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    Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel

    Source: Journal of Pressure Vessel Technology:;2020:;volume( 143 ):;issue: 003::page 031704-1
    Author:
    Lu, Kai
    ,
    Katsuyama, Jinya
    ,
    Masaki, Koichi
    ,
    Watanabe, Tadashi
    ,
    Li, Yinsheng
    DOI: 10.1115/1.4049048
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Structural integrity assessment of reactor pressure vessel (RPV) is important for the safe operation of nuclear power plant. For an RPV in a pressurized water reactor (PWR), pressurized thermal shock (PTS) resulted from rapid coolant water injection due to a loss-of-coolant accident is an issue of particular concern. The coolant water temperature in the emergency core cooling system (ECCS) can influence the integrity of RPV subjected to PTS events; thus, this paper is focused on investigating the effect of coolant water temperature of ECCS on failure probability of an RPV. First, thermal-hydraulic (TH) analyses were conducted for a Japanese PWR model plant by using RELAP5, and different coolant water temperatures in ECCS were considered to investigate the effect of coolant water temperature on TH behaviors during a PTS event. Using the TH analysis results, probabilistic fracture mechanics (PFM) analyses were performed for the RPV of the Japanese model plant. Based on the PFM analysis results, the effect of coolant water temperature on failure probability of the RPV was quantified.
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      Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4276661
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    contributor authorLu, Kai
    contributor authorKatsuyama, Jinya
    contributor authorMasaki, Koichi
    contributor authorWatanabe, Tadashi
    contributor authorLi, Yinsheng
    date accessioned2022-02-05T21:58:09Z
    date available2022-02-05T21:58:09Z
    date copyright11/18/2020 12:00:00 AM
    date issued2020
    identifier issn0094-9930
    identifier otherpvt_143_03_031704.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4276661
    description abstractStructural integrity assessment of reactor pressure vessel (RPV) is important for the safe operation of nuclear power plant. For an RPV in a pressurized water reactor (PWR), pressurized thermal shock (PTS) resulted from rapid coolant water injection due to a loss-of-coolant accident is an issue of particular concern. The coolant water temperature in the emergency core cooling system (ECCS) can influence the integrity of RPV subjected to PTS events; thus, this paper is focused on investigating the effect of coolant water temperature of ECCS on failure probability of an RPV. First, thermal-hydraulic (TH) analyses were conducted for a Japanese PWR model plant by using RELAP5, and different coolant water temperatures in ECCS were considered to investigate the effect of coolant water temperature on TH behaviors during a PTS event. Using the TH analysis results, probabilistic fracture mechanics (PFM) analyses were performed for the RPV of the Japanese model plant. Based on the PFM analysis results, the effect of coolant water temperature on failure probability of the RPV was quantified.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleEffect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel
    typeJournal Paper
    journal volume143
    journal issue3
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4049048
    journal fristpage031704-1
    journal lastpage031704-8
    page8
    treeJournal of Pressure Vessel Technology:;2020:;volume( 143 ):;issue: 003
    contenttypeFulltext
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