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    The History of Allowable Damping Values for U.S. Nuclear Plant Piping

    Source: Journal of Pressure Vessel Technology:;1991:;volume( 113 ):;issue: 002::page 284
    Author:
    A. G. Ware
    DOI: 10.1115/1.2928756
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Prior to 1982, pipe damping values in nuclear plants were prescribed by Regulatory Guide 1.61 and Appendix N to Section III of the ASME Boiler and Pressure Vessel Code. In the early 1980s, it became clear that piping design was too conservative resulting in systems that had far too many supports, particularly snubbers. These supports were costly to design, install, and inspect; contributed to increased worker radiation exposure; and since snubbers sometimes lock when unloaded causing higher fatigue usage in piping, the safety margin of the systems was reduced. A series of steps was undertaken by the Pressure Vessel Research Committee (PVRC) to propose new damping limits, which culminated in alternate damping allowable values, called PVRC damping. This damping was later adopted as Code Case N-411 to the ASME Code. Code Case N-411 has enabled several utilities to make significant reductions in the number of snubbers on their plants, resulting in lower maintenance costs, lower worker radiation exposure, and greater reliability (since the consequences of snubber malfunction are reduced). More recently, the Electric Power Research Institute sponsored a project by Bechtel to review the damping data, perform a regression analysis, and recommend a permanent change to the ASME Code to replace Code Case N-411.
    keyword(s): Damping , Pipes , Nuclear power stations , ASME Standards , Radiation (Physics) , Safety , Public utilities , Reliability , Pressure vessels , Fatigue , Electricity (Physics) , Locks (Waterways) , Maintenance , Regression analysis , Piping design , ASME Boiler and Pressure Vessel Code , Industrial plants AND Design ,
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      The History of Allowable Damping Values for U.S. Nuclear Plant Piping

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    https://yetl.yabesh.ir/yetl1/handle/yetl/109075
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    contributor authorA. G. Ware
    date accessioned2017-05-08T23:36:25Z
    date available2017-05-08T23:36:25Z
    date copyrightMay, 1991
    date issued1991
    identifier issn0094-9930
    identifier otherJPVTAS-28326#284_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/109075
    description abstractPrior to 1982, pipe damping values in nuclear plants were prescribed by Regulatory Guide 1.61 and Appendix N to Section III of the ASME Boiler and Pressure Vessel Code. In the early 1980s, it became clear that piping design was too conservative resulting in systems that had far too many supports, particularly snubbers. These supports were costly to design, install, and inspect; contributed to increased worker radiation exposure; and since snubbers sometimes lock when unloaded causing higher fatigue usage in piping, the safety margin of the systems was reduced. A series of steps was undertaken by the Pressure Vessel Research Committee (PVRC) to propose new damping limits, which culminated in alternate damping allowable values, called PVRC damping. This damping was later adopted as Code Case N-411 to the ASME Code. Code Case N-411 has enabled several utilities to make significant reductions in the number of snubbers on their plants, resulting in lower maintenance costs, lower worker radiation exposure, and greater reliability (since the consequences of snubber malfunction are reduced). More recently, the Electric Power Research Institute sponsored a project by Bechtel to review the damping data, perform a regression analysis, and recommend a permanent change to the ASME Code to replace Code Case N-411.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleThe History of Allowable Damping Values for U.S. Nuclear Plant Piping
    typeJournal Paper
    journal volume113
    journal issue2
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2928756
    journal fristpage284
    journal lastpage290
    identifier eissn1528-8978
    keywordsDamping
    keywordsPipes
    keywordsNuclear power stations
    keywordsASME Standards
    keywordsRadiation (Physics)
    keywordsSafety
    keywordsPublic utilities
    keywordsReliability
    keywordsPressure vessels
    keywordsFatigue
    keywordsElectricity (Physics)
    keywordsLocks (Waterways)
    keywordsMaintenance
    keywordsRegression analysis
    keywordsPiping design
    keywordsASME Boiler and Pressure Vessel Code
    keywordsIndustrial plants AND Design
    treeJournal of Pressure Vessel Technology:;1991:;volume( 113 ):;issue: 002
    contenttypeFulltext
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