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Control of heavy loads at nuclear power plants : resolution of Generic Technical Activity A-36 / / H. George
| Control of heavy loads at nuclear power plants : resolution of Generic Technical Activity A-36 / / H. George |
| Autore | George H. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , July 1980 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | Generic letter |
| Soggetto topico |
Loading and unloading - Safety measures
Cranes, derricks, etc - Reliability Spent reactor fuels Nuclear power plants - United States - Safety measures |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Control of heavy loads at nuclear power plants |
| Record Nr. | UNINA-9910705602203321 |
George H.
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| Washington, DC : , : Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , July 1980 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Control of heavy loads near spent fuel
| Control of heavy loads near spent fuel |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1978 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Nuclear power plants - Equipment and supplies
Materials handling Spent reactor fuels |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715488703321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1978 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Corrected letter on heavy loads over spent fuel
| Corrected letter on heavy loads over spent fuel |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1978 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Nuclear power plants - Equipment and supplies
Materials handling Spent reactor fuels |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715488603321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1978 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Dropped fuel assembly
| Dropped fuel assembly |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1986 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Spent reactor fuels
Nuclear fuel rods |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715193703321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1986 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Good practices for water quality management in research reactors and spent fuel storage facilities
| Good practices for water quality management in research reactors and spent fuel storage facilities |
| Edizione | [1st ed.] |
| Pubbl/distr/stampa | [Place of publication not identified], : International Atomic Energy Agency, 2011 |
| Descrizione fisica | 1 online resource (151 pages) |
| Soggetto topico |
Water quality management
Spent reactor fuels |
| ISBN |
1-5231-3004-0
1-280-12788-0 9786613531766 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Intro -- FOREWORD -- CONTENTS -- 1. INTRODUCTION -- 2. WATER CHEMISTRY -- 2.1. IMPORTANCE OF WATER QUALITY IN RESEARCH REACTOR SYSTEMS -- 2.2. CHEMICAL COMPOSITION OF WATER -- 2.4. CONDUCTIVITY -- 2.5. ACTIVATION PRODUCTS IN REACTOR PRIMARY COOLANT WATER -- 2.6. FORMATION OF IONS IN WATER, OXIDATION-REDUCTION -- 2.7. EFFECT OF DISSOLVED ANIONS IN ALUMINIUM STRUCTURES -- 2.8. ORGANIC COMPOUNDS -- 2.9. ALGAE -- 3. DEGRADATION OF MATERIALS IN WATER -- 3.1. INTRODUCTION -- 3.2. ALUMINIUM AND ITS ALLOYS -- 3.3. CARBON STEELS -- 3.4. STAINLESS STEEL -- 3.5. CONCRETE -- 3.6. COPPER ALLOYS -- 3.7. OTHER MATERIALS IN CONTACT WITH WATER IN A RESEARCH REACTOR -- 4. WATER TREATMENT AND PURIFICATION -- 4.1. WATER TREATMENT AND PURIFICATION: GENERAL CONCEPTS -- 4.2. PRIMARY COOLANT WATER TREATMENT SYSTEM -- 4.3. FUEL DECAY POOL/FUEL STORAGE BASIN WATER TREATMENT SYSTEM -- 4.4. SECONDARY CIRCUIT TREATMENT SYSTEM -- 5. MEASURING DEVICES AND METHODOLOGY -- 5.1. INTRODUCTION -- 5.2. ON-LINE VERSUS OFF-LINE MEASUREMENTS -- 5.3. RECOMMENDED EQUIPMENT AND TECHNIQUES -- 5.4. SAMPLING -- 5.5. PROCEDURES FOR WATER ANALYSIS -- 6. RECOMMENDED PRACTICES FOR MANAGEMENT OF WATER QUALITY -- 6.1. PRIMARY COOLING SYSTEM -- 6.2. DECAY AND SPENT FUEL STORAGE BASINS -- 6.3. SECONDARY CIRCUIT -- 6.4. MAKE-UP SYSTEMS AND RESERVOIRS -- 7. CORROSION SURVEILLANCE PROGRAMMES -- 7.1. INTRODUCTION -- 7.2. PRIMARY CIRCUIT AND FUEL STORAGE BASIN CORROSION SURVEILLANCE PROGRAMME -- 7.3. THE SECONDARY CIRCUIT -- 8. QUALITY ASSURANCE -- 8.1. INTRODUCTION -- 8.2. RELEVANT QUALITY SYSTEMS -- 8.3. DOCUMENTS AND RECORDS -- 8.4. ADDITIONAL CONSIDERATIONS FOR A WATER MANAGEMENT QA PROGRAMME -- 9. CASE STUDIES -- 9.1. OPERATIONAL EXPERIENCE IN THE IEA-R1 RESEARCH REACTOR: EFFECT OF A TEMPERATURE EXCURSION.
9.2. OPERATIONAL EXPERIENCE IN WATER QUALITY MANAGEMENT IN TRANSITION OF SPENT FUEL DECAY BASINS TO A SPENT FUEL STORAGE BASIN AT THE SAVANNAH RIVER SITE -- 9.3. OPERATIONAL EXPERIENCE IN RA6 RESEARCH REACTOR (ARGENTINA): CORROSION INDUCED BY SETTLED SOLIDS IN GOOD QUALITY WATER -- 9.4. MEASUREMENT OF PH AND CONDUCTIVITY IN THE HFR RESEARCH REACTOR, PETTEN (NETHERLANDS) -- 9.5. OPERATIONAL EXPERIENCE AT CSF, ARGENTINA: INFLUENCE OF WATER QUALITY IN ALUMINIUM CORROSION -- Appendix I - REFERENCE TEST PROTOCOL FOR A CORROSION SURVEILLANCE PROGRAMME -- I.1. INTRODUCTION -- I.2. DEFINITIONS -- I.3. PRE-ASSEMBLY OF RACKS -- I.4. ASSEMBLY OF RACK -- I.5. IMMERSION OF RACKS IN REACTOR POOL OR SPENT FUEL BASIN -- I.6. ACTIONS DURING THE TEST -- I.7. REMOVAL AND EXAMINATION OF COUPONS -- I.8. DETAILED EXAMINATION IN THE LABORATORY -- Appendix II - EXAMPLE OF OPERATIONAL PROCEDURE FOR WATER QUALITY CONTROL -- REFERENCES -- CONTRIBUTORS TO DRAFTING AND REVIEW. |
| Record Nr. | UNINA-9911006529803321 |
| [Place of publication not identified], : International Atomic Energy Agency, 2011 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Guidebook on Spent Fuel Storage Options and Systems
| Guidebook on Spent Fuel Storage Options and Systems |
| Edizione | [1st ed.] |
| Pubbl/distr/stampa | Havertown : , : International Atomic Energy Agency, , 2024 |
| Descrizione fisica | 1 online resource (108 pages) |
| Collana | Technical Reports Series |
| Soggetto topico |
Spent reactor fuels
Radioactive wastes |
| ISBN |
9789201357236
9201357230 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | 1. INTRODUCTION -- 1.1. Background -- 1.2. Objective -- 1.3. Scope -- 1.4. Structure -- 2. SPENT FUEL STORAGE -- 2.1. Spent fuel arisings -- 2.2. Alternatives for spent fuel storage -- 2.3. Selection criteria for away from reactor storage -- 3. SPENT FUEL STORAGE TECHNOLOGIES -- 3.1. Wet storage -- 3.2. Dry storage -- 3.2.1. Dry storage casks (metal and concrete) -- 3.2.2. Dry storage units (vertical and horizontal) -- 3.2.3. Storage buildings -- 4. SAFETY -- 4.1. Generic spent fuel storage design safety considerations -- 4.2. Specific spent fuel storage design safety considerations -- 4.2.1. Wet storage -- 4.2.2. Dry storage -- 4.3. Safety assessment -- 4.3.1. Anticipated operational occurrences -- 4.3.2. Design basis accidents -- 4.3.3. Design extension conditions -- 5. IMPACT OF AGEING ON SPENT FUEL AND SPENT FUEL STORAGE SYSTEMS -- 5.1. Potential degradation mechanisms affecting storage systems and spent fuel -- 5.1.1. Potential degradation mechanisms of storage systems, structures and components -- 5.1.2. Spent fuel potential degradation mechanisms (wet and dry) -- 5.2. Surveillance -- 5.2.1. Wet storage |
| Record Nr. | UNINA-9911008426003321 |
| Havertown : , : International Atomic Energy Agency, , 2024 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Human reliability analysis [[electronic resource] ] : informed insights on cask drops / / prepared by J. Brewer ... [and others]
| Human reliability analysis [[electronic resource] ] : informed insights on cask drops / / prepared by J. Brewer ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2012] |
| Descrizione fisica | 1 online resource (281 unnumbered pages) : color illustrations |
| Altri autori (Persone) | BrewerJ |
| Soggetto topico |
Spent reactor fuels
Radioactive substances Materials handling |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Human reliability analysis |
| Record Nr. | UNINA-9910701504903321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
| Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management |
| Autore | Agency International Atomic Energy |
| Edizione | [1st ed.] |
| Pubbl/distr/stampa | Lanham : , : International Atomic Energy Agency, , 2006 |
| Descrizione fisica | 1 online resource (138 pages) |
| Disciplina | 796.7209 |
| Soggetto topico |
Radioactive waste disposal
Spent reactor fuels |
| ISBN | 1-280-84915-0 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910693521603321 |
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Agency International Atomic Energy
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| Lanham : , : International Atomic Energy Agency, , 2006 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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KR-85 hazards from decayed fuel
| KR-85 hazards from decayed fuel |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1990 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Spent reactor fuels
Krypton - Isotopes |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715379003321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Overview of nuclear data uncertainty in scale and application to light water reactor uncertainty analysis / / prepared by: W. Wieselquist [and four others] ; Mourad Aissa, NRC project manager
| Overview of nuclear data uncertainty in scale and application to light water reactor uncertainty analysis / / prepared by: W. Wieselquist [and four others] ; Mourad Aissa, NRC project manager |
| Autore | Wieselquist William |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , December 2018 |
| Descrizione fisica | 1 online resource (various pagings) : color illustrations |
| Soggetto topico |
Uncertainty - Mathematical models
Light water reactors Spent reactor fuels |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910711861603321 |
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Wieselquist William
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , December 2018 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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