On the thermal oxidation of nuclear graphite relevant to high-temperature gas cooled reactors-Reference-Cited by-同舟云学术

On the thermal oxidation of nuclear graphite relevant to high-temperature gas cooled reactors

Published:2023-01 Issue: Volume:573 Page:154103
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Paul Ryan M.,Contescu Cristian I.^ORCID,Gallego Nidia C.^ORCID,Smith Rebecca^ORCID,Bass Joseph,Kane Joshua J.^ORCID,Tzelepi Athanassia^ORCID,Metcalfe Martin

Funder

National Nuclear Laboratory

Office of Nuclear Energy

Oak Ridge National Laboratory

U.S. Department of Energy

UT-Battelle

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference106 articles.

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2. The advanced reactor technologies (ART) graphite R&D program;Windes;Nucl. Eng. Des.,2020

3. Graphite Oxidation Thermodynamics/Reactions;Propp,1998

4. Gas reactions of carbon;Walker;Adv. Catal.,1959

5. Oxidation Behavior and Property Degradation of Nuclear Graphites;Contescu,2022

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