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contributor authorD. Moulin
contributor authorB. Drubay
contributor authorD. Acker
contributor authorL. Laiarinandrasana
date accessioned2017-05-08T23:48:07Z
date available2017-05-08T23:48:07Z
date copyrightNovember, 1995
date issued1995
identifier issn0094-9930
identifier otherJPVTAS-28363#335_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/115826
description abstractThe behavior of defects like cracks in nuclear components operating at high temperature, where creep is significant, must be under control. There exists the need to have a practical method of analysis, which can be used by engineers, to calculate the time of initiation for defects existing at the start of life of nuclear components. This study presents the background, the development, the application, and results concerning validation work made for a simplified method named σd of prediction of initiation for nuclear structures made of 316L austenitic steel and operating at temperature where creep is significant. This method relies on the evaluation of real stress-strain history on a small distance d (d = 0.05 mm) close to the crack front and material characteristics (limiting stresses) that are available in nuclear codes like ASME Code cases or RCC-MR.
publisherThe American Society of Mechanical Engineers (ASME)
titleA Practical Method Based on Stress Evaluation (σd Criterion) to Predict Initiation of Crack Under Creep and Creep-Fatigue Conditions
typeJournal Paper
journal volume117
journal issue4
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.2842132
journal fristpage335
journal lastpage340
identifier eissn1528-8978
keywordsCreep
keywordsFatigue
keywordsStress
keywordsFracture (Materials)
keywordsProduct quality
keywordsHigh temperature
keywordsASME Standards
keywordsTemperature
keywordsSteel AND Engineers
treeJournal of Pressure Vessel Technology:;1995:;volume( 117 ):;issue: 004
contenttypeFulltext


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