Safety Related Issues of Spent Nuclear Fuel Storage (eBook, PDF)
154,69 €
inkl. MwSt.
Sofort per Download lieferbar
Safety Related Issues of Spent Nuclear Fuel Storage (eBook, PDF)
- Format: PDF
- Merkliste
- Auf die Merkliste
- Bewerten Bewerten
- Teilen
- Produkt teilen
- Produkterinnerung
- Produkterinnerung
Bitte loggen Sie sich zunächst in Ihr Kundenkonto ein oder registrieren Sie sich bei
bücher.de, um das eBook-Abo tolino select nutzen zu können.
Hier können Sie sich einloggen
Hier können Sie sich einloggen
Sie sind bereits eingeloggt. Klicken Sie auf 2. tolino select Abo, um fortzufahren.
Bitte loggen Sie sich zunächst in Ihr Kundenkonto ein oder registrieren Sie sich bei bücher.de, um das eBook-Abo tolino select nutzen zu können.
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.
- Geräte: PC
- ohne Kopierschutz
- eBook Hilfe
- Upload möglich
Andere Kunden interessierten sich auch für
- Engineering of Crystalline Materials Properties (eBook, PDF)154,69 €
- Advances in Earthquake Engineering for Urban Risk Reduction (eBook, PDF)309,23 €
- Carbon Nanotubes: From Basic Research to Nanotechnology (eBook, PDF)213,99 €
- Symmetry and Heterogeneity in High Temperature Superconductors (eBook, PDF)213,99 €
- Tribology of Diamond-like Carbon Films (eBook, PDF)149,79 €
- Energy Technology 2016 (eBook, PDF)106,99 €
- Bodie DouglasStructure and Chemistry of Crystalline Solids (eBook, PDF)149,79 €
-
-
-
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.
Produktdetails
- Produktdetails
- Verlag: Springer / Springer Netherland
- Erscheinungstermin: 24. April 2007
- Englisch
- ISBN-13: 9781402059032
- Artikelnr.: 37355392
- Verlag: Springer / Springer Netherland
- Erscheinungstermin: 24. April 2007
- Englisch
- ISBN-13: 9781402059032
- Artikelnr.: 37355392
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
Preface.- Acknowledgements.- Strategies for Safe Storage of Spent Fuel.- Spent Nuclear Fuel from Research Reactors: International Status and Perspectives; P. Adlelfang et al.- Regulatory Approach for Managing Radioactive Waste in the Republic of Kazakhstan; T. Zhantikin, M. Sharipov.- Spent Fuel Management in Poland; S. Chwaszczewski.- An Overview of Spent Fuel Storage at Commercial Reactors in the United States; J. D. B. Lambert, R. Lambert.- Managing Spent Nuclear Fuel at the Idaho National Laboratory; T. J. Hill, D. L. Fillmore.- Radiological Problems of Spent Fuel Storage.-Assessment of Environmental Impact of Reactor Facilities in Kazakhstan; K. K. Kadyrzhanov et al.- Design and Manufacture of Fuel Assemblies for Russian Research Reactors; V. V. Rozhikov et al.- Strategy for Handling Spent BN-350 Cesium Traps in the Republic of Kazakhstan; O. G. Romanenko et al.- Account and Control of Nuclear Materials at the WWR-SM Reactor in the Institute of Nuclear Physics, Tashkent; B. S. Yuldashev et al.- Activities of the Kharkov Institute Related to the Problem of Spent Nuclear Fuel Management; V. M. Azhazha et al.- Technical Issues of Wet and Dry Storage.- Understanding and Managing Aging of Spent Nuclear Fuel and Facility Components in Wet Storage; A. B. Johnson, Jr.- Long-Term (100-300 Year) Interim Dry Storage for Spent Fuel: Package and Facilities Development including Safety Aspects and Durability Assessment Program; J. P. Silvy et al.- Technical Issues of Wet and Dry Storage Facilities for Spent Nuclear Fuel; E. D. Federovich.- Problems of Nuclear and Radiation Safety of Casks with Spent Fuel during Long-term Dry Storage; A. Z. Aisabekov et al.- Trial of Storage Container Technology for Research Reactor Spent Fuel; Z. I. Chechetkina et al.- Interim Storage and Long Term Disposal of Research Reactor Spent Fuel in the United States; N. C. Iyer et al.- Materials Stability Issues of Spent Fuel Storage.- Managing Spent Fuel in Wet Storage at the Savannah River Site; R. L. Sindelar et al.- Corrosion of Aluminium Alloy SAV-1 and Austenitic Stainless Steels 08Cr16Ni11Mo3 and 12Cr18Ni10Ti—Core Structural Materials for WWR-K and BN-350 Reactors; O. P. Maksimkin.- Corrosion of Fast-Reactor Claddings by Physical and Chemical Interaction with Fuel and Fission Products; V. A. Tzykanov et al.- Corrosion of Research Reactor Aluminum Clad Spent Fuel In Wet Storage; L. V. Ramanathan et al.- Influence of Neutron Irradiation on Mechanical and Dimensional Stability of Irradiated Stainless Steels and Possible Impact on Spent Fuel Storage; F. A. Garner.- 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 Reactor; K. K. Kadyrzhanovet al.- List of Authors.- Workshop Photographs.-
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.
Preface.- Acknowledgements.- Strategies for Safe Storage of Spent Fuel.- Spent Nuclear Fuel from Research Reactors: International Status and Perspectives; P. Adlelfang et al.- Regulatory Approach for Managing Radioactive Waste in the Republic of Kazakhstan; T. Zhantikin, M. Sharipov.- Spent Fuel Management in Poland; S. Chwaszczewski.- An Overview of Spent Fuel Storage at Commercial Reactors in the United States; J. D. B. Lambert, R. Lambert.- Managing Spent Nuclear Fuel at the Idaho National Laboratory; T. J. Hill, D. L. Fillmore.- Radiological Problems of Spent Fuel Storage.-Assessment of Environmental Impact of Reactor Facilities in Kazakhstan; K. K. Kadyrzhanov et al.- Design and Manufacture of Fuel Assemblies for Russian Research Reactors; V. V. Rozhikov et al.- Strategy for Handling Spent BN-350 Cesium Traps in the Republic of Kazakhstan; O. G. Romanenko et al.- Account and Control of Nuclear Materials at the WWR-SM Reactor in the Institute of Nuclear Physics, Tashkent; B. S. Yuldashev et al.- Activities of the Kharkov Institute Related to the Problem of Spent Nuclear Fuel Management; V. M. Azhazha et al.- Technical Issues of Wet and Dry Storage.- Understanding and Managing Aging of Spent Nuclear Fuel and Facility Components in Wet Storage; A. B. Johnson, Jr.- Long-Term (100-300 Year) Interim Dry Storage for Spent Fuel: Package and Facilities Development including Safety Aspects and Durability Assessment Program; J. P. Silvy et al.- Technical Issues of Wet and Dry Storage Facilities for Spent Nuclear Fuel; E. D. Federovich.- Problems of Nuclear and Radiation Safety of Casks with Spent Fuel during Long-term Dry Storage; A. Z. Aisabekov et al.- Trial of Storage Container Technology for Research Reactor Spent Fuel; Z. I. Chechetkina et al.- Interim Storage and Long Term Disposal of Research Reactor Spent Fuel in the United States; N. C. Iyer et al.- Materials Stability Issues of Spent Fuel Storage.- Managing Spent Fuel in Wet Storage at the Savannah River Site; R. L. Sindelar et al.- Corrosion of Aluminium Alloy SAV-1 and Austenitic Stainless Steels 08Cr16Ni11Mo3 and 12Cr18Ni10Ti—Core Structural Materials for WWR-K and BN-350 Reactors; O. P. Maksimkin.- Corrosion of Fast-Reactor Claddings by Physical and Chemical Interaction with Fuel and Fission Products; V. A. Tzykanov et al.- Corrosion of Research Reactor Aluminum Clad Spent Fuel In Wet Storage; L. V. Ramanathan et al.- Influence of Neutron Irradiation on Mechanical and Dimensional Stability of Irradiated Stainless Steels and Possible Impact on Spent Fuel Storage; F. A. Garner.- 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 Reactor; K. K. Kadyrzhanovet al.- List of Authors.- Workshop Photographs.-
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.