Liquid Metal Coolants for Fast Reactors (Reactors Cooled by Sodium, Lead and Lead-bismuth Eutectic).

Format:

Book

Author/Creator:

Author), IAEA (Corporate.

Contributor:

Editor), IAEA (Corporate.

Language:

English

Subjects (All):

Fast reactors.

Liquid metal cooled reactors.

Physical Description:

1 online resource (95 pages)

Edition:

1st ed.

Other Title:

Liquid Metal Coolants for Fast Reactors

Place of Publication:

Lanham : International Atomic Energy Agency, 2012.

Summary:

The choice of the coolant is one of the main technical issues concerning fast reactors design, since it determines design approach as well as safety, technical and economic characteristics of the system. This publication provides a comprehensive summary of the status of the liquid metal coolant technology development for fast reactors, with regard to basic data and main technological challenges. It starts with historical remarks on the nuclear power development, provides a complete survey of physical and chemical properties of liquid metals and discusses the coolant quality control and thermal-hydraulics studies for both sodium and lead alloys systems. Other chapters elaborate on radioactivity of coolants and describe past experiences as well as current projects. Finally, design objectives, main research and technology development challenges of innovative fast reactor concepts, currently under investigation in Russia, having sodium, lead-bismuth eutectic, and lead as coolant, as well as the status of the respective research and development activities are summarized.

Contents:

Cover

FOREWORD

CONTENTS

1. INTRODUCTION

1.1. BACKGROUND

1.2. SCOPE AND OBJECTIVES

1.3. STRUCTURE

2. SHORT HISTORY OF NUCLEAR POWER DEVELOPMENT

3. PHYSICAL AND CHEMICAL PROPERTIES OF COOLANTS (SODIUM, LEAD AND LEAD-BISMUTH ALLOY)

3.1. LIQUID METAL DEVELOPMENT (SHORT HISTORY)

3.2. PHYSICAL PROPERTIES

3.3. CHEMICAL PROPERTIES

4. COMPARISON OF DIFFERENT SODIUM AND LEAD COOLANT TECHNOLOGIES

4.1. BACKGROUND

4.2. SODIUM TECHNOLOGY

4.3. LEAD AND LEAD-BISMUTH TECHNOLOGY

4.4. CONCLUSION

5. THERMOHYDRAULICS OF REACTOR CORE

5.1. HYDRODYNAMICS

5.2. HEAT TRANSFER

5.3. CONCLUSIONS

6. COOLANT RADIOACTIVITY

6.1. SODIUM RADIOACTIVITY

6.2. LEAD AND LEAD-BISMUTH RADIOACTIVITY

6.3. CONCLUSIONS

7. LIQUID METAL COOLED FAST REACTOR TECHNOLOGY DEVELOPMENT

7.1. INTRODUCTION

7.2. OBJECTIVES AND CHALLENGES FOR THE DEVELOPMENT OF ADVANCED LIQUID METAL COOLED FAST REACTOR

7.3. FEATURES OF LIQUID METAL COOLED FAST REACTORS

7.4. CONCLUSION

8. MODULAR LEAD-BISMUTH COOLED SMALL SIZE FAST REACTORS

8.1. INTRODUCTION

8.2. EXPERIENCE AND OPPORTUNITY TO USE LEAD-BISMUTH EUTECTIC ALLOY AS A FAST REACTORS' COOLANT

8.3. BRIEF DESCRIPTION OF EXPERIENCE WITH LEAD-BISMUTH EUTECTIC APPLICATIONS

8.4. REACTOR INSTALLATION SVBR-75/100

8.5. BASIC CONCEPTS OF THE NUCLEAR POWER PLANT BASED ON SVBR-75/100

8.6. CONCLUSIONS

9. LIQUID LEAD COOLED FAST REACTORS

9.1. THE LEAD COOLED FAST REACTOR CONCEPT

9.2. NUCLEAR FUEL CYCLE CONCEPT

9.3. BREST CONCEPT

9.4. BREST-1200

REFERENCES

ABBREVIATIONS

CONTRIBUTORS TO DRAFTING AND REVIEW.

Notes:

Description based on publisher supplied metadata and other sources.

Part of the metadata in this record was created by AI, based on the text of the resource.

ISBN:

1-5231-3009-1

1-283-98861-5

OCLC:

1027169092