Safety Related Issues of Spent Nuclear Fuel Storage (eBook, PDF)
Redaktion: Lambert, J. D. B.; Kadyrzhanov, K. K.
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Safety Related Issues of Spent Nuclear Fuel Storage (eBook, PDF)
Redaktion: Lambert, J. D. B.; Kadyrzhanov, K. K.
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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.
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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.
Dieser Download kann aus rechtlichen Gründen nur mit Rechnungsadresse in A, B, BG, CY, CZ, D, DK, EW, E, FIN, F, GR, HR, H, IRL, I, LT, L, LR, M, NL, PL, P, R, S, SLO, SK ausgeliefert werden.
Produktdetails
- Produktdetails
- Verlag: Springer Netherlands
- Seitenzahl: 359
- Erscheinungstermin: 24. April 2007
- Englisch
- ISBN-13: 9781402059032
- Artikelnr.: 37355392
- Verlag: Springer Netherlands
- Seitenzahl: 359
- Erscheinungstermin: 24. April 2007
- Englisch
- ISBN-13: 9781402059032
- Artikelnr.: 37355392
- Herstellerkennzeichnung Die Herstellerinformationen sind derzeit nicht verfügbar.
J.D.B. Lambert, Argonne National Laboratory, Chicago, IL, USA / K.K. Kadyrzhanov, Institute of Nuclear Physics, NNC of the Republic of Kazakhstan, Almaty, Kazakhstan
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.
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.