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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.
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.
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.-
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.-
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