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contributor authorCabet, Celine
contributor authorCarroll, Laura
contributor authorWright, Richard
date accessioned2017-05-09T01:02:30Z
date available2017-05-09T01:02:30Z
date issued2013
identifier issn0094-9930
identifier otherpvt_135_06_061401.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/153112
description abstractAlloy 617 is the leading candidate material for an intermediate heat exchanger (IHX) application of the very high temperature nuclear reactor (VHTR), expected to have an outlet temperature as high as 950 آ°C. Acceptance of Alloy 617 in Section III of the ASME Code for nuclear construction requires a detailed understanding of the creepfatigue behavior. Initial creepfatigue work on Alloy 617 suggests a more dominant role of environment with increasing temperature and/or hold times evidenced through changes in creepfatigue crack growth mechanisms and failure life. Continuous cycle fatigue and creepfatigue testing of Alloy 617 was conducted at 950 آ°C and 0.3% and 0.6% total strain in air to simulate damage modes expected in a VHTR application. Continuous cycle fatigue specimens exhibited transgranular cracking. Intergranular cracking was observed in the creepfatigue specimens and the addition of a hold time at peak tensile strain degraded the cycle life. This suggests that creepfatigue interaction occurs and that the environment may be partially responsible for accelerating failure.
publisherThe American Society of Mechanical Engineers (ASME)
titleLow Cycle Fatigue and Creep Fatigue Behavior of Alloy 617 at High Temperature
typeJournal Paper
journal volume135
journal issue6
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.4025080
journal fristpage61401
journal lastpage61401
identifier eissn1528-8978
treeJournal of Pressure Vessel Technology:;2013:;volume( 135 ):;issue: 006
contenttypeFulltext


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