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    Overview of Nuclear Piping Seismic Verification

    Source: Journal of Pressure Vessel Technology:;2022:;volume( 144 ):;issue: 003::page 31903-1
    Author:
    Abe
    ,
    Hiroshi;Chokshi
    ,
    Nilesh
    DOI: 10.1115/1.4053831
    Publisher: The American Society of Mechanical Engineers (ASME)
    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 U.S. A relatively less active period followed in U.S. in 1990s followed by resurgence of interest and activities in 2000s. Currently, some countries are focusing on advanced reactor technology and smaller modular reactors instead of large light water reactors. Along with the transition in the need for power and technological advances, one other major change has occurred. Most of the workforce that participated in development, design, research, construction, and operation of currently operating plants is no longer active. 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 professionals 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 1981–2004 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 piping tests conducted in Japan at the era. 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 U.S. 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.
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      Overview of Nuclear Piping Seismic Verification

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    contributor authorAbe
    contributor authorHiroshi;Chokshi
    contributor authorNilesh
    date accessioned2022-08-18T13:04:46Z
    date available2022-08-18T13:04:46Z
    date copyright3/24/2022 12:00:00 AM
    date issued2022
    identifier issn0094-9930
    identifier otherpvt_144_03_031903.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4287395
    description abstractNuclear power has gone through several transitional phases worldwide with early development, design, and construction in 1960s, 1970s, and 1980s, particularly in Japan and U.S. A relatively less active period followed in U.S. in 1990s followed by resurgence of interest and activities in 2000s. Currently, some countries are focusing on advanced reactor technology and smaller modular reactors instead of large light water reactors. Along with the transition in the need for power and technological advances, one other major change has occurred. Most of the workforce that participated in development, design, research, construction, and operation of currently operating plants is no longer active. 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 professionals 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 1981–2004 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 piping tests conducted in Japan at the era. 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 U.S. 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.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleOverview of Nuclear Piping Seismic Verification
    typeJournal Paper
    journal volume144
    journal issue3
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4053831
    journal fristpage31903-1
    journal lastpage31903-12
    page12
    treeJournal of Pressure Vessel Technology:;2022:;volume( 144 ):;issue: 003
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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