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

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4.11 Graphite in Gas-Cooled Reactors

Marsden, B J; Hall, G N

Reference Module in Materials Science and Materials Engineering. 2015;.

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Full-text held externally

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

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.

Keyword(s)

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

Bibliographic metadata

Type of resource:

text

Content type:

Journal article

Publication status:

Published

Publication type:

Original research

Publication form:

Academic journal article

Author(s):

Published date:

2015-10-06

Article title:

4.11 Graphite in Gas-Cooled Reactors

Journal title:

Reference Module in Materials Science and Materials Engineering

Digital Object Identifier:

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

Attached files embargo period:

Immediate release

Attached files release date:

9th December, 2015

Access state:

Active

Institutional metadata

University researcher(s):

Marsden, Barry

Academic department(s):

Record metadata

Manchester eScholar ID:

uk-ac-man-scw:283021

Created by:

Bentley, Hazel

Created:

9th December, 2015, 14:25:45

Last modified by:

Bentley, Hazel

Last modified:

10th December, 2015, 10:31:50