Graphite in Gas-Cooled Reactors

B J Marsden; G N Hall

doi:10.1016/B978-0-12-803581-8.00729-3

Graphite in Gas-Cooled Reactors

B J Marsden, G N Hall

Mechanical and Aeronautical Engineering Division L5

Research output: Contribution to journal › Article › peer-review

Abstract

When graphite is used in a nuclear reactor, it will undergo dimensional and material properties changes due to the fast neutron irradiation and changes in temperature. These changes are further complicated in air and CO2-cooled reactors due to the effect of radiolytic oxidation. This chapter draws upon the unique experiences in the UK of CO2-cooled reactors and the behavior of graphite within such reactor environments. Examples of the observed changes in UK graphite grades as well as the current understanding of the mechanisms behind the changes are presented.

Original language	English
Pages (from-to)	357-421
Number of pages	65
Journal	Reference Module in Materials Science and Materials Engineering
Volume	14
DOIs	https://doi.org/10.1016/B978-0-12-803581-8.00729-3
Publication status	Published - 3 Aug 2020

Keywords

Advanced gas-cooled reactor (AGR); Dimensional change; Fast neutron irradiation; Gilsocarbon; Graphite; High-temperature reactor (HTR); Irradiation creep; Magnox; Material properties; Pile Grade A (PGA); Radiolytic oxidation

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10.1016/B978-0-12-803581-8.00729-3

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title = "Graphite in Gas-Cooled Reactors",

abstract = "When graphite is used in a nuclear reactor, it will undergo dimensional and material properties changes due to the fast neutron irradiation and changes in temperature. These changes are further complicated in air and CO2-cooled reactors due to the effect of radiolytic oxidation. This chapter draws upon the unique experiences in the UK of CO2-cooled reactors and the behavior of graphite within such reactor environments. Examples of the observed changes in UK graphite grades as well as the current understanding of the mechanisms behind the changes are presented.",

keywords = "Advanced gas-cooled reactor (AGR); Dimensional change; Fast neutron irradiation; Gilsocarbon; Graphite; High-temperature reactor (HTR); Irradiation creep; Magnox; Material properties; Pile Grade A (PGA); Radiolytic oxidation",

author = "Marsden, {B J} and Hall, {G N}",

year = "2020",

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doi = "10.1016/B978-0-12-803581-8.00729-3",

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N2 - When graphite is used in a nuclear reactor, it will undergo dimensional and material properties changes due to the fast neutron irradiation and changes in temperature. These changes are further complicated in air and CO2-cooled reactors due to the effect of radiolytic oxidation. This chapter draws upon the unique experiences in the UK of CO2-cooled reactors and the behavior of graphite within such reactor environments. Examples of the observed changes in UK graphite grades as well as the current understanding of the mechanisms behind the changes are presented.

AB - When graphite is used in a nuclear reactor, it will undergo dimensional and material properties changes due to the fast neutron irradiation and changes in temperature. These changes are further complicated in air and CO2-cooled reactors due to the effect of radiolytic oxidation. This chapter draws upon the unique experiences in the UK of CO2-cooled reactors and the behavior of graphite within such reactor environments. Examples of the observed changes in UK graphite grades as well as the current understanding of the mechanisms behind the changes are presented.

KW - Advanced gas-cooled reactor (AGR); Dimensional change; Fast neutron irradiation; Gilsocarbon; Graphite; High-temperature reactor (HTR); Irradiation creep; Magnox; Material properties; Pile Grade A (PGA); Radiolytic oxidation

U2 - 10.1016/B978-0-12-803581-8.00729-3

DO - 10.1016/B978-0-12-803581-8.00729-3

M3 - Article

VL - 14

SP - 357

EP - 421

JO - Reference Module in Materials Science and Materials Engineering

JF - Reference Module in Materials Science and Materials Engineering

ER -

Graphite in Gas-Cooled Reactors

Abstract

Keywords

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