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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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