The development of a stress analysis code for nuclear graphite components in gas-cooled reactors

D. K L Tsang; B. J. Marsden

doi:10.1016/j.jnucmat.2006.01.015

The development of a stress analysis code for nuclear graphite components in gas-cooled reactors

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Abstract

Most of the UK nuclear power reactors are gas-cooled and graphite moderated. As well as acting as a moderator the graphite also acts as a structural component providing channels for the coolant gas and control rods. For this reason the structural integrity assessments of nuclear graphite components is an essential element of reactor design. In order to perform graphite component stress analysis, the definition of the constitutive equation relating stress and strain for irradiated graphite is required. Apart from the usual elastic and thermal strains, irradiated graphite components are subject to additional strains due to fast neutron irradiation and radiolytic oxidation. In this paper a material model for nuclear graphite is presented along with an example of a stress analysis of a nuclear graphite moderator brick subject to both fast neutron irradiation and radiolytic oxidation. © 2006 Elsevier B.V. All rights reserved.

Original language	English
Pages (from-to)	208-220
Number of pages	12
Journal	Journal of Nuclear Materials
Volume	350
Issue number	3
DOIs	https://doi.org/10.1016/j.jnucmat.2006.01.015
Publication status	Published - 1 May 2006

Keywords

C0100
M0200
M0300

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10.1016/j.jnucmat.2006.01.015

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abstract = "Most of the UK nuclear power reactors are gas-cooled and graphite moderated. As well as acting as a moderator the graphite also acts as a structural component providing channels for the coolant gas and control rods. For this reason the structural integrity assessments of nuclear graphite components is an essential element of reactor design. In order to perform graphite component stress analysis, the definition of the constitutive equation relating stress and strain for irradiated graphite is required. Apart from the usual elastic and thermal strains, irradiated graphite components are subject to additional strains due to fast neutron irradiation and radiolytic oxidation. In this paper a material model for nuclear graphite is presented along with an example of a stress analysis of a nuclear graphite moderator brick subject to both fast neutron irradiation and radiolytic oxidation. {\textcopyright} 2006 Elsevier B.V. All rights reserved.",

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AB - Most of the UK nuclear power reactors are gas-cooled and graphite moderated. As well as acting as a moderator the graphite also acts as a structural component providing channels for the coolant gas and control rods. For this reason the structural integrity assessments of nuclear graphite components is an essential element of reactor design. In order to perform graphite component stress analysis, the definition of the constitutive equation relating stress and strain for irradiated graphite is required. Apart from the usual elastic and thermal strains, irradiated graphite components are subject to additional strains due to fast neutron irradiation and radiolytic oxidation. In this paper a material model for nuclear graphite is presented along with an example of a stress analysis of a nuclear graphite moderator brick subject to both fast neutron irradiation and radiolytic oxidation. © 2006 Elsevier B.V. All rights reserved.

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The development of a stress analysis code for nuclear graphite components in gas-cooled reactors

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