Written to assist individuals in academia and industry and in relevant regulatory and policy roles, this publication provides a summary of the current knowledge on the status of research, technological developments, reactor designs and experiments in the area of advanced reactors that are fueled or cooled by a molten salt. Identification of challenges and areas where research and development are still required in preparation for commercial deployment gives context to current and planned work. The aim of this publication is to share information on programs and projects on molten salt reactors in Member States which will shape future collaborative efforts.

• 1. INTRODUCTION
  • 1.1. Background
  • 1.2. Objective
  • 1.3. Scope
  • 1.4. Structure
• 2. HISTORY OF MSR TECHNOLOGY
  • 2.1. Development efforts in the United States of America
  • 2.2. Development efforts outside the United States of America
    • 2.2.1. Development efforts in Poland and Switzerland
    • 2.2.2. Development efforts in Germany
    • 2.2.3. Development efforts in the United Kingdom
    • 2.2.4. Development efforts in the Netherlands
    • 2.2.5. Development efforts in China
    • 2.2.6. Development efforts in Japan
    • 2.2.7. Development efforts in France
    • 2.2.8. Development efforts in the Russian Federation
• 3. ADVANTAGES AND TECHNICAL CHALLENGES OF MSR TECHNOLOGY
  • 3.1. Advantages of MSR technology
    • 3.1.1. Safety advantages
    • 3.1.2. Economic advantages
  • 3.2. Technical challenges of MSR technology
    • 3.2.1. Challenges associated with reactor physics
    • 3.2.2. Challenges associated with salt chemistry and materials science
    • 3.2.3. Challenges associated with engineering design
• 4. CLASSIFICATION OF MSR FAMILIES
  • 4.1. Introduction
  • 4.2. Neutronic characteristics of major considered nuclides
    • 4.2.1. Hydrogen and deuterium
    • 4.2.2. Lithium-6 and lithium-7
    • 4.2.3. Beryllium-9 and carbon-12
    • 4.2.4. Fluorine-19 and sodium-23
    • 4.2.5. Chlorine-35 and chlorine-37
    • 4.2.6. Graphite moderator
  • 4.3. Taxonomy of MSRs
  • 4.4. Classes and families
    • 4.4.1. Class I: Graphite based MSRs
    • 4.4.2. Class II: Homogeneous MSRs
    • 4.4.3. Class III: Heterogeneous MSRs
    • 4.4.4. Class IV: Other MSRs
  • 4.5. Family I.1: Fluoride salt cooled reactors
    • 4.5.1. Major reactor types
  • 4.6. Family I.2: Graphite moderated MSRs
    • 4.6.1. Major reactor types
  • 4.7. Family II.3: Homogeneous fluoride fast MSRs
    • 4.7.1. Major reactor types
  • 4.8. Family II.4: Homogeneous chloride fast MSRs
    • 4.8.1. Major reactor types
  • 4.9. Family III.5: Non-graphite moderated MSRs
    • 4.9.1. Major reactor types
  • 4.10. Family III.6: Heterogeneous chloride fast MSRs
    • 4.10.1. Major reactor types
  • 4.11. Other MSRs
    • 4.11.1. Major reactor types
• 5. RESEARCH AND DEVELOPMENT ACTIVITIES
  • 5.1. Introduction
  • 5.2. Research and development activities in Canada
    • 5.2.1. Background
    • 5.2.2. Research and development activities
  • 5.3. Research and development activities in China
    • 5.3.1. Progress of R&D in TMSR technology
    • 5.3.2. Design and construction of the TMSR-0 simulator reactor
    • 5.3.3. Design and construction of the TMSR-LF1 experimental reactor
  • 5.4. Research and development activities in the Czech Republic
    • 5.4.1. Reactor physics
    • 5.4.2. Fuel and coolant chemistry and supporting technology
    • 5.4.3. Performance of materials
  • 5.5. Research and development activities in Denmark
  • 5.6. Research and development activities by the European Commission
    • 5.6.1. Introduction and main achievements
    • 5.6.2. Fuel and coolant chemistry and supporting technology
    • 5.6.3. Component and technology development
  • 5.7. Research and development activities in France
    • 5.7.1. Introduction and main achievements
    • 5.7.2. Reactor physics
    • 5.7.3. System behaviour and safety evaluation
    • 5.7.4. Safety approach
    • 5.7.5. Performance of materials
  • 5.8. Research and development activities in Italy
    • 5.8.1. Activities at Politecnico di Milano
    • 5.8.2. Activities at Politecnico di Torino
  • 5.9. Research and development activities in Japan
  • 5.10. Research and development activities in the Netherlands
    • 5.10.1. Activities at the Nuclear Research and Consultancy Group
    • 5.10.2. Activities at TU Delft
  • 5.11. Research and development activities in the Russian Federation
    • 5.11.1. ISTC project number 1606 (2001–2008)
    • 5.11.2. ISTC project number 3749 (2008–2016)
  • 5.12. Research and development activities in Switzerland
    • 5.12.1. Motivation
    • 5.12.2. Major achievements
  • 5.13. Research and development activities in the United States of America
• 6. CURRENT CHALLENGES TO DEPLOYING MSRs
  • 6.1. Supply chain challenges
    • 6.1.1. Qualification of suppliers
    • 6.1.2. Infrastructure considerations
    • 6.1.3. Reactor developer and supplier engagement
  • 6.2. Fuel supply challenges
    • 6.2.1. Supply challenges for high assay low enriched uranium fuel
    • 6.2.2. Supply challenges for uranium–plutonium and transuranic fuel
    • 6.2.3. Supply challenges for thorium fuel
  • 6.3. Regulatory challenges
    • 6.3.1. Acceptance of evaluation tools by regulators
    • 6.3.2. Evaluation of accident progression
    • 6.3.3. Consensus on industry standards
  • 6.4. Fuel salt waste disposal challenges
  • 6.5. Safeguards and security challenges
    • 6.5.1. Material control and accountancy
    • 6.5.2. Security challenges unique to MSRs
  • 6.6. Maintenance and operations challenges
  • 6.7. Programme documentation challenges
  • 6.8. Summary of identified issues for MSR deployment
• 7. SUMMARY
• Appendix IHISTORY OF MSR TECHNOLOGY IN POLAND AND SWITZERLAND
• Appendix IIHISTORY OF MSR TECHNOLOGY IN CHINA
• Appendix IIIHISTORY OF MSR TECHNOLOGY IN FRANCE
• Appendix IVHISTORY OF MSR TECHNOLOGY IN THE RUSSIAN FEDERATION
• Appendix VDESCRIPTION OF MSR CONCEPTS
• REFERENCES
• ABBREVIATIONS
• CONTRIBUTORS TO DRAFTING AND REVIEW