rdf-syntax-grammar
mods:
  schema location: http://www.loc.gov/mods/v3 http://www.loc.gov/standards/mods/v3/mods-3-2.xsd
  title info:
    title: Benefits and challenges of small modular fast reactors
    sub title: proceedings of a technical meeting
  name:
    name part: International Atomic Energy Agency
    role:
      role term: issuing body.
  type of resource: text
  genre: bibliography
  genre: elektronické knihy
  genre: electronic books
  origin info:
    place:
      place term: au
    date issued: 2021
    issuance: monographic
  language:
    language term: eng
  physical description:
    form: remote
    extent: 1 online resource (351 pages) : illustrations
  abstract: "In the world market of power-producing nuclear reactors, there is growing interest in small and medium sized or modular reactors (SMRs). These can be assembled in-factory, transported by ship or train, installed on site and connected to the electricity grid in a short time, significantly reducing the financial burden of the investment. This publication, which is the outcome of a technical meeting, presents a detailed overview of the different concepts of fast SMRs and highlights the technological, economic and safety potential of these reactors and the associated innovative systems. Although it is mainly focused on innovative reactor solutions aimed to increase safety and simplicity of design, the parameters that contribute to the final cost of the plant are also considered."--Publisher's description.
  table of contents: 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.
  table of contents: 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.
  table of contents: 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.
  table of contents: 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.
  table of contents: 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 ramp.
  note: "August 2021"--Title page verso.
  note: Plný text je dostupný pouze z IP adres počítačů Univerzity Tomáše Bati ve Zlíně nebo vzdáleným přístupem pro zaměstnance a studenty
  note: Includes bibliographical references
  subject:
    topic: Nuclear reactors
  subject:
    topic: Fast reactors
  subject:
    topic: Sodium cooled reactors
  related item:
    title info:
      title: Benefits and challenges of small modular fast reactors
    origin info:
      publisher: Vienna, Austria : International Atomic Energy Agency, 2021
    identifier: (OCoLC)1273673965
  related item:
    title info:
      title: IAEA-TECDOC ; 1972
  identifier: 9789201241214
  identifier: 9201241216
  identifier: 9789201240217
  identifier: https://proxy.k.utb.cz/login
  access condition: Plný text je dostupný pouze z IP adres počítačů Univerzity Tomáše Bati ve Zlíně nebo vzdáleným přístupem pro zaměstnance a studenty
  record info:
    record content source: COD
    record creation date: 220209
    record change date: 20240717213016.0
    record identifier: kn-on1296084195
    language of cataloging:
      language term: eng