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contributor authorRen, Weiju
contributor authorSwindeman, Robert
date accessioned2017-05-09T01:12:08Z
date available2017-05-09T01:12:08Z
date issued2014
identifier issn0094-9930
identifier otherpvt_136_05_054001.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/156195
description abstractAlloy 800 H is currently under consideration for applications in the next generation nuclear plant (NGNP) at operational temperatures above 750 آ°C. This paper first describes service requirements of the nuclear system for structural materials; and then an extensive review of Alloy 800 H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application. Finally, further research and development activities to support the materials qualification are suggested.
publisherThe American Society of Mechanical Engineers (ASME)
titleStatus of Alloy 800 H in Considerations for the Gen IV Nuclear Energy Systems
typeJournal Paper
journal volume136
journal issue5
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.4025093
journal fristpage54001
journal lastpage54001
identifier eissn1528-8978
treeJournal of Pressure Vessel Technology:;2014:;volume( 136 ):;issue: 005
contenttypeFulltext


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