VVER-440反应堆容器运行45年后未辐照焊缝金属的研究

IF 0.5 Q4 MATERIALS SCIENCE, MULTIDISCIPLINARY
K. I. Medvedev, D. Yu. Erak, A. A. Chernobaeva, D. A. Zhurko, V. N. Kochkin, M. A. Skundin, S. A. Bubyakin, N. V. Pal, A. A. Reshetnikov
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引用次数: 0

摘要

摘要给出了VVER-440反应堆压力容器(RPV)运行45年后未辐照焊接接头切割金属试样的力学特性和化学成分的研究结果。根据初始性能、磷、铜含量和快中子通量密度随接头厚度的分布,计算得到了VVER-440反应堆压力容器(140 mm)辐照接头韧脆转变温度随接头厚度的分布。由于VVER-440 RPV中连接壳体的所有圆形焊缝均采用相同的工艺,因此研究未辐照焊缝的结果可用于评估辐照焊缝中的性能分布。同时,假定270℃(未辐照焊缝的工作温度)的热时效影响不显著,可以忽略。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Study of the Unirradiated Weld Metal of the VVER-440 Reactor Vessel after 45 Years of Operation

Study of the Unirradiated Weld Metal of the VVER-440 Reactor Vessel after 45 Years of Operation

Abstract—The results of studying the mechanical characteristics and chemical composition of metal specimens cut from an unirradiated weld joint of a VVER-440 reactor pressure vessel (RPV) after 45 years of operation are given. The calculated distribution of the ductile-to-brittle transition temperature over the thickness of the irradiated weld joint of the VVER-440 reactor pressure vessel (140 mm) is obtained accounting for the distribution of the initial properties, the content of phosphorus and copper, and the density of the fast neutron flux over the thickness of the joint. Since all the circular welds connecting the shells in the VVER-440 RPV are made using the same technology, the results of studying the unirradiated weld can be used to assess the distribution of properties in the irradiated weld. At the same time, it is assumed that the effect of thermal aging at a temperature of 270°C (operating temperature of a unirradiated weld) is insignificant and can be neglected.

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来源期刊
Inorganic Materials: Applied Research
Inorganic Materials: Applied Research Engineering-Engineering (all)
CiteScore
0.90
自引率
0.00%
发文量
199
期刊介绍: Inorganic Materials: Applied Research  contains translations of research articles devoted to applied aspects of inorganic materials. Best articles are selected from four Russian periodicals: Materialovedenie, Perspektivnye Materialy, Fizika i Khimiya Obrabotki Materialov, and Voprosy Materialovedeniya  and translated into English. The journal reports recent achievements in materials science: physical and chemical bases of materials science; effects of synergism in composite materials; computer simulations; creation of new materials (including carbon-based materials and ceramics, semiconductors, superconductors, composite materials, polymers, materials for nuclear engineering, materials for aircraft and space engineering, materials for quantum electronics, materials for electronics and optoelectronics, materials for nuclear and thermonuclear power engineering, radiation-hardened materials, materials for use in medicine, etc.); analytical techniques; structure–property relationships; nanostructures and nanotechnologies; advanced technologies; use of hydrogen in structural materials; and economic and environmental issues. The journal also considers engineering issues of materials processing with plasma, high-gradient crystallization, laser technology, and ultrasonic technology. Currently the journal does not accept direct submissions, but submissions to one of the source journals is possible.
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