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    U.S. High Fluence Power Reactor Surveillance Data—Past and Future

    Source: Journal of Pressure Vessel Technology:;2014:;volume( 136 ):;issue: 002::page 21603
    Author:
    Server, William L.
    ,
    Hardin, Timothy C.
    ,
    Brian Hall, J.
    ,
    Nanstad, Randy K.
    DOI: 10.1115/1.4026149
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Enhanced radiation embrittlement at high fluence, indicative of extended operating life beyond 60 years for current operating pressurized water reactor (PWR) vessels, has been identified as a potential limiting degradation mechanism. Currently, there are limited U.S. power reactor surveillance data available at fluences greater than 4 أ— 1019 n/cm2 (E > 1 MeV) for comparison with existing embrittlement prediction models. Additional data will be required to support extended operations to 80+ years, where some plants are projected to have peak vessel fluences approaching 1 أ— 1020 n/cm2. A number of programs are designed to contribute to the high fluence surveillance data to support extended operating life. The U.S programs include the Coordinated PWR Reactor Vessel Surveillance Program (CRVSP), the PWR Supplemental Surveillance Program (PSSP), and the Light Water Reactor Sustainability (LWRS) Program. The LWRS Program involves generation of high fluence test reactor data on many different reactor pressure vessel steels and model alloys, including some of the same PWR vessel materials irradiated to higher fluences in conventional power reactor surveillance programs. This paper surveys the existing high fluence data and the data projected to come from the above listed programs to show when such data will become available. The data will be used to validate or revise embrittlement trend correlations applicable for the high fluence regime. Mechanical property data are being developed, and finescale microstructure data are being produced using stateoftheart methods.
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      U.S. High Fluence Power Reactor Surveillance Data—Past and Future

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    contributor authorServer, William L.
    contributor authorHardin, Timothy C.
    contributor authorBrian Hall, J.
    contributor authorNanstad, Randy K.
    date accessioned2017-05-09T01:11:56Z
    date available2017-05-09T01:11:56Z
    date issued2014
    identifier issn0094-9930
    identifier otherpvt_136_02_021603.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/156127
    description abstractEnhanced radiation embrittlement at high fluence, indicative of extended operating life beyond 60 years for current operating pressurized water reactor (PWR) vessels, has been identified as a potential limiting degradation mechanism. Currently, there are limited U.S. power reactor surveillance data available at fluences greater than 4 أ— 1019 n/cm2 (E > 1 MeV) for comparison with existing embrittlement prediction models. Additional data will be required to support extended operations to 80+ years, where some plants are projected to have peak vessel fluences approaching 1 أ— 1020 n/cm2. A number of programs are designed to contribute to the high fluence surveillance data to support extended operating life. The U.S programs include the Coordinated PWR Reactor Vessel Surveillance Program (CRVSP), the PWR Supplemental Surveillance Program (PSSP), and the Light Water Reactor Sustainability (LWRS) Program. The LWRS Program involves generation of high fluence test reactor data on many different reactor pressure vessel steels and model alloys, including some of the same PWR vessel materials irradiated to higher fluences in conventional power reactor surveillance programs. This paper surveys the existing high fluence data and the data projected to come from the above listed programs to show when such data will become available. The data will be used to validate or revise embrittlement trend correlations applicable for the high fluence regime. Mechanical property data are being developed, and finescale microstructure data are being produced using stateoftheart methods.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleU.S. High Fluence Power Reactor Surveillance Data—Past and Future
    typeJournal Paper
    journal volume136
    journal issue2
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4026149
    journal fristpage21603
    journal lastpage21603
    identifier eissn1528-8978
    treeJournal of Pressure Vessel Technology:;2014:;volume( 136 ):;issue: 002
    contenttypeFulltext
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    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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