Restituzioni 2013 : tesori d'arte restaurati : Sedicesima edizione. Guida alla mostra

• Record Nr.: UNINA990009845490403321
• Pubbl/distr/stampa: [Torino] : Intesa Sanpaolo, 2013; Venezia : Marsilio
• ISBN: 978-88-317-1630-7
• Descrizione fisica: 167 p. : ill. ; 22 cm
• Disciplina: 702.88
• Locazione: FLFBC
• Collocazione: 702.88 MOSTRE NAPOLI 2013
• Lingua di pubblicazione: Italiano
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Note generali: Catalogo della Mostra tenutasi a Napoli [23 marzo - 9 luglio 2013, Museo di Capodimonte Gallerie d'Italia, Palazzo Zevallos Stigliano]; Curatori Carlo Bertelli e Giorgio Bonsanti

Benefits and challenges of small modular fast reactors : proceedings of a technical meeting / / International Atomic Energy Agency

• Record Nr.: UNINA9911007259803321
• Pubbl/distr/stampa: Vienna, Austria : , : International Atomic Energy Agency, , 2021
• ISBN: 9789201241214; 9201241216; 9781523149841; 1523149841
• Edizione: [1st ed.]
• Descrizione fisica: 1 online resource (351 pages) : illustrations
• Collana: IAEA TECDOC series, , 1011-4289 ; ; no. 1972
• Disciplina: 621.483
• Soggetti: Nuclear reactors; Fast reactors - Safety measures; Sodium cooled reactors; Liquid metal cooled reactors
• Lingua di pubblicazione: Inglese
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Nota di bibliografia: Includes bibliographical references.
• 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&amp -- 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&amp.; d facilities.
• Sommario/riassunto: The IAEA usually defines smal and medium sized or modular reactors (SMRs) as reactors producing up to 300 MW(e) (small sized or small modular) and reactors producing 300-700 MW(e) (medium sized). There has been increasing interest in SMRs globally owing applications, enhanced safety resulting from inherent passive safety features, reduced upfront capital investment and possibilities for cogeneration and ono-electrical applications. At the same time, SMRs face various technical and economic challenges to their development and wide-scale deployment.