Structural materials for heavy liquid metal cooled fast reactors : proceedings of a technical meeting.

"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 pro...

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Detalles Bibliográficos
Clasificación:Libro Electrónico
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Vienna : International Atomic Energy Agency, 2021.
Colección:IAEA-TECDOC ; 1978.
Temas:
Liquid metal cooled reactors.
Nuclear reactors > Materials.
Réacteurs à réfrigérant liquide métallique.
Réacteurs nucléaires > Matériaux.
Liquid metal cooled reactors
Nuclear reactors > Materials
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 &amp
  • liquid LBE
  • 3.2. T91 &amp
  • liquid Pb
  • 4. RESULTS II
  • CONDITIONS FOR LME/EAC CRACKING IN HLM: INITIATION
  • 4.1. T91 &amp
  • liquid LBE
  • 4.2. T91 &amp
  • 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
  • SESSION II: CORROSION MITIGATION MEASURES: COATING, NEW STRUCTURAL MATERIALS, ENVIRONMENTAL CONDITIONING
  • CORROSION AND MECHANICAL TESTING OF A LOW ALLOYED ALUMINA FORMING AUSTENITE FOR LIQUID LEAD APPLICATIONS
  • 1. INTRODUCTION
  • 2. MATERIALS AND EXPERIMENTS
  • 2.1. Materials
  • 2.2. Liquid lead corrosion exposures
  • 2.3. Small punch testing
  • 3. RESULTS
  • 3.1. Liquid lead corrosion exposures
  • 3.1.1. 550 C exposures
  • 3.1.2. 600 C exposures
  • 3.2. Small punch testing and aging
  • 4. DISCUSSION
  • 5. CONCLUSIONS
  • ALUMINA NANOCERAMIC COATINGS: AN ENABLING TECHNOLOGY FOR HEAVY LIQUID METAL-COOLED FAST REACTORS
  • 1. INTRODUCTION
  • 1.1. Lead Fast Reactor (LFR) technology: materials perspective
  • 1.2. Mitigation strategy for LFR development: state of the art
  • 2. ALUMINA COATINGS BY PULSED LASER DEPOSITION AND BASIC PROPERTIES.
  • 3. MATERIAL QUALIFICATION FOR lfr APPLICATIONS
  • 3.1. Heavy ion irradiation tests
  • 3.2. Gas permeation tests for tritium confinement
  • 3.3. Corrosion tests
  • 4. SUMMARY AND CONCLUSIONS
  • EVALUATION OF THE HIGH-ENTROPY CR-FE-MN-NI ALLOYS COMPATIBILITY WITH A LIQUID LEAD COOLANT
  • 1. INTRODUCTION
  • 2. MATERIALS AND METHODS
  • 3. RESULTS AND DISCUSSION
  • 4. CONCLUSIONS
  • DESIGN AND MATERIAL SELECTION FOR LEAK-BEFORE BREAK NATURE OF DOUBLE WALLED ONCE THROUGH STEAM GENERATORS IN LEAD-BISMUTH COOLED FAST REACTORS
  • 1. INTRODUCTION
  • 2. STEAM GENERATOR DESIGN AND MATERIALS SELECTION
  • 2.1. Double-walled Once-through Steam Generator Design
  • 2.2. Lead-bismuth side Materials Selection for Double Wall Tubes
  • 2.3. Advanced Corrosion Control
  • 2.3.1. Operation Temperature Reduction
  • 2.3.2. Oxygen Control
  • 2.4. Alumina Forming Austenitic Steel Development
  • 3. LEAK BEFORE BREAK APPROACH
  • 4. SUMMARY AND FUTURE WORK
  • COMPATIBILITY EVALUATION ON STRUCTURAL MATERIALS FOR CLEAR IN OXYGEN CONTROLLED LEAD-BISMUTH EUTECTIC AT 500 C AND 550 C
  • 1. INTRODUCTION
  • 2. EXPERIMENTAL
  • 2.1. Specimen preparation
  • 2.2. Post-test analysis
  • 3. EFFECT OF OXYGEN CONCENTRATIONS IN STATIC LBE ON CORROSION BEHAVIOR
  • 4. LONG-TERM CORROSION BEHAVIOR
  • 5. RESEARCH AND DEVELOPMENT OF SI-CONTAINED STEEL
  • 6. CONCLUSIONS
  • DEVELOPMENT OF ALUMINA FORMING MATERIALS FOR CORROSION MITIGATION IN HEAVY LIQUID METAL COOLED NUCLEAR REACTORS
  • 1. INTRODUCTION
  • 2. CORROSION OF METALLIC MATERIALS IN LEAD ALLOYS AT ELEVATED TEMPERTAURES
  • 3. ADVANCED MITIGATION STRATEGIES
  • 3.1. Surface alloying
  • 3.2. AFA
  • alumina forming austenitic steels
  • 3.3. HEA
  • Alumina forming High Entropy Alloys
  • 3.4. Corrosion tests
  • Set-up and conditions
  • 4. RESULTS AND DISCUSSION
  • 4.1. GESA FeCrAl-surface alloys
  • 4.2. AFA alloys after corrosion test.
  • 4.3. HEA alloys after corrosion test
  • 5. SUMMARY AND OUTLOOK
  • CORROSION OF STEEL CLADDINGS OF FAST REACTORS FUEL ELEMENTS IN THE INTERACTION WITH URANIUM-PLUTONIUM NITRIDE FUEL
  • 1. INTRODUCTION
  • 2. THE EFFECT OF THE CARBON AND OXYGEN IMPURITIES
  • 3. CONCLUSION
  • SESSION III: QUALIFICATION PROGRAMMES OF STRUCTURAL MATERIALS FOR HLM FAST REACTORS
  • QUALIFICATION PROGRAMME OF CANDIDATE MATERIALS FOR ALFRED
  • 1. INTRODUCTION
  • 2. MATERIAL CHOICE AND COOLANT CHEMISTRY STRATEGY
  • 3. MATERIALS QUALIFICATION AND RESULTS
  • 3.1. Al2O3 by PLD
  • 3.2. FeCrAl Aluminizing
  • 3.3. AlTiN coating by Physical Vapor Deposition (PVD)
  • 3.4. Al2O3 by Detonation Gun Spray
  • 3.5. AFA steels
  • 4. SUMMARY AND R&amp
  • D NEEDS
  • SOME NEW R&amp
  • D FOCUS IN STRUCTURE MATERIALS LICENSING FOR THE SVBR-100 REACTOR FACILITIES
  • 1. INTRODUCTION
  • 2. MAIN RESULTS OF MATERIALS CORROSION RESISTANCE JUSTIFICATION FOR SVBR-100 REACTOR
  • 3. MAIN RESULTS OF MATERIALS REACTOR TESTING
  • 4. RESEARCH PROGRAM ON COMPLETION OF JUSTIFICATIONS FOR THE USE OF MATERIALS
  • STATUS OF HLMC TECHNOLOGY AND RELATED MATERIALS RESEARCH IN CHINA INSTITUTE OF ATOMIC ENERGY
  • 1. INTRODUCTION
  • 2. LBE DyNAMIC CORROSION TEST LOOP
  • 2.1. Characteristic of loop design
  • 2.2. Main parameters
  • 2.3. Main components and auxiliary system
  • 2.3.1. Main circuit
  • 2.3.2. Storage tank and LBE supply system
  • 2.3.3. Covering gas and vacuum system
  • 2.3.4. Sampling system
  • 2.3.5. Instrumentation control system
  • 2.4. Current state of the loop
  • 3. LBE ThermoNVECTION LOOP
  • 3.1. Characteristics of loop
  • 3.2. Main parameters
  • 3.3. Current studies performing in the loop
  • 4. LBE STATIC CORROSION TEST APPARATUS
  • 4.1. Characteristic of the apparatus
  • 4.2. Main parameters
  • 4.3. Studies performed in the apparatus
  • 5. CORROSION TESTS IN LBE
  • 5.1. Parameters for corrosion test.
  • 5.2. Test results
  • 5.3. Summary
  • 6. LME EFFECTS ON FM STEEL T91
  • 6.1. Parameters for SSRT test
  • 6.2. Test results
  • 6.3. Summary
  • 7. CONCLUSIONS
  • Appendix
  • MEETING PROGRAMME
  • A.1. Meeting Organization
  • A.2. Meting Sessions
  • A.3. Group Discussions
  • LIST OF PARTICIPANTS
  • CONTRIBUTORS TO DRAFTING AND REVIEW.

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