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contributor authorTracy L. Albers
date accessioned2017-05-09T00:32:30Z
date available2017-05-09T00:32:30Z
date copyrightNovember, 2009
date issued2009
identifier issn1528-8919
identifier otherJETPEZ-27086#064501_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/140400
description abstractThe unique combination of physical properties inherent to graphite makes it an attractive material for use as a moderator in high-temperature nuclear reactors. High-temperature physical properties of three nuclear-grade graphites manufactured by GrafTech International Holdings Inc. (GrafTech, Parma, OH), PCEA™, PCIB-SFG™, and PPEA™, have been determined experimentally and are presented here. Tensile strength, Young’s modulus, thermal conductivity, specific resistance, and coefficient of thermal expansion (CTE) data are collected at temperatures from 25°C to as high as 2000°C, and are found to be consistent with classical graphite behavior.
publisherThe American Society of Mechanical Engineers (ASME)
titleHigh-Temperature Properties of Nuclear Graphite
typeJournal Paper
journal volume131
journal issue6
journal titleJournal of Engineering for Gas Turbines and Power
identifier doi10.1115/1.3093995
journal fristpage64501
identifier eissn0742-4795
keywordsTemperature
keywordsGraphite
keywordsHigh temperature
keywordsTensile strength
keywordsElectrical resistance AND Elasticity
treeJournal of Engineering for Gas Turbines and Power:;2009:;volume( 131 ):;issue: 006
contenttypeFulltext


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