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Safety Related Issues of Spent Nuclear Fuel Storage
At a NATO-sponsored workshop in Almaty in September 2005, specialists from the IAEA, Brazil, France, Kazakhstan, Poland, Russia, USA and Uzbekistan discussed safety-related issues of storing spent nuclear fuel. Fifteen papers dealt with aluminium-clad fuel discharged from research reactors worldwide...
| Clasificación: | Libro Electrónico |
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| Autor Corporativo: | |
| Otros Autores: | , |
| Formato: | Electrónico eBook |
| Idioma: | Inglés |
| Publicado: |
Dordrecht :
Springer Netherlands : Imprint: Springer,
2007.
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| Edición: | 1st ed. 2007. |
| Colección: | Nato Security through Science Series C:, Environmental Security,
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| Temas: | |
| Acceso en línea: | Texto Completo |
Tabla de Contenidos:
- Strategies for Safe Storage of Spent Fuel
- Spent Nuclear Fuel from Research Reactors: International Status and Perspectives
- Regulatory Approach for Managing Radioactive Waste in the Republic of Kazakhstan
- Spent Fuel Management in Poland
- An Overview of Spent Fuel Storage at Commercial Reactors in the United States
- Managing Spent Nuclear Fuel at the Idaho National Laboratory
- Radiological Problems of Spent Fuel Storage
- Assessment of Environmental Impact of Reactor Facilities in Kazakhstan
- Design and Manufacture of Fuel Assemblies for Russian Research Reactors
- Strategy for Handling Spent BN-350 Cesium Traps in the Republic of Kazakhstan
- Account and Control of Nuclear Materials at the WWR-SM Reactor in the Institute of Nuclear Physics, Tashkent
- Activities of the Kharkov Institute Related to the Problem of Spent Nuclear Fuel Management
- Technical Issues of Wet and Dry Storage
- Understanding and Managing the Aging of Spent Fuel and Facility Components in Wet Storage
- Long-Term (100-300 Years) Interim Dry Storage for Spent Fuel: Package and Facilities Development Including Safety Aspects and Durability Assessment Program
- Technical Issues of Wet and Dry Storage Facilities for Spent Nuclear Fuel
- Problems of Nuclear and Radiation Safety of Casks with Spent Fuel during Long-Term Dry Storage
- Trial of Storage Container Technology for Research Reactor Spent Nuclear Fuel
- Interim Storage and Long-Term Disposal of Research Reactor Spent Fuel in the United States
- Materials Stability Issues of Spent Fuel Storage
- Managing Spent Fuel in Wet Storage at the Savannah River Site
- Corrosion of Aluminium Alloy SAV-1 and Austenitic Stainless Steels 12Cr18Ni10Ti and 08Cr16Ni11Mo3-Core Structural Materials for WWR-K and BN-350 Reactors
- Corrosion of Fast-Reactor Claddings by Physical and Chemical Interaction with Fuel and Fission Products
- Corrosion of Research Reactor Aluminum Clad Spent Fuel in Wet Storage
- Influence of Neutron Irradiation on Mechanical and Dimensional Stability of Irradiated Stainless Steels and its Possible Impact on Spent Fuel Storage
- Degradation in Mechanical Properties of Stainless Steels C0.12Cr18Ni10Ti and C0.08Cr16Ni11Mo3-Materials for Hexagonal Ducts of Spent Fuel Assemblies from the BN-350 Fast Neutron Reactor.