The thermal performance of fuel matrix material in a CO2 atmosphere

Autor:	Timothy Abram, M. J S Schmidt, Joel Turner
Rok vydání:	2013
Předmět:	Thermal oxidation Nuclear and High Energy Physics Materials science Metallurgy Matrix (geology) Atmosphere Materials Science(all) Nuclear Energy and Engineering Nuclear graphite Thermal Particle General Materials Science Graphite Oxidation rate
Zdroj:	Journal of Nuclear Materials. 443(1-3):398-402
ISSN:	0022-3115
DOI:	10.1016/j.jnucmat.2013.07.012
Popis:	The thermal oxidation performance of a semi-graphitic fuel matrix-material has been compared to two grades of nuclear graphite between 600 °C and 1200 °C in flowing CO2. Fuel matrix material is used to produce compacts or pebbles containing TRISO coated particle fuel for High Temperature Reactors (HTRs). The A3-27 fuel matrix-material grade was compared to NBG-18 and Gilsocarbon nuclear graphite grades. At 1200 °C temperatures A3-27 appears to be more reactive than NBG-18, but less so than Gilsocarbon. At 600 °C the oxidation rate of A3-27 is comparable to that of NBG-18, but both are significantly higher than that of Gilsocarbon. It is concluded that the comparable thermal oxidation behaviour of graphite and fuel-matrix material suggests that operating temperatures in a CO2 cooled reactor fuelled with TRISO coated particle fuel would not need to be reduced below those considered acceptable for the use of nuclear graphite.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d85c73fc736c26eefbec1efcd2a9a243 Zobrazit plný text záznamu Full Text from ScienceDirect