Management of Ageing in Graphite Reactor Cores

Herausgeber: Neighbour, Gareth B

• Gebundenes Buch

Produktbeschreibung

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.

Produktdetails

• Verlag: RSC Publishing
• Seitenzahl: 299
• Erscheinungstermin: 28. März 2007
• Englisch
• Abmessung: 237mm x 168mm x 23mm
• Gewicht: 621g
• ISBN-13: 9780854043453
• ISBN-10: 0854043454
• Artikelnr.: 22957849

Autorenporträt

The Author Gareth Neighbour is a Senior Lecturer in Engineering at the University of Hull and is an accepted international authority on the phenomenon of irradiation creep in nuclear graphite. He has acted on various International Scientific Advisory Committees and was a member of the Organising Committee for the premier international carbon conference, Carbon 2006.

Inhaltsangabe

Part A - Reactor Designs & Operation: The Management of Magnox Graphite
Reactor Cores to Underwrite Continued Safe Operation; AGR Core Design,
Operation and Safety Functions; An Overview of British Energy's Core
Assessment Methodology; UK Regulatory Strategy for Management of Graphite;
Ageing in Gas-Cooled, Graphite-Moderated Reactors; Part B - Advances in the
Fundamental Knowledge of Graphite Behaviour under Irradiation: The Effects
of Thermal Annealing on the Mechanical Properties of PGA Graphite;
Development of a Model of Dimensional Change in AGR Graphites Irradiated in
Inert Environments; Relating Measurements of Mechanical Properties of
Nuclear Graphites to Reactor Conditions. A Review of the Effects of
Temperature and Pressure; Flexural Strength of Graphite; Observations of
Strain Localisation and Failure in Nuclear Graphite; Evaluation of the
Brazilian Disc Test in Fracture Strength Measurements of Nuclear Graphite;
Irradiation Damage in Graphite from First Principles; Development of a Code
to Predict Fundamental Material and Fracture Properties of Nuclear
Graphite; Modelling Graphite Ageing: Black Art or Forensic Science?; A
Holistic, Structurally Based, Approach to Modelling Graphite Properties;
X-ray Tomographic Observations Applied to Porosity; Models for the Thermal
Properties of Oxidised Nuclear Graphite; Part C - Advances in the
Understanding of Graphite-Component Behaviour and its Assessment: Crack
Propagation Resistance and Damage Mechanisms in Nuclear Graphite; Graphite
Irradiation Testing at the HFR Petten; The Development of Measurement
Techniques for Mechanical Properties Applicable to Small Reactor Graphite
Samples; Techniques for Measuring the Properties of Unirradiated and
Irradiated AGR Graphite; Material Modelling of Nuclear Graphite under
Irradiation Conditions; Predicting the Stresses and Deformations of
Irradiated Graphite Moderator Bricks; Explicit Modelling of Graphite Core
Components During a Reactor Thermal Transient; Part D - The Consequences of
Graphite Deterioration: Whole-Core Behaviour: PBMR Graphite Core Structures
Fitness for Purpose Management Strategy; Seismic Modelling of an AGR
Nuclear Reactor Core; Measurement of AGR Graphite Fuel Brick Shrinkage and
Channel Distortion; Investigation of Degradation of AGR Graphite Core
Geometry Using a Whole Core Scale Model; The Feasibility of Introducing
Core Stiffening Devices and Diverse Shutdown Systems at Hinkley Point B /
Hunterston B and Hartlepool / Heysham 1; An Integrated Architecture for
Graphite Core Data Analysis; Graphite Core Condition Monitoring Through
Intelligent Analysis of Fuel Grab Load Trace Data; Application of Whole
Core Modelling Methodology to Life Extension of AGR Reactor Graphite Cores;
Statistical Models for Bore Cracking in AGR Graphite Cores; Development and
Validation of Whole Core Modelling Methodology for AGR Graphite Cores;
Method for Determining if Control Rods and Fuel Stringer can be Inserted /
Removed from an AGR Core; Part E - Lessons Learned from Management of
Ageing Plant: Experience of Ageing Processes in Nuclear Power Reactors; The
Importance of Understanding of Basic Principles in the Management of Ageing
Plant; An Overview and Summary of the Technical Papers in Parts B, C and D;