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Securing the Safe Performance of Graphite Reactor Cores

The Proceedings of the Meeting on securing the Safe Performance of Graohite Reactor cores held 24th-26th November 2008 at the University of Nottingham

¥ 23,136 (tax included)

Description

This comprehensive book provides an account of the recent advances in securing safe performance of graphite-moderated nuclear reactors both within the UK and abroad which underpin life extension whilst maintaining high levels of plant performance. These reactors rely on graphite as a moderator in the form of layers of interlocked graphite bricks which undergo complex changes when exposed over long periods to the effects of neutron irradiation and radiolytic oxidation. The book is a sequel to the successful RSC publication "Managing of Ageing Processes in Graphite Reactor Cores", but with the emphasis on the challenges for the future safe performance. It is hoped that the contributed papers will also help in the design, construction, operation and eventual decommissioning of the new generation of graphite-moderated reactors. Papers presented in the book represent contributions from the most eminent specialists in the field and reflect the UK's contribution over the past 50 years to graphite reactor technology that will remain significant for years to come, especially in the development of Generation IV designs.

The book addresses the following general topic areas:

Assessment methodologies (including the development of test methods for collection of data)
Surveillance and Test methods (including in-core methods, e.g. monitoring and inspection, and out-of-core methods, e.g. irradiation experiments in a materials test reactor)
Prediction of the performance of the graphite core (including fundamental material properties, modelling graphite component behaviour and modelling whole-core behaviour)
Plant modifications (such as diverse shut down systems)
Graphite decommissioning (including on safe disposal of the graphite core)
Regulatory requirements
Future reactor designs.

Contents

A Look into the Past- How it All Began

The Development and Application of a Protocol for the Validation of Core Component Condition Assessment Prediction Methods

Application of Whole Core Modelling Methodology with Representative Core Loading to Life Extension of AGR Graphite Cores

Assessment Methodologies for Simulation of Control Rod Movements in an Ageing Graphite Core

IMAPS  A System for Managing Graphite Core Information

On Non Smooth Contact Dynamics Methodology for the Behaviour Assessment of Discontinuous Blocky Assemblies

Two Dimensional Analysis of AGR Core using a Super-Element Technique

The Applicability of the Equivalent Temperature Concept for the Correlation of Graphite Dimensional Change Behaviour in Magnox Reactor Cores

Underwriting the Weight Loss Limit for Graphite in AGR Power Stations

BETA: A System for Automated Intelligent Analysis of Fuel Grab Load Trace Data for Graphite Core Condition Monitoring

Volumetric Inspection of Reactor Core Graphite Using Eddy Currents

A Statistical Analysis of the Mechanical Properties of PGA Graphite Samples taken from Magnox Nuclear Reactors

Understanding AGR Graphite Brick Cracking using Physical Understanding and Statistical Modelling

Development of Dynamic Young's Modulus Test Setup for Irradiated and Oxidised Graphite

Stress Measurment in Porous Graphite at Different Scale Lengths

Mechanical and Thermal Property Measurements on AGR Core Graphite Using Electronic Speckle Pattern Interferometry

Pile Grade A Graphite- Poisson's Ratio

Derivation of Dimensional Change Behaviour from Irradiated Brick Geometry

Biaxial Testing: Appropriate for Mechanical Characterisation?

The Development of a Microstructural Model to Evaluate the Irradiation Induced Property Changes in IG-110 Graphite using X-ray Tomography

A Consideration of the Effect of Radiolytic Oxidation on Fracture Behaviour of Reactor Core Graphites

Stress Concentration Factors for Magnox Moderator Graphite

Using First Principles Calculations to Estimate Thermal Properties of Graphite and its Defects

Irradiation Induced Creep in Nuclear Graphite  Present Status and Near Future Activities

Continuing Development of the Quarter Scale Core Rig to Support the Safe Performance of Graphite Reactor Cores

The Effect of Reactor Parameters on AGR Refuelling at Hinkley Point B

Twenty-First Century Solutions to the Graphite Dismantling and Radwaste Problems

Should Subjective Risk be taken into Account in the Design Process for Graphite Disposal?

The Location of Radioisotopes in British Experimental Pile Grade Zero Graphite Waste

Radioactive Gas Generation and Containment in ILW Repositories