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contributor authorWilhelm, Paul
contributor authorRudolph, Jأ¼rgen
contributor authorSteinmann, Paul
date accessioned2017-05-09T01:23:16Z
date available2017-05-09T01:23:16Z
date issued2015
identifier issn0094-9930
identifier otherpvt_137_06_061404.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/159540
description abstractA statistical model for austenitic stainless steels for predicting the effect of pressurized water reactor (PWR) environments on fatigue life for a range of temperatures and strain rates is developed based on analysis of available material data from USA, Europe, and Japan. Only fatigue data from polished specimens of wrought material tested under strain control were considered. Hollow specimens were not treated in the final calculations. The fatigue life correction factors were defined as the ratio of life in water at 300 آ°C (572 آ°F) (reference conditions) to that in water at service conditions. The model is recommended for predicting fatigue lives that are 103–105 cycles.
publisherThe American Society of Mechanical Engineers (ASME)
titleEffects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels
typeJournal Paper
journal volume137
journal issue6
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.4029832
journal fristpage61404
journal lastpage61404
identifier eissn1528-8978
treeJournal of Pressure Vessel Technology:;2015:;volume( 137 ):;issue: 006
contenttypeFulltext


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