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Materials and Water Chemistry for Supercritical Water-cooled Reactors

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Materials and Water Chemistry for Supercritical Water-cooled Reactors

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Contents

Acknowledgements

List of abbreviations

1 - Introduction

1.1 Early efforts

1.2 Recent developments

1.2.1 Synergies

1.3 Supercritical water-cooled reactor materials requirements

1.3.1 Candidate materials

1.4 Summary

References

2 - Experimental methodologies

2.1 Test facilities for corrosion and environmentally assisted cracking studies

2.2 Test specimens

2.2.1 Galvanic effects

2.3 Corrosion rate measurements

2.3.1 Surface finish

2.3.2 Weight gain versus weight loss

2.3.2.1 Reproducibility

2.3.3 Electrochemical methods

2.3.4 Other in situ analyses

2.4 Measurements of thermodynamic properties

2.5 Stress corrosion cracking

2.6 Testing under irradiated conditions

2.6.1 Materials testing

2.6.2 Water radiolysis studies

References

3 - Radiation effects and mechanical properties

3.1 Primary radiation damage

3.2 Effects on mechanical properties

3.2.1 Hardening

3.2.2 Ductility

3.2.3 Irradiation-assisted stress corrosion cracking

3.2.4 Void swelling

3.3 Effects on microchemistry: radiation-induced segregation

3.4 Creep

3.4.1 Introduction

3.4.2 Predicting creep

3.4.3 Irradiation-assisted creep

3.5 Microstructural instability

3.5.1 Microstructural instability due to high temperature exposure

3.5.2 Formation of precipitates due to radiation exposure

3.6 Modelling

References

4 - Water chemistry

4.1 Introduction

4.1.1 What is supercritical water?

4.2 Feedwater chemistry

4.2.1 Transport of corrosion products and other impurities

4.2.2 Transport of other impurities to the core

4.3 Activity transport

4.3.1 Activation of in-core materials

4.3.2 Defected fuel in a supercritical water-cooled reactor

4.3.2.1 Plant experience and experimental data

Noble gases and iodines

Fuel leaching tests

4.4 Water radiolysis

4.4.1 Approaches to modelling

4.4.1.1 Microscopic models

4.4.1.2 Semiempirical modelling

4.4.1.3 Large-scale loop or in-reactor studies

4.5 Chemistry control in a supercritical water-cooled reactor

4.6 Molecular dynamics simulations

References

5 - Corrosion

5.1 Introduction

5.1.1 Performance criteria

5.2 Alloy composition

5.2.1 Zr-based alloys

5.2.2 Ti-based alloys

5.3 Effects of key parameters

5.3.1 Temperature

5.3.2 Surface finish and grain size

5.3.3 Water chemistry

5.3.3.1 pH

5.3.3.2 Dissolved oxygen

5.3.3.3 Supercritical water pressure/density

Near-critical region

High T region

5.3.4 Flow rate

5.3.5 Heat transfer

5.3.6 Ageing

5.3.7 Irradiation

5.4 Oxide morphology

5.4.1 Ferritic–martensitic steels

5.4.2 Austenitic steels

5.4.3 Ni-based alloys

5.4.4 Coatings

5.5 Oxide growth kinetics

5.6 Mechanisms and modelling

5.6.1 Empirical and phenomenological models

5.6.2 Deterministic models

References

6 - Environmentally assisted cracking

6.1 Introduction

6.2 Effects of key variables

6.2.1 Environmental factors

6.2.1.1 Temperature

6.2.1.1.1 Near-critical region – the effect of supercritical water density

6.2.1.1.2 High Temperature Behaviour

6.2.1.2 Water chemistry

6.2.2 Material factors

6.2.3 Mechanical factors

6.2.3.1 Irradiation factors

6.3 Mechanisms and modelling

References

Index

A

B

C

D

E

F

G

H

I

J

L

M

N

O

P

R

S

T

U

V

W

Y

Z

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