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Advances in Nuclear Power Process Heat Applications
| Advances in Nuclear Power Process Heat Applications |
| Autore | Author) IAEA (Corporate |
| Pubbl/distr/stampa | Lanham : , : International Atomic Energy Agency, , 2012 |
| Descrizione fisica | 1 online resource (286 pages) |
| Altri autori (Persone) | Editor)IAEA (Corporate |
| Soggetto topico |
Gas cooled reactors
Nuclear power plants - Safety measures |
| ISBN |
1-5231-3010-5
1-283-59422-6 9786613906670 |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | Cover -- FOREWORD -- CONTENTS -- 1. INTRODUCTION -- 1.1. OBJECTIVES -- 1.2. NUCLEAR PROCESS HEAT APPLICATIONS -- 1.3. SCOPE OF THE REPORT -- 2. PROCESS HEAT HIGH TEMPERAT R REACTOR CONCEPTS -- 2.1. DESIGN ASPECTS -- 2.2. NUUCLEAR HEAT SUPPLY SYSTEM (COUPLING) -- 2.3. SPECIFIC HTGR DESIGN PROPOSALS -- 3. PROCESS HEAT HTGR APPLICATIONS -- 3.1. NUCLEAR HYDROGEN PRODUCTION -- 3.2. NUCLEAR DESALINATION -- 3.3. OTHER APPLICATIONS -- 4. SAFETY AND ENVIRONMENTAL CONSIDERATIONS -- 4.1. SAFETY ISSUES OF NUCLEAR HYDROGEN PRODUCTION -- 4.2. SAFETY ISSUES FOR DESALINATION SYSTEM -- 4.3. COUPLING SCHEMES AND CONTAMINATION OF END PRODUCTS FOR HYDROGEN PRODUCTION -- 4.4. COUPLING SCHEMES AND CONTAMINATION OF END PRODUCTS IN DESALINATION SYSTEM -- 4.5. ENVIRONMENTAL ISSUES OF DESALINATION -- 5. CONCLUSIONS AND RECOMMENDATIONS -- APPENDIX I. NUCLEAR HYDROGEN PRODUCTION IN CHINA -- APPENDIX II. NUCLEAR COAL GASIFICATION RESEARCH IN GERMANY -- APPENDIX III. NUCLEAR REACTOR -- APPENDIX IV. THERMODYNAMIC PROPERTIES OF PLANT MATERIALS -- APPENDIX V. ARGENTINA PHYSICO-CHEMICAL STUDIES ON THE THERMOCHEMICAL REACTION PROCESSES FOR HYDROGEN PRODUCTION -- APPENDIX VI. RECOMMENDATIONS CONCERNING REQUIREMENTS FOR COMPONENTS AND EQUIPMENT -- REFERENCES -- ABBREVIATIONS -- CONTRIBUTORS TO DRAFTING AND REVIEW. |
| Record Nr. | UNINA-9911006593803321 |
Author) IAEA (Corporate
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| Lanham : , : International Atomic Energy Agency, , 2012 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Application of Radiotracer Techniques for Interwell Studies
| Application of Radiotracer Techniques for Interwell Studies |
| Autore | Author) IAEA (Corporate |
| Pubbl/distr/stampa | Lanham : , : International Atomic Energy Agency, , 2012 |
| Descrizione fisica | 1 online resource (248 pages) |
| Altri autori (Persone) | Editor)IAEA (Corporate |
| Soggetto topico |
Radioactive tracers in geophysics
Geothermal resources |
| ISBN |
1-5231-3008-3
1-283-59418-8 9786613906632 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | Cover -- FOREWORD -- CONTENTS -- COPYRIGHT NOTICE -- 1. Introduction -- 1.1. Background -- 1.2. Interwell tracer technology USE in oilfieldS -- 1.3. Interwell tracer technology USE In geothermal fieldS -- 2. Technical Steps in THE Application of Interwell Tracer technology -- 2.1. Planning an interwell tracer test -- 2.2. Implementation of field related operations -- 2.3. Tracer analysis steps -- 2.4. Data interpretation -- 3. QUALITY ASSURANCE of tracers and analytical METHODS -- 3.1. Tracer stability and integrity -- 3.2. analysis of radiolabelled [Co(CN)6]3- and SCN- in the same sample -- II.1. Laboratory intercomparison test on HTO analysis -- II.2. Laboratory intercomparison of analysis of HTO and 14C tagged Methanol -- II.3. LABORATORY INTERCOMPARISON OF PRODUCTION CURVES WITH THE ANDURIL software program -- REFERENCES -- Contributors to drafting and review. |
| Record Nr. | UNINA-9911006548603321 |
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Author) IAEA (Corporate
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| Lanham : , : International Atomic Energy Agency, , 2012 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Construction Technologies for Nuclear Power Plants
| Construction Technologies for Nuclear Power Plants |
| Autore | Author) IAEA (Corporate |
| Pubbl/distr/stampa | Lanham : , : International Atomic Energy Agency, , 2012 |
| Descrizione fisica | 1 online resource (207 pages) |
| Altri autori (Persone) | Editor)IAEA (Corporate |
| Soggetto topico |
Nuclear power plants - Design and construction
Nuclear engineering - Safety measures |
| ISBN |
1-5231-3005-9
1-280-66625-0 9786613643186 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Intro -- FOREWORD -- CONTENTS -- 1. INTRODUCTION -- 1.1. BACKGROUND -- 1.2. OBJECTIVE, SCOPE AND INTENDED AUDIENCE -- 1.3. PREPARATION AND STRUCTURE OF THIS PUBLICATION -- 2. DESCRIPTION AND RATIONALE FOR GROUPING OF BUILDINGS AND STRUCTURES -- 3. PRE-PROJECT (PRE-DEPLOYMENT) AND SITE INFRASTRUCTURE ACTIVITIES -- 3.1. ACTIVITIES RELATED TO INFRASTRUCTURE AND LAYOUT FOR SITE CONSTRUCTION -- 3.2. METHODS FOR PREPARING SITE INFRASTRUCTURE AND LAYOUT FOR SITE CONSTRUCTION -- 4. CONSTRUCTION ACTIVITIES AND METHODS OFGENERIC APPLICABILITY TO ALL BUILDING GROUPS -- 4.1. CIVIL AND STRUCTURAL WORKS -- 4.2. MECHANICAL INSTALLATIONS -- 4.3. ELECTRICAL AND I&C INSTALLATIONS -- 4.4. MATERIALS OF CONSTRUCTION -- 4.5. ECO-FRIENDLY (GREEN BUILDING) DESIGN -- 5. CONSTRUCTION ACTIVITIES AND TECHNOLOGIES SPECIFIC TO GROUP A (NUCLEAR ISLAND) BUILDINGS AND STRUCTURES -- 5.1. CONTAINMENT BUILDING - CONSTRUCTION ACTIVITIES AND TECHNOLOGIES -- 5.2. DIESEL GENERATOR BUILDING - CONSTRUCTION ACTIVITIES AND TECHNOLOGIES -- 5.3. CONTROL ROOM COMPLEX - CONSTRUCTION ACTIVITIES AND TECHNOLOGIES -- 5.4. FUEL BUILDING - CONSTRUCTION ACTIVITIES AND TECHNOLOGIES -- 6. CONSTRUCTION ACTIVITIES AND TECHNOLOGIES SPECIFIC TO GROUP B (TURBINE ISLAND) BUILDINGS AND STRUCTURES -- 6.1. EXCAVATION -- 6.2. SETTING UP OF DEWATERING SYSTEM -- 6.3. CONSTRUCTION OF BASE SLAB -- 6.4. CONSTRUCTION OF CONDENSER COOLING WATER PIPING -- 6.5. INSTALLATION OF CONDENSER -- 6.6. CASTING OF TURBOGENERATOR PEDESTAL -- 6.7. ERECTION OF STRUCTURAL STEEL -- 7. CONSTRUCTION ACTIVITIES AND TECHNOLOGIES SPECIFIC TO GROUP C (BALANCE OF PLANT) BUILDINGS AND STRUCTURES -- 7.1. INTAKE AND DISCHARGE STRUCTURES -- 7.2. CATHODIC PROTECTION -- 8. MODULARIZATION -- 8.1. DEFINITIONS -- 8.2. DESCRIPTION -- 8.3. RECENT CONSTRUCTION EXPERIENCE IN MODULARIZATION WITH PREFABRICATION ANDPREASSEMBLY.
8.4. ADVANTAGES AND DISADVANTAGES -- 8.5. REQUIRED PLANNING -- 8.6. POTENTIAL FUTURE IMPROVEMENTS -- 9. OPEN TOP CONSTRUCTION METHOD -- 9.1. VERY HEAVY LIFTING OPEN TOP CONSTRUCTION -- 9.2. LIFT TOWERS -- 10. QUALITY ASSURANCE, INSPECTION AND TESTING -- 10.1. DEPLOYMENT PLANNING FOR INSPECTION AND TESTING -- 10.2. RADIOGRAPHIC AND ULTRASONIC INSPECTION AND IMAGING -- 10.3. INSPECTION TOOLS -- 10.4. RETRIEVABILITY OF TEST AND CERTIFICATION DOCUMENTATION -- 10.5. AS-BUILT AND BUILDING INFORMATION MANAGEMENT -- 10.6. SHOP INSPECTION AND QUALITY CONTROL FOR MODULE FABRICATION -- 10.7. DOCUMENTATION -- 11. INTEGRATED PROJECT PLANNING AND MANAGEMENT -- 11.1. BACKGROUND -- 11.2. PROJECT CONTROLS PROCESS -- 12. SUMMARY AND CONCLUSION -- 12.1. SUMMARY -- 12.2. CONCLUSION -- Appendix I - SURVEY OF TECHNOLOGIES FOR NUCLEAR POWER PLANT CONSTRUCTION -- I.1. INTEGRATED PROJECT PLANNING AND MANAGEMENT -- I.2. SITE CONSTRUCTION INFRASTRUCTURE AND LAYOUT FOR CONSTRUCTION -- I.3. CIVIL WORKS -- I.4. STRUCTURAL WORKS -- I.5. MECHANICAL INSTALLATIONS -- I.6. ELECTRICAL AND CONTROLS INSTALLATIONS -- I.7. TESTING MANAGEMENT -- Appendix II - SUGGESTED BUILDING LIST -- Appendix III - PLANNING ACTIVITY CHART -- REFERENCES -- BIBLIOGRAPHY -- ABBREVIATIONS -- CONTRIBUTORS TO DRAFTING AND REVIEWING -- Structure of the IAEA Nuclear Energy Series. |
| Record Nr. | UNINA-9911006548203321 |
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Author) IAEA (Corporate
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| Lanham : , : International Atomic Energy Agency, , 2012 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Efficient Water Management in Water Cooled Reactors
| Efficient Water Management in Water Cooled Reactors |
| Autore | Author) IAEA (Corporate |
| Pubbl/distr/stampa | Lanham : , : International Atomic Energy Agency, , 2012 |
| Descrizione fisica | 1 online resource (131 pages) |
| Altri autori (Persone) | Editor)IAEA (Corporate |
| Soggetto topico |
Water conservation
Nuclear power plants |
| ISBN |
1-5231-3014-8
1-283-98866-6 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Cover -- FOREWORD -- CONTENTS -- 1. INTRODUCTION -- 1.1. BACKGROUND -- 1.2. OBJECTIVES AND SCOPE -- 1.3. STRUCTURE -- 2. CURRENT PRACTICES OF WATER USE AND CONSUMPTION IN MAJOR PHASES OF A NUCLEAR POWER PLANT -- 2.1. WATER USE AND CONSUMPTION DURING CONSTRUCTION -- 2.2. WATER USE AND CONSUMPTION DURING COMMISSIONING -- 2.3. WATER USE AND CONSUMPTION DURING OPERATION -- 2.4. WATER USE AND CONSUMPTION DURING SHUTDOWN STATE -- 2.5. WATER USE AND CONSUMPTION DURING DECOMMISSIONING -- 2.6. CONCLUSION -- 3. TECHNOLOGIES AVAILABLE FOR COOLING SYSTEMS -- 3.1. OPEN LOOP COOLING -- 3.2. CLOSED COOLING SYSTEMS -- 3.3. BASIS FOR SELECTION OF COOLING SYSTEMS -- 3.4. EXAMPLES OF POWER PLANTS OPERATING WITH WET DRY OR HYBRID COOLING SYSTEMS -- 3.5. CONCLUSION -- 4. TECHNOLOGIES AVAILABLE FOR PRODUCTION OF INDUSTRIAL AND POTABLE WATER -- 4.1. INDUSTRIAL AND POTABLE WATER USE IN NPPs -- 4.2. TECHNOLOGIES FOR RAW WATER TREATMENT -- 4.3. TECHNOLOGIES FOR PRODUCTION OF INDUSTRIAL AND POTABLE WATER -- 4.4. CONCLUSION -- 5. STRATEGIES FOR REDUCTION OF WATER USE AND CONSUMPTION IN NUCLEAR POWER PLANTS -- 5.1. REDUCTION OF WATER USE AND CONSUMPTION IN COOLING SYSTEMS -- 5.2. REDUCTION OF INDUSTRIAL AND POTABLE WATER USE AND CONSUMPTION -- 5.3. REDUCTION OF WATER USE AND CONSUMPTION FOR WASTE DILUTION -- 5.4. STRATEGIES FOR OPTIMIZING WATER USE AND CONSUMPTION IN MAJOR PHASES OF A NUCLEAR POWER PLANT -- 5.5. CONCLUSION -- 6. FUTURE NPP DESIGNS FOR IMPROVED WATER MANAGEMENT -- 6.1. NEW CONCEPTS OF WATER COOLED REACTOR SYSTEMS AND COMPONENTS TO IMPROVE WATER MANAGEMENT -- 6.2. TRENDS IN SPENT FUEL MANAGEMENT -- 6.3. NEW TECHNOLOGIES FOR REDUCING ACTIVE LIQUID WASTE DILUTION REQUIREMENTS -- 6.4. NEXT GENERATION REACTORS (GENERATION IV) -- 6.5. CONCLUSION -- 7. CONCLUSION -- Appendix - CURRENT PRACTICES ON WATER USE/CONSUMPTION AND MANAGEMENT IN NPPs.
A.1. TURKEY POINT NUCLEAR POWER PLANT -- A.2. PALO VERDE NUCLEAR POWER PLANT -- A.3. DIABLO CANYON NUCLEAR POWER PLANT -- A.4. WATER USE DURING DECOMMISSIONING BASED ON US PRACTICES -- A.5. VALUES REGARDING COOLING WATER SYSTEMS OF SOME EXEMPLARY PLANTS -- GLOSSARY -- REFERENCES -- ABBREVIATIONS -- CONVERSION FACTORS -- CONTRIBUTORS TO DRAFTING AND REVIEW. |
| Record Nr. | UNINA-9911006771103321 |
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Author) IAEA (Corporate
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| Lanham : , : International Atomic Energy Agency, , 2012 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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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 |
| 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 |
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Author) IAEA (Corporate
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| Lanham : , : International Atomic Energy Agency, , 2012 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Management System Standards
| Management System Standards |
| Autore | Author) IAEA (Corporate |
| Pubbl/distr/stampa | Lanham : , : International Atomic Energy Agency, , 2012 |
| Descrizione fisica | 1 online resource (76 pages) |
| Altri autori (Persone) | Editor)IAEA (Corporate |
| Soggetto topico |
Quality assurance - Standards
Nuclear facilities |
| ISBN |
1-5231-3012-1
1-283-59412-9 9786613906571 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | Cover -- FOREWORD -- CONTENTS -- 1. INTRODUCTION -- 1.1.BACKGROUND -- 1.2.OBJECTIVE -- 1.3.SCOPE -- 1.5.STRUCTURE -- 2. APPLICATION OF IAEA GS-R-3 AND ASME NQA-1 STANDARDS -- 2.1.OBJECTIVES OF IAEA GS-R-3 AND ASME NQA-1 -- 2.2.SCOPE AND APPROACH -- 2.3.APPLICATION -- 3. EXTENT TO WHICH IAEA GS-R-3 ADDRESSES ASME NQA-1 REQUIREMENTS -- 4. EXTENT TO WHICH ASME NQA-1 ADDRESSES IAEA GS-R-3 REQUIREMENTS -- 4.1.MANAGEMENT SYSTEM -- APPENDIX I: CORRELATION BETWEEN THE REQUIREMENTS OF IAEA GS-R-3 AND THOSE OF ASME NQA-1 -- APPENDIX II: CORRELATION BETWEEN THE REQUIREMENTS OF ASME NQA-1 AND THOSE OF IAEA GS-R-3 -- REFERENCES -- CONTRIBUTORS TO DRAFTING AND REVIEW. |
| Record Nr. | UNINA-9911006536503321 |
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Author) IAEA (Corporate
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| Lanham : , : International Atomic Energy Agency, , 2012 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Management System Standards
| Management System Standards |
| Autore | Author) IAEA (Corporate |
| Pubbl/distr/stampa | Lanham : , : International Atomic Energy Agency, , 2012 |
| Descrizione fisica | 1 online resource (69 pages) |
| Altri autori (Persone) | Editor)IAEA (Corporate |
| Soggetto topico |
Nuclear power plants - Safety measures
Quality assurance - Standards |
| ISBN |
1-5231-3011-3
1-283-59411-0 9786613906564 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | Cover -- FOREWORD -- CONTENTS -- 1. INTRODUCTION -- 1.1. BACKGROUND -- 1.2. OBJECTIVE -- 1.3. SCOPE -- 1.4. USERS -- 2. APPLICATION OF IAEA GS-R-3 AND ISO 9001:2008 STANDARDS -- 3. MAJOR DIFFERENCES AND CORRELATIONS -- 3.1. GENERAL APPROACH -- 3.2. MANAGEMENT SYSTEM -- 3.3. MANAGEMENT RESPONSIBILITY -- 3.4. RESOURCE MANAGEMENT -- 3.5. PROCESS IMPLEMENTATION -- 3.6. MEASUREMENT, ASSESSMENT AND IMPROVEMENT -- 4. NOTES TO AID USERS IN MEETING ADDITIONAL REQUIREMENTS -- APPENDIX: CORRELATION BETWEEN THE REQUIREMENTS OF IAEA GS-R-3 AND THOSE OF ISO 9001:2008 -- REFERENCES -- CONTRIBUTORS TO DRAFTING AND REVIEW. |
| Altri titoli varianti |
Management System Standards - Comparison between IAEA GS-R-3 and ISO 9001
Management System Standards |
| Record Nr. | UNINA-9911006536303321 |
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Author) IAEA (Corporate
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| Lanham : , : International Atomic Energy Agency, , 2012 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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