Management of Ageing Processes in Graphite Reactor Cores

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  • Edition: 1st
  • Format: Hardcover
  • Copyright: 2007-08-15
  • Publisher: Royal Society of Chemistry

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Nuclear power currently contributes nearly a quarter of the electricity needs of the UK. Much of this is from nuclear reactor plants developed some fifty years ago. Consequently, in the next few decades, many of these reactors and components are coming to the end of their 'useful' life and strategies for the effective management of these decommissioned parts are paramount. Management of Ageing Processes in Graphite Reactor Cores discusses in detail both the scientific challenges and the issues involved in this subject. It begins with an introductory section on the fundamentals of reactor design and goes on to discuss graphite core behaviour under irradiation; graphite-component behaviour and its assessment; and whole core behaviour. The book concludes with a section on the lessons learned from decades of experience. Written by leading experts in the field, this high level book is ideal for both academia and industry, and would also be of relevance to policy makers and governments.

Table of Contents

The management of Magnox graphite reactor cores to underwrite continued safe operationp. 3
AGR core design, operation and safety functionsp. 11
An overview of British Energy's graphite core assessment methodologyp. 19
UK regulatory strategy for management of graphite ageing in gas-cooled, graphite-moderated reactorsp. 25
The effects of thermal annealing on the mechanical properties of PGA graphitep. 35
Development of a model of dimensional change in AGR in inert environmentsp. 43
Relating measurements of mechanical properties of nuclear graphites to reactor conditions : a review of the effects of temperature and pressurep. 51
Flexural strength of graphitep. 59
Observations of strain localisation and failure in graphite
Evaluation of the Brazilian disc test in fracture strength measurements of nuclear graphitep. 75
Irradiation damage in graphite from first principlesp. 83
Development of a code to predict fundamental material and fracture properties of nuclear graphitep. 91
Modelling gaphite ageing : black art or forensic science?p. 100
A holistic, tructurally-based approach to modelling graphite propertiesp. 108
X-ray tomographic observations applied to porosity models for properties of oxidised nuclear graphitep. 116
Crack propagation resistance and damage mechanisms in nuclear graphitep. 127
Graphite irradiation testing at the NRG Pettenp. 134
The development of techniques for mechanical properties applicable to small reactor graphite samplesp. 142
Techniques for measuring the properties of unirradiated and irradiated AGR graphitep. 150
Modelling of nuclear graphite under irradiation conditionsp. 158
Predicting the stresses and deformations of irradiated graphite moderator bricksp. 167
Explicit modelling of graphite core components during a reactor thermal transientp. 175
PBMR graphite core structures fitness for purpose management strategyp. 185
Seismic modelling of an AGR nuclear reactor corep. 193
Measurement of AGR graphite fuel brick shrinkage and channel distortionp. 201
Investigation of degradation of AGR graphite core geometry using a whole core scale modelp. 209
The feasibility of introducing core stiffening devices and diverse shutdown systems at Hinkley Point B/Hunterston B and Hartlepool/Heysham 1p. 216
An integrated architecture for graphite core data analysisp. 224
Graphite core condition monitoring through intelligent analysis of fuel grab load trace datap. 232
Application of whole core modelling methodology to life extension of AGR reactor graphite coresp. 240
A strategy for monitoring bore cracking in AGR graphite coresp. 248
Development and validation of whole core modelling methodology for AGR graphite coresp. 256
Method for determining if control rods and fuel stringer can be inserted/removed from an AGR corep. 264
Experience of ageing processes in nuclear power reactorsp. 273
The importance of understanding of basic principles in the management of ageing plantsp. 282
Table of Contents provided by Blackwell. All Rights Reserved.

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