| 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.
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| Record Nr. | UNINA-9911007259803321 |
Info
"279-1968 - Proposed IEEE Criteria for Nuclear Power Plant Protection Systems" / / IEEE
