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contributor authorF. J. Loss
contributor authorR. A. Gray
contributor authorJ. R. Hawthorne
date accessioned2017-05-08T23:07:29Z
date available2017-05-08T23:07:29Z
date copyrightNovember, 1979
date issued1979
identifier issn0094-9930
identifier otherJPVTAS-28178#298_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/92561
description abstractAn experimental investigation was conducted to characterize the benefits of warm prestress (WPS) in limiting crack extension in the wall of a nuclear vessel during a LOCA-ECCS. The present research emphasized material behavior under conditions of a small ΔT between the temperature of WPS and the failure temperature as might occur during a LOCA. The results have demonstrated that fracture will not occur during a simultaneous unloading and cooling of the crack-tip region following WPS even though the critical KIc of the virgin material is achieved. Based on a statistical analysis, it is concluded that WPS produces an “effective” elevation in KIc ; furthermore, it is suggested that this elevation will limit crack extension in the vessel wall so as to retain the coolant.
publisherThe American Society of Mechanical Engineers (ASME)
titleInvestigation of Warm Prestress for the Case of Small ΔT During a Reactor Loss-of-Coolant Accident
typeJournal Paper
journal volume101
journal issue4
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.3454637
journal fristpage298
journal lastpage304
identifier eissn1528-8978
keywordsCoolants
keywordsAccidents
keywordsTemperature
keywordsVessels
keywordsCooling
keywordsFracture (Process)
keywordsFailure AND Statistical analysis
treeJournal of Pressure Vessel Technology:;1979:;volume( 101 ):;issue: 004
contenttypeFulltext


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