Understanding fracture behaviour of PGA reactor core graphite: perspective

R Moskovic; Peter E J Flewitt; E Schlangen; G Smith; AG Crocker; A Hodgkins; Peter J Heard; MR Wootton

doi:10.1179/1743284713Y.0000000354

Understanding fracture behaviour of PGA reactor core graphite: perspective

R Moskovic, Peter E J Flewitt, E Schlangen, G Smith, AG Crocker, A Hodgkins, Peter J Heard, MR Wootton

Research output: Contribution to journal › Article (Academic Journal) › peer-review

Abstract

Magnox reactors are cooled by carbon dioxide gas. The pile grade A (PGA) graphite moderator bricks in the reactor core loose mass and become more porous during service due to the radiolytic oxidation caused by energy deposition, mainly gamma radiation. In addition, neutron irradiation brings about strengthening by irradiation hardening and dimensional change. In this perspective, experimental data related to the attendant microstructural changes and the associated initiation and propagation of cracks within the graphite are revisited. These results are compared with the predictions of multiscale finite element modelling based upon an idealised microstructure. The discussion considers the quasi-brittle characteristics of the PGA graphite over a range of service exposure conditions.

Original language	English
Pages (from-to)	129-145
Number of pages	17
Journal	Materials Science and Technology
Volume	30
Issue number	2
DOIs	https://doi.org/10.1179/1743284713Y.0000000354
Publication status	Published - Feb 2014

Keywords

PGA graphite
Microstructure
Neutron Irradiation
Strength
Quasi-brittle fracture

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QUBE:- QUasi-Brittle fracture: a 3D Experimentally-validated approach
Flewitt, P. E. J. (Principal Investigator)
1/10/12 → 1/04/16
Project: Research

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title = "Understanding fracture behaviour of PGA reactor core graphite: perspective",

abstract = "Magnox reactors are cooled by carbon dioxide gas. The pile grade A (PGA) graphite moderator bricks in the reactor core loose mass and become more porous during service due to the radiolytic oxidation caused by energy deposition, mainly gamma radiation. In addition, neutron irradiation brings about strengthening by irradiation hardening and dimensional change. In this perspective, experimental data related to the attendant microstructural changes and the associated initiation and propagation of cracks within the graphite are revisited. These results are compared with the predictions of multiscale finite element modelling based upon an idealised microstructure. The discussion considers the quasi-brittle characteristics of the PGA graphite over a range of service exposure conditions.",

keywords = " PGA graphite, Microstructure, Neutron Irradiation, Strength, Quasi-brittle fracture",

author = "R Moskovic and Flewitt, {Peter E J} and E Schlangen and G Smith and AG Crocker and A Hodgkins and Heard, {Peter J} and MR Wootton",

year = "2014",

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doi = "10.1179/1743284713Y.0000000354",

language = "English",

volume = "30",

pages = "129--145",

journal = "Materials Science and Technology",

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TY - JOUR

T1 - Understanding fracture behaviour of PGA reactor core graphite: perspective

AU - Moskovic, R

AU - Flewitt, Peter E J

AU - Schlangen, E

AU - Smith, G

AU - Crocker, AG

AU - Hodgkins, A

AU - Heard, Peter J

AU - Wootton, MR

PY - 2014/2

Y1 - 2014/2

N2 - Magnox reactors are cooled by carbon dioxide gas. The pile grade A (PGA) graphite moderator bricks in the reactor core loose mass and become more porous during service due to the radiolytic oxidation caused by energy deposition, mainly gamma radiation. In addition, neutron irradiation brings about strengthening by irradiation hardening and dimensional change. In this perspective, experimental data related to the attendant microstructural changes and the associated initiation and propagation of cracks within the graphite are revisited. These results are compared with the predictions of multiscale finite element modelling based upon an idealised microstructure. The discussion considers the quasi-brittle characteristics of the PGA graphite over a range of service exposure conditions.

AB - Magnox reactors are cooled by carbon dioxide gas. The pile grade A (PGA) graphite moderator bricks in the reactor core loose mass and become more porous during service due to the radiolytic oxidation caused by energy deposition, mainly gamma radiation. In addition, neutron irradiation brings about strengthening by irradiation hardening and dimensional change. In this perspective, experimental data related to the attendant microstructural changes and the associated initiation and propagation of cracks within the graphite are revisited. These results are compared with the predictions of multiscale finite element modelling based upon an idealised microstructure. The discussion considers the quasi-brittle characteristics of the PGA graphite over a range of service exposure conditions.

KW - PGA graphite

KW - Microstructure

KW - Neutron Irradiation

KW - Strength

KW - Quasi-brittle fracture

U2 - 10.1179/1743284713Y.0000000354

DO - 10.1179/1743284713Y.0000000354

M3 - Article (Academic Journal)

SN - 0267-0836

VL - 30

SP - 129

EP - 145

JO - Materials Science and Technology

JF - Materials Science and Technology

IS - 2

ER -

Understanding fracture behaviour of PGA reactor core graphite: perspective

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QUBE:- QUasi-Brittle fracture: a 3D Experimentally-validated approach

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