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contributor authorA. Cowan
contributor authorR. W. Nichols
date accessioned2017-05-08T23:19:21Z
date available2017-05-08T23:19:21Z
date copyrightOctober, 1964
date issued1964
identifier issn1528-8919
identifier otherJETPEZ-26638#393_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/99313
description abstractSome of the materials problems associated with the use of mild steels in large gas-cooled reactor pressure vessels are discussed. Tests to failure of 5-ft-dia 0.36 percent carbon-steel vessels with through-thickness longitudinal slots, supported by tests on 7-ft-wide centrally slotted flat plates, have indicated that rapid failure at working-stress levels can only initiate from very long cracks, feet rather than inches in length. Of the mechanisms whereby realistic defects can grow to these sizes, brittle-crack propagation is considered the most important and this can be prevented by the maintenance of a minimum pressurization temperature, based on the crack-arrest temperature. The tests used to assess the crack arrest temperature of plates up to 4 in. thick are described; compared with tests on thinner specimens the thick plate gives arrest temperatures higher by approximately 10 deg C per in. of test-specimen thickness. A comparison is made of crack-arrest temperature and data given by small-scale tests, particularly the Charpy V-notch test. Mechanical limitations of creep deformation in some current designs have been more restrictive on design stress than the values allowed by the existing BS.1500. The test data quoted for stress-rupture and fatigue indicate that these modes of crack extension are not important in current designs. Possible magnitudes and effects of stress concentrations are quoted but, other than a large body of satisfactory service operation, there is little direct evidence of the effect of operating in the creep range on these stress concentrations. The importance of work of this type in justifying higher design stresses and more economic use of material is emphasized.
publisherThe American Society of Mechanical Engineers (ASME)
titleAssessment of Steels for Nuclear Reactor Pressure Vessels
typeJournal Paper
journal volume86
journal issue4
journal titleJournal of Engineering for Gas Turbines and Power
identifier doi10.1115/1.3677619
journal fristpage393
journal lastpage401
identifier eissn0742-4795
keywordsSteel
keywordsPressure vessels
keywordsNuclear reactors
keywordsStress
keywordsFracture (Materials)
keywordsTemperature
keywordsFailure
keywordsDesign
keywordsCreep
keywordsThickness
keywordsVessels
keywordsMechanisms
keywordsFatigue
keywordsBrittleness
keywordsCarbon steel
keywordsMaintenance
keywordsProduct quality
keywordsGas cooled reactors
keywordsPlates (structures)
keywordsFlat plates AND Rupture
treeJournal of Engineering for Gas Turbines and Power:;1964:;volume( 086 ):;issue: 004
contenttypeFulltext


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