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contributor authorYu. I. Zvezdin
contributor authorD. M. Shur
contributor authorA. A. Popov
date accessioned2017-05-08T23:36:23Z
date available2017-05-08T23:36:23Z
date copyrightMay, 1991
date issued1991
identifier issn0094-9930
identifier otherJPVTAS-28326#159_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/109059
description abstractThe results obtained from the experimental investigation of Cr-Ni-Mo-V and Mn-Ni-Mo-V steel service properties used in the USSR reactor building, as well as the static crack resistance KIC versus reference temperature dependence and Paris kinetic diagrams of fatigue crack growth rate in air and water of high parameters, are given.
publisherThe American Society of Mechanical Engineers (ASME)
titleService Properties of Reactor Structural Steels and Prediction of NPP Equipment Life With PWR-Type Reactors
typeJournal Paper
journal volume113
journal issue2
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.2928741
journal fristpage159
journal lastpage162
identifier eissn1528-8978
keywordsTemperature
keywordsSteel
keywordsElectrical resistance
keywordsStructural steel
keywordsFracture (Materials)
keywordsFatigue cracks
keywordsWater AND Pressurized water reactors
treeJournal of Pressure Vessel Technology:;1991:;volume( 113 ):;issue: 002
contenttypeFulltext


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