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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.

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

Management of Ageing Processes in Graphite Reactor Cores

0854043454

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