{"title":"Overview of Nuclear Piping Seismic Verification","authors":"H. Abe, N. Chokshi","doi":"10.1115/1.4053831","DOIUrl":null,"url":null,"abstract":"\n Nuclear power has gone through several transitional phases worldwide with early development, design, and construction in 1960s,1970s, and 1980s, particularly in Japan and US. There were some major research programs conducted during those years to develop methodology and prove the technology. Much of this knowledge is still very relevant and applicable and would be useful to young engineers and new professional coming to the nuclear industry. One of such programs is seismic verification of major structures, systems, and components (SSCs) by tests in Japan during the period of 1981 through 2004 at a large shaking table facility. Opportunities for conducting such large tests are not likely in the current environment of the industry and, therefore, one of the objectives of this paper is to summarize some earlier tests to raise awareness for the newcomers to the industry.\n This paper discusses on Seismic verification tests of PWR and BWR Primary Loop, Main Steam and Feed Water line, Ultimate Strength of Piping and eroded piping , conducted in Japan. In particular, this paper focuses on: insights obtained from the test results; comparisons of test results with responses during actual earthquakes; collaboration of Japan and US in these tests; observations on robustness of Japanese seismic design; how the results relate to current issues; and use of these results from the future perspectives.","PeriodicalId":50080,"journal":{"name":"Journal of Pressure Vessel Technology-Transactions of the Asme","volume":null,"pages":null},"PeriodicalIF":1.0000,"publicationDate":"2022-02-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Pressure Vessel Technology-Transactions of the Asme","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1115/1.4053831","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"ENGINEERING, MECHANICAL","Score":null,"Total":0}
引用次数: 0
Abstract
Nuclear power has gone through several transitional phases worldwide with early development, design, and construction in 1960s,1970s, and 1980s, particularly in Japan and US. There were some major research programs conducted during those years to develop methodology and prove the technology. Much of this knowledge is still very relevant and applicable and would be useful to young engineers and new professional coming to the nuclear industry. One of such programs is seismic verification of major structures, systems, and components (SSCs) by tests in Japan during the period of 1981 through 2004 at a large shaking table facility. Opportunities for conducting such large tests are not likely in the current environment of the industry and, therefore, one of the objectives of this paper is to summarize some earlier tests to raise awareness for the newcomers to the industry.
This paper discusses on Seismic verification tests of PWR and BWR Primary Loop, Main Steam and Feed Water line, Ultimate Strength of Piping and eroded piping , conducted in Japan. In particular, this paper focuses on: insights obtained from the test results; comparisons of test results with responses during actual earthquakes; collaboration of Japan and US in these tests; observations on robustness of Japanese seismic design; how the results relate to current issues; and use of these results from the future perspectives.
期刊介绍:
The Journal of Pressure Vessel Technology is the premier publication for the highest-quality research and interpretive reports on the design, analysis, materials, fabrication, construction, inspection, operation, and failure prevention of pressure vessels, piping, pipelines, power and heating boilers, heat exchangers, reaction vessels, pumps, valves, and other pressure and temperature-bearing components, as well as the nondestructive evaluation of critical components in mechanical engineering applications. Not only does the Journal cover all topics dealing with the design and analysis of pressure vessels, piping, and components, but it also contains discussions of their related codes and standards.
Applicable pressure technology areas of interest include: Dynamic and seismic analysis; Equipment qualification; Fabrication; Welding processes and integrity; Operation of vessels and piping; Fatigue and fracture prediction; Finite and boundary element methods; Fluid-structure interaction; High pressure engineering; Elevated temperature analysis and design; Inelastic analysis; Life extension; Lifeline earthquake engineering; PVP materials and their property databases; NDE; safety and reliability; Verification and qualification of software.