Outgassing Behavior of Egcr Moderator Graphite

Blakely, Jeannie; Overholser, L.G.

doi:10.2172/4064541

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Gas Desorption From Graphite1

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1972

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“…Although several authors (212)(213)(214)(215)have investigated the release of gases from graphite, the most pertinent work t o HTGR technology is t h a t of Blakely and Overholser. (215) They measured the desorption of gases from a needle coke graphite which was graphitized t o 2800°C and specially fabricated f o r the Experimental Gas Cooled Reactor (EGCR).…”

Section: Gas Desorption From Graphitementioning

confidence: 99%

Graphite for helium-cooled reactors. A review

Tingey¹,

Morgan²

1972

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This review encompasses information on the manufacture of nuclear graphites, including the improved i s o t r o p i c grades, the phy sicaZ, chemical, and morpho logical differences among these materials, the theory of radiationinduced changes as influenced by morphology, and available data on radiationinduced changes i n dimensions, physical properties, and chemical r e a c t i v i t y . The review a l s o includes information on neutron dosimetry, carbon displacement cross sections, and the general problem of transposing data from one reactor t o m o t h e r . I n lesser d e t a i l , information on other materials, such as boron carbide, non-graphitized carbons, cmd py r o ly t i c carbon coatings, i s reviewed w i t h respect t o possible use and performance i n a HTGR.

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Section: Gas Desorption From Graphitementioning

confidence: 99%

Graphite for helium-cooled reactors. A review

Tingey¹,

Morgan²

1972

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Outgassing Behavior of Egcr Moderator Graphite

Cited by 1 publication

References 0 publications

Graphite for helium-cooled reactors. A review

Graphite for helium-cooled reactors. A review

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