Buch, Englisch, 359 Seiten, Format (B × H): 155 mm x 235 mm, Gewicht: 1150 g
Buch, Englisch, 359 Seiten, Format (B × H): 155 mm x 235 mm, Gewicht: 1150 g
Reihe: Nato Security through Science Series C:
ISBN: 978-1-4020-5902-5
Verlag: Springer Netherlands
This book contains papers from a NATO-sponsored workshop in Almaty in September 2005, which discussed safety-related issues of storing spent nuclear fuel. Fifteen papers cover aluminum-clad fuel discharged from research reactors worldwide, while five papers examine stainless steel-clad fuel from fast reactors, and two Zircaloy-clad fuel from commercial light-water reactors.
Zielgruppe
Research
Autoren/Hrsg.
Fachgebiete
- Technische Wissenschaften Energietechnik | Elektrotechnik Atomenergietechnik
- Technische Wissenschaften Energietechnik | Elektrotechnik Energietechnik & Elektrotechnik
- Technische Wissenschaften Sonstige Technologien | Angewandte Technik Bergbau, Hüttenwesen
- Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Materialwissenschaft: Metallische Werkstoffe
- Geowissenschaften Umweltwissenschaften Nuklearer Strahlenschutz, Nuklearenergie
- Wirtschaftswissenschaften Betriebswirtschaft Bereichsspezifisches Management Arbeitsplatz, Arbeitsschutz, Gefahrstoffschutz
- Geowissenschaften Umweltwissenschaften Abfallbeseitigung, Abfallentsorgung
- Wirtschaftswissenschaften Wirtschaftssektoren & Branchen Energie- & Versorgungswirtschaft Entsorgungswirtschaft
- Rechtswissenschaften Arbeitsrecht Arbeitsschutz- und Arbeitssicherheitsrecht
- Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Materialwissenschaft: Verbundwerkstoffe
- Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Werkstoffkunde, Materialwissenschaft: Forschungsmethoden
- Technische Wissenschaften Maschinenbau | Werkstoffkunde Maschinenbau Tribologie
- Technische Wissenschaften Verfahrenstechnik | Chemieingenieurwesen | Biotechnologie Metallurgie
Weitere Infos & Material
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 ofFast-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.




