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MARC Lista (tabellare)
Benefits and challenges of small modular fast reactors : proceedings of a technical meeting / / International Atomic Energy Agency
Benefits and challenges of small modular fast reactors : proceedings of a technical meeting / / International Atomic Energy Agency
Edizione [1st ed.]
Pubbl/distr/stampa Vienna, Austria : , : International Atomic Energy Agency, , 2021
Descrizione fisica 1 online resource (351 pages) : illustrations
Disciplina 621.483
Collana IAEA TECDOC series
Soggetto topico Nuclear reactors
Fast reactors - Safety measures
Sodium cooled reactors
Liquid metal cooled reactors
ISBN 9789201241214
9201241216
9781523149841
1523149841
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Nota di contenuto Intro -- 1. INTRODUCTION -- 1.1. Background -- 1.2. Objective -- 1.3. Scope -- 1.4. Structure -- 2. SUMMARY OF MEETING SESSIONS -- 2.1. Session I: Sodium cooled fast SMRs -- 2.2. Session II: Heavy Liquid Metal COOLED FAST SMRS -- 2.3. Session III: Safety aspects of fast smrs -- 2.4. Session IV: Technology and Research in Support of SMR Development -- 3. SUMMARY OF GROUP DISCUSSIONS -- 3.1. Group Discussion I: In-factory construction -- 3.2. Group DIiscussion II: Technological challenges to be resolved -- 3.3. Group discussion III: Benefits of fast smrs including market needs -- 4. CONCLUSIONS AND RECOMMENDATIONS -- REFERENCES -- ABBREVIATIONS -- PAPERS PRESENTED AT THE MEETING -- SESSION I: SODIUM COOLED FAST SMRS -- LARGE-EDDY SIMULATION OF THERMALSTRIPING IN THE UPPER INTERNAL STRUCTURE OF THE PROTOTYPE GEN-IV SODIUM-COOLED FAST REACTOR: Detailed modelling and simulation with optimal flow region and integrated simulation with component simplification -- 1. Introduction -- 2. Large eddy simulation of THE upper internal structure -- 2.1. Preliminary simulation -- 2.2. Simulation setup and numerical methods for the LES of the UIS -- 3. integrated modelling and simulation of the entire PHTS for rvcs design -- 4. conclusion -- SMR CADOR: A SMALL SFR WITH INHERENT SAFETY FEATURES -- 1. Introduction -- 2. Context for Gen-IV SMR development -- 2.1. General interest in SMR -- 2.2. Gen-IV objectives -- 2.3. Inherent safety for Gen-IV SFR -- 2.3.1. Reactivity insertions -- 2.3.2. Decay heat removal -- 3. Objectives of the smr-cador -- 4. governing equations of the problem -- 5. Design of the decay heat removal system -- 6. Complete pre-design scheme -- 7. Pre-design options -- 8. Conclusions -- EVALUATION OF POTENTIAL SAFETY AND ECONOMIC BENEFITS AND CHALLENGES OF MODULAR SODIUM-COOLED FAST REACTORS -- 1. Introduction -- 2. Modular SFR and its features.
3. Analysis of influence of modular SFR safety characteristics on its economic indicators -- 3.1. Reactor core safety features -- 3.2. Reactor shutdown system -- 3.3. Decay heat removal system -- 3.4. Localizing safety system -- 3.5. Severe beyond-design basis accidents -- 3.5.1. Method for accounting of possible BDBA consequences in cost of electricity -- 3.5.2. Analysis of impact of BDBA conditions on specific cost of electricity -- 4. Recommendations on ways of improvement of modular SFR -- 5. Conclusion -- FEASIBILITY STUDY OF SMALL SODIUM COOLED FAST REACTORS -- 1. Introduction -- 2. Modular concept -- 2.1. Core design -- 2.2. Plant design -- 2.3. Economic evaluation -- 3. Non Refueling Concept -- 3.1. Core design -- 3.2. Plant design -- 3.3. Economic Evaluation -- 4. Conclusions -- A PRELIMINARY STUDY OF AUTONOMOUS AND ULTRA-LONG LIFE HYBRID MICRO-MODULAR REACTOR COOLED BY SODIUM HEAT PIPES -- 1. Introduction -- 2. Conceptual design of h-mmr core -- 3. Numerical results -- 4. conclusions and futureworks -- SESSION II: HEAVY LIQUID METAL COOLED FAST SMRS -- VALIDATION OF THERMAL HYDRAULIC DESIGN SUPPORT AND SAFETY METHODOLOGY AND APPLICATION SEALER -- 1. Introduction -- 2. Sealer -- 3. Validation efforts in support of later application to sealer -- 3.1. Validation for SPECTRA Simulations -- 3.1.1. ELSY and ALFRED code-to-code comparison -- 3.1.2. CIRCE experiments -- 3.2. Validation for CFD Simulations -- 3.2.1. CIRCE -- 3.2.2. E-SCAPE -- 4. Sealer Safety Analyses -- 4.1. SPECTRA Model -- 4.2. UTOP Analysis -- 4.3. CFD Model -- 4.4. Steady State at Beginning-of-Life -- 4.5. Core Support Analysis -- 5. Conclusions and outlook -- LFR-SMR: AFFORDABLE SOLUTIONS FOR MULTIPLE NEEDS -- 1. Introduction -- 2. The LFR-AS-200 -- 2.1. Description of the LFR-AS-200 -- 2.2. Performance of the LFR-AS-200.
2.2.1. The LFR-AS-200 version nearly self-sustaining in Pu -- 2.2.2. The LFR-AS-200 as a Pu burner -- 3. The micro LFR-TL -- 4. Potential deployment of LFR at different power levels -- 5. Conclusion -- INHERENT SELF-PROTECTION, PASSIVE SAFETY AND COMPETITIVNESS OF SMALL POWER MODULAR FAST REACTOR SVBR-100 -- 1. Introduction -- 2. Inherent self-protection and passive safety of SVBR-100 -- 2.1. Reactor self-protection against loss of coolant type accident -- 2.2. Coolant compatibility with working medium in the secondary circuit and fuel -- 2.3. Self-protection against accidents with SG tube rapture -- 2.4. Reactor self-protection against loss of heat sink, unprotected loss of heat sink (ULOHS) type accidents -- 2.5. Passive protection against reactivity accidents and unprotected transient over power type accidents -- 2.6. Passive protection against unprotected loss-of-flow type accidents -- 2.7. Radio-ecological safety -- 2.8. Self-Protection against unauthorized "freezing" of LBE in the reactor -- 2.9. Defence-in-Depth Barriers -- 2.10. Tolerance to extreme initial events -- 3. Competitiveness of NPPs based on reactors SVBR-100 -- 4. R& -- D key results to subtantiate the reactor SVBR-100 project -- 5. Conclusion -- CLFR-300, AN INNOVATIVE LEAD-COOLED FAST REACTOR BASED ON NATURAL-DRIVEN SAFETY TECHNOLOGIES -- 1. Introduction -- 2. conceptural desing OF CLFR-300 -- 2.1. General description -- 2.2. Reactor core -- 2.3. Primary system and related auxiliary systems -- 2.4. Safety systems -- 3. natural-driven safety technology and its implementations in CLFR-300 -- 3.1. Definition of natural-driven safety technology -- 3.2. NDS technology implementations in CLFR-300 -- 3.2.1. Natural-driven shutdown system (NDSS) -- 3.2.2. Natural-driven decay heat removal system (NDDHRS) -- 4. Conclusions.
CONCEPTUAL DESIGN OF CHINA LEAD Cooled MINI-REACTOR CLEAR-M10D -- 1. Introduction -- 2. China lead cooled reactor development strategy -- 3. Design description of CLEAR-M10d -- 3.1. Core design -- 3.1.1. Reactor core design -- 3.1.2. Fuel element design -- 3.1.3. Thermal hydraulics design -- 3.2. Reactor System design -- 3.2.1. Key components design -- 3.2.2. Engineering safety features -- 3.3. Heat and Power Cogeneration System -- 4. Conclusion -- LEAD FAST REACTOR TECHNOLOGY: A PROMISING OPTION FOR SMR APPLICATION -- 1. Introduction -- 2. Compliance of the LFR to the SMR concept -- 2.1. Technology-specific features -- 2.1.1. Neutronics -- 2.1.2. Physics and chemistry -- 2.2. SMR-specific features -- 2.2.1. Plant integration -- 2.2.2. Flexibility -- 2.2.3. Simplicity, compactness and sharing -- 3. A commercial SM-LFR -- 4. Challenges to deployment and role of ALFRED -- 5. Conclusions -- PRELIMINARY CONCEPTUAL DESIGN OF LEAD-COOLED SMALL FAST REACTOR CORE FOR ICEBREAKER -- 1. Introduction -- 2. Computer codes -- 2.1. Fast reactor analysis code system ARC -- 2.2. Monte Carlo code MCS -- 3. The design strategy of the conceptual core -- 3.1. Core design requirements and primary parameters -- 3.2. Pin design parameter -- 3.3. Core configurations -- 3.4. Optimization of the conceptual core -- 4. Performance analyses -- 4.1. Neutronic performance -- 4.2. Thermal-hydraulic performance -- 4.3. Control rod worth and reactivity feedback coefficients -- 4.4. Integral reactivity parameters for quasi-static reactivity balance -- 5. Conclusion -- SEALER-UK: a 55 MW(E) LEAD COOLED REACTOR FOR COMMERCIAL POWER PRODUCTION -- 1. Introduction -- 2. Plant, fuel and core designL -- 3. Safety -- 3.1. Safety performance -- 4. Economic performance -- 5. Conclusions -- SESSION III: SAFETY ASPECTS OF FAST SMRS.
EXPERIENCE IN THE PHYSICS DESIGN AND SAFETYANALYSIS OF SMALL AND MEDIUM SIZED FBR CORES -- 1. Introduction -- 2. Calculation scheme and reference cores -- 3. Core physics parameters - a comparison -- 4. Response to unprotected loss of flow accident (ULOF) -- 5. Conclusion -- INNOVATIVE MODELLING APPROACHES FOR MOLTEN SALT SMALL MODULAR REACTORS -- 1. INTRODUCTION -- 2. THE INVESTIGATED SYSTEM -- 3. THE MODELLING APPROACH -- 3.2. Thermal-hydraulics model -- 3.3. Neutronics model -- 4. ANALYSIS OF THE VOID REACTIVITY EFFECT -- 5. ANALYSIS OF FUEL COMPRESSIBILITY EFFECTS -- 6. CONCLUSIONS -- NUMERICAL ASSESMENT OF SODIUM FIRE INCIDENT -- 1. Introduction -- 2. Numerical models in sphincs -- 2.1. Pool combustion model -- 2.2. Chemical reaction and recombination ratio of hydrogen -- 2.3. Water vapor release from concrete -- 3. Numerical investigation of sodium pool fire incident -- 3.1. Numerical condition -- 3.2. Result and Discussion -- 3.2.1. No water vapor release from concrete -- 3.2.2. Water vapor release from concrete -- 4. Challenges in SMR -- 5. Conclusion -- ALFRED PROTECTED LOSS OF FLOW ACCIDENT EXPERIMENT IN CIRCE FACILITY -- 1. Introduction -- 2. Circe-hero experimental test PLOFA #1 -- 2.1. Facility description -- 2.2. Experimental test PLOFA #1 description -- 2.3. Experimental results -- 3. Simulation activity -- 3.1. Steady state results -- 3.2. Transient results -- 4. Conclusions -- A PASSIVE SAFETY DEVICE FOR SFRS WITH POSITIVE COOLANT TEMPERATURE COEFFICIENT -- 1. Introduction -- 2. Description of FAST -- 3. Reference cores -- 4. ATWS analyses -- 4.1. ULOF -- 4.2. ULOHS -- 4.3. UTOP -- 5. Conclusions and future works -- SESSION IV: TECHNOLOGY AND RESEARCH IN SUPPORT OF SMR DEVELOPMENT -- MYRRHA TECHNOLOGY AND RESEARCH FACILITIES IN SUPPORT OF HEAVY LIQUID METAL SMR FAST REACTORS -- 1. Introduction -- 2. Applicability of MYRRHA r&.
d facilities.
Record Nr. UNINA-9911007259803321
Vienna, Austria : , : International Atomic Energy Agency, , 2021
Materiale a stampa
Lo trovi qui: Univ. Federico II
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Lead-cooled fast reactor (LFR) [[electronic resource]]
Lead-cooled fast reactor (LFR) [[electronic resource]]
Pubbl/distr/stampa [Idaho Falls, Idaho] : , : Idaho National Laboratory, , [2007?]
Descrizione fisica 1 unnumbered page : digital, PDF file
Collana [Fact sheet ]
Soggetto topico Liquid metal cooled reactors
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Altri titoli varianti Lead-Cooled Fast Reactor
Record Nr. UNINA-9910698520203321
[Idaho Falls, Idaho] : , : Idaho National Laboratory, , [2007?]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Liquid Metal Coolants for Fast Reactors (Reactors Cooled by Sodium, Lead and Lead-bismuth Eutectic)
Liquid Metal Coolants for Fast Reactors (Reactors Cooled by Sodium, Lead and Lead-bismuth Eutectic)
Autore Author) IAEA (Corporate
Edizione [1st ed.]
Pubbl/distr/stampa Lanham : , : International Atomic Energy Agency, , 2012
Descrizione fisica 1 online resource (95 pages)
Altri autori (Persone) Editor)IAEA (Corporate
Soggetto topico Fast reactors
Liquid metal cooled reactors
ISBN 1-5231-3009-1
1-283-98861-5
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Nota di contenuto 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.
Altri titoli varianti Liquid Metal Coolants for Fast Reactors
Record Nr. UNINA-9911006769503321
Author) IAEA (Corporate  
Lanham : , : International Atomic Energy Agency, , 2012
Materiale a stampa
Lo trovi qui: Univ. Federico II
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Recent advances in power conversion and heat rejection technology for fission surface power [[electronic resource] /] / Lee Mason ; prepared for the Nuclear and Emerging Technologies for Space (NETS-2009) cosponsored by ANS and AIAA, Atlanta, Georgia, June 14-18, 2009
Recent advances in power conversion and heat rejection technology for fission surface power [[electronic resource] /] / Lee Mason ; prepared for the Nuclear and Emerging Technologies for Space (NETS-2009) cosponsored by ANS and AIAA, Atlanta, Georgia, June 14-18, 2009
Autore Mason Lee
Pubbl/distr/stampa Cleveland, Ohio : , : National Aeronautics and Space Administration, Glenn Research Center, , [2010]
Descrizione fisica 1 online resource (7 pages) : color illustrations
Collana NASA/TM
Soggetto topico Fission
NASA programs
Technology utilization
Stirling cycle
Liquid metal cooled reactors
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910699800303321
Mason Lee  
Cleveland, Ohio : , : National Aeronautics and Space Administration, Glenn Research Center, , [2010]
Materiale a stampa
Lo trovi qui: Univ. Federico II
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Status of LMFBR reheat in Western Europe, 1972 : report of the United States of America LMFBR Sodium Reheat Team visit to France, Germany (FRG), Netherlands, and United Kingdom, May 22-June 6, 1972
Status of LMFBR reheat in Western Europe, 1972 : report of the United States of America LMFBR Sodium Reheat Team visit to France, Germany (FRG), Netherlands, and United Kingdom, May 22-June 6, 1972
Pubbl/distr/stampa Washington, D.C. : , : Division of Reactor Development and Technology, United States Atomic Energy Commission, , 1973
Descrizione fisica 1 online resource (xiv, 170 pages) : illustrations
Collana WASH (Series)
Soggetto topico Liquid metal cooled reactors
Steam-boilers
Liquid sodium
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Altri titoli varianti Status of LMFBR reheat in Western Europe, 1972
Record Nr. UNINA-9910707089203321
Washington, D.C. : , : Division of Reactor Development and Technology, United States Atomic Energy Commission, , 1973
Materiale a stampa
Lo trovi qui: Univ. Federico II
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Structural materials for heavy liquid metal cooled fast reactors : proceedings of a technical meeting / / International Atomic Energy Agency
Structural materials for heavy liquid metal cooled fast reactors : proceedings of a technical meeting / / International Atomic Energy Agency
Edizione [1st ed.]
Pubbl/distr/stampa Vienna, Austria : , : International Atomic Energy Agency, , [2021]
Descrizione fisica 1 online resource (228 pages)
Disciplina 621.4834
Soggetto topico Liquid metal cooled reactors
Nuclear reactors - Materials
ISBN 92-0-128721-6
1-5231-4991-4
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Nota di contenuto 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 -- 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& -- D NEEDS -- SOME NEW R& -- 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.
Record Nr. UNINA-9910795871203321
Vienna, Austria : , : International Atomic Energy Agency, , [2021]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Structural materials for heavy liquid metal cooled fast reactors : proceedings of a technical meeting / / International Atomic Energy Agency
Structural materials for heavy liquid metal cooled fast reactors : proceedings of a technical meeting / / International Atomic Energy Agency
Edizione [1st ed.]
Pubbl/distr/stampa Vienna, Austria : , : International Atomic Energy Agency, , [2021]
Descrizione fisica 1 online resource (228 pages)
Disciplina 621.4834
Soggetto topico Liquid metal cooled reactors
Nuclear reactors - Materials
ISBN 92-0-128721-6
1-5231-4991-4
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Nota di contenuto 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 -- 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& -- D NEEDS -- SOME NEW R& -- 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.
Record Nr. UNINA-9910807017403321
Vienna, Austria : , : International Atomic Energy Agency, , [2021]
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