Structural Materials for Heavy Liquid Metal Cooled Fast Reactors

The compatibility of structural materials, such as steels with lead and lead-bismuth eutectic, poses a critical challenge in the development of heavy liquid metal (HLM) cooled fast reactors. Factors such as the high temperatures, fast neutron flux and irradiation exposure and corrosiveness provide a...

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Detalles Bibliográficos
Clasificación:Libro Electrónico
Autor principal: IAEA
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Vienna : International Atomic Energy Agency, 2021.
Temas:
Liquid metal cooled reactors.
Nuclear reactors > Materials.
Réacteurs à réfrigérant liquide métallique.
Réacteurs nucléaires > Matériaux.
Acceso en línea:Texto completo
Tabla de Contenidos:
  • Intro
  • 1. Introduction
  • 1.1. Background
  • 1.2. Objective
  • 1.3. Scope
  • 1.4. Structure
  • 2. Summary of Meeting Sessions
  • 2.1. Session I: HLM Compatibility with Structural Materials: Phenomena, Modelling and Operational Experience
  • 2.2. Session II: Corrosion Mitigation Measures: Coating, New Structural Materials, Environmental Conditioning
  • 2.3. Session III: Qualification Programmes of Structural Materials for HLM Fast Reactors
  • 3. Summary of Group Discussions
  • 3.1. Group Discussion i: Outstanding Research Challenges
  • 3.2. Group Discusion II: New Materials and Coating Techniques
  • 3.3. Group discussion III: Industrialization
  • 4. Conclusions
  • ABBREVIATIONS
  • PAPERS PRESENTED AT THE MEETING
  • SESSION I: HLM COMPATIBILITY WITH STRUCTURAL MATERIALS: PHENOMENA, MODELLING AND OPERATIONAL EXPERIENCE
  • KINETICS AND MECHANISM OF CRACK INITIATION OF LIQUID METAL EMBRITTLEMENT
  • 1. INTRODUCTION
  • 2. EXPERIMENTAL
  • 2.1. Materials
  • 2.2. Specimens
  • 2.3. Test technique
  • 2.4. Environment
  • 2.5. Post-test evaluation
  • 3. RESULTS I
  • SENSITIVITY TO LME/EAC CRACKING IN HLM
  • 3.1. T91 & liquid LBE
  • 3.2. T91 & liquid Pb
  • 4. RESULTS II
  • CONDITIONS FOR LME/EAC CRACKING IN HLM: INITIATION
  • 4.1. T91 & liquid LBE
  • 4.2. T91 & liquid Pb
  • 4.3. Initiation of LME/EAC of T91 in HLM
  • summary
  • 4.4. 15-15Ti in liquid LBE
  • 4.5. 15-15Ti in liquid Pb
  • 5. RESULTS III
  • CONDITIONS FOR LME/EAC CRACKING IN HLM: KINETICS
  • 5.1. Fracture resistance of T91 in liquid LBE
  • 5.2. Crack Growth Rate of T91 in HLM
  • 6. Discussion
  • 7. Conclusions
  • RATEN ICN STATUS ON MECHANICAL PROPERTIES INVESTIGATION OF 316L GENERATION iv CANDIDATE MATERIAL
  • 1. INTRODUCTION
  • 2. EXPERIMENTAL METHOD
  • 3. RESULTS AND DISCUSSION
  • 4. PLANNED WORKS
  • 5. CONCLUSIONS
  • SIMULATIONS OF SOME STRUCTURAL MATERIALS BEHAVIOR UNDER NEUTRON IRRADIATION
  • 1. INTRODUCTION
  • 2. REACTOR CONFIGURATION AND COMPUTATIONAL TOOLS
  • 3. RESULTS AND DISCUSSION
  • 3.1. Molybdenum Alloys
  • 3.2. Vanadium Alloys
  • 4. CONCLUSIONS
  • VACANCY TYPE DEFECTS BEHAVIOR IN MATERIALS FORESEEN FOR LIQUID METAL COOLED FAST REACTORS
  • RESEARCH OF CORROSION BEHAVIOR OF STEAM GENERATOR TUBES FOR LEAD-COOLED POWER UNIT
  • 1. INTRODUCTION
  • 2. CORROSION RESISTANCE IN LIQUID LEAD
  • 3. CORROSION RESISTANCE IN WATER AND SUPERHEATED STEAM
  • 4. INTERGRANULAR CORROSION RESISTANCE
  • 5. THE MAIN RESULTS AND CONCLUSIONS
  • TENSILE TESTING OF SUB-SIZED T91 STEEL SPECIMENS IN LIQUID LEAD
  • 1. INTRODUCTION
  • 2. THE LILLA FACILITY AND TEST SECTIONS
  • 2.1. The description of the LILLA facility
  • 2.2. The description of the test sections
  • 3. SSRT TESTS OF T91 IN ARGON AND LIQUID LEAD
  • 3.1. Material and test conditions
  • 3.2. Tests in argon and liquid lead
  • 4. CONCLUSIONS

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