剂中的应用面临着很大的挑战。CuCrZr/ 316l复合材料爆炸焊接板在保证高效传热的同时,又保持了较高的结构强度,是常用的导流靶热沉材料。在有利于等离子体剥离的连续封闭v型导流靶结构的研制中,复合材料在结合界面弯曲至R60mm半径时可提供足够的传热性能。然而,暴露在830℃的高温下会导致弯曲区域的粘合界面泄漏。本研究通过拉伸试验、显微硬度测量、显微组织表征和元素扩散分析,对不同弯曲半径和热处理条件下爆炸焊接CuCrZr/ 316l复合材料板的结合界面进行了研究,从而找出泄漏的根本原因。结果表明,在弯曲前进行970℃的固溶体处理可诱导CuCrZr和316l的再结晶,消除了爆炸焊接引起的加工硬化。在随后的固溶体和弯曲半径为R60 mm的实验中,结合界面成功地承受了4.5 MPa的氦压力测试。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Effect of bending and thermal treatment on CuCrZr/316 L interface for flat-type divertor target by explosive welding
The application of copper alloy in divertor faces great challenges. The explosively welded CuCrZr/316 L composite plate, which maintains high structural strength while ensuring efficient heat transfer, is commonly employed as a heat sink material in divertor targets. In the development of continuous closed V-shaped structure of divertor target, which is beneficial for plasma detachment, the composite material can provide sufficient heat transfer performance when the bonding interface is bent to a radius of R60mm. However, exposure to high temperatures of 830 °C can induce leakage along the bonding interface in the bent region. This study investigates the bonding interface of explosively welded CuCrZr/316 L composite plates under different bending radii and thermal treatments through tensile tests, microhardness measurements, microstructural characterization, and elemental diffusion analysis, thereby identifying the root cause of leakage. It is found that performing a solid solution at 970 °C prior to bending induces recrystallization in both CuCrZr and 316 L, eliminating the work hardening introduced by explosive welding. In the subsequent experiments involving solid solution followed by bending to a radius of R60 mm, the bonding interface successfully withstood a helium pressure test of 4.5 MPa.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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