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
{"title":"Study of the Unirradiated Weld Metal of the VVER-440 Reactor Vessel after 45 Years of Operation","authors":"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","doi":"10.1134/S2075113322060156","DOIUrl":null,"url":null,"abstract":"<div><div><p><b>Abstract</b>—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.</p></div></div>","PeriodicalId":586,"journal":{"name":"Inorganic Materials: Applied Research","volume":"13 6","pages":"1727 - 1735"},"PeriodicalIF":0.5000,"publicationDate":"2022-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Inorganic Materials: Applied Research","FirstCategoryId":"1085","ListUrlMain":"https://link.springer.com/article/10.1134/S2075113322060156","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0
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.
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.
求助内容：
应助结果提醒方式：
京公网安备 11010802042870号
