Safety Related Issues of Spent Nuclear Fuel Storage: Strategies For Safe Storage Of Spent Fuel

Front Matter....Pages i-xi
Front Matter....Pages 1-1
Spent Nuclear Fuel from Research Reactors: International Status and Perspectives....Pages 3-25
Regulatory Approach for Managing Radioactive Waste in the Republic of Kazakhstan....Pages 27-36
Spent Fuel Management in Poland....Pages 37-54
An Overview of Spent Fuel Storage at Commercial Reactors in the United States....Pages 55-70
Managing Spent Nuclear Fuel at the Idaho National Laboratory....Pages 71-84
Front Matter....Pages 86-86
Assessment of Environmental Impact of Reactor Facilities in Kazakhstan....Pages 87-94
Design and Manufacture of Fuel Assemblies for Russian Research Reactors....Pages 95-105
Strategy for Handling Spent BN-350 Cesium Traps in the Republic of Kazakhstan....Pages 107-142
Account and Control of Nuclear Materials at the WWR-SM Reactor in the Institute of Nuclear Physics, Tashkent....Pages 143-146
Activities of the Kharkov Institute Related to the Problem of Spent Nuclear Fuel Management....Pages 147-164
Front Matter....Pages 166-166
Understanding and Managing the Aging of Spent Fuel and Facility Components in Wet Storage....Pages 167-180
Long-Term (100–300 Years) Interim Dry Storage for Spent Fuel: Package and Facilities Development Including Safety Aspects and Durability Assessment Program....Pages 181-188
Technical Issues of Wet and Dry Storage Facilities for Spent Nuclear Fuel....Pages 189-208
Problems of Nuclear and Radiation Safety of Casks with Spent Fuel during Long-Term Dry Storage....Pages 209-210
Trial of Storage Container Technology for Research Reactor Spent Nuclear Fuel....Pages 211-223
Interim Storage and Long-Term Disposal of Research Reactor Spent Fuel in the United States....Pages 225-241
Front Matter....Pages 244-244
Managing Spent Fuel in Wet Storage at the Savannah River Site....Pages 245-266
Corrosion of Aluminium Alloy SAV-1 and Austenitic Stainless Steels 12Cr18Ni10Ti and 08Cr16Ni11Mo3—Core Structural Materials for WWR-K and BN-350 Reactors....Pages 267-279
Corrosion of Fast-Reactor Claddings by Physical and Chemical Interaction with Fuel and Fission Products....Pages 281-293
Corrosion of Research Reactor Aluminum Clad Spent Fuel in Wet Storage....Pages 295-306
Front Matter....Pages 244-244
Influence of Neutron Irradiation on Mechanical and Dimensional Stability of Irradiated Stainless Steels and its Possible Impact on Spent Fuel Storage....Pages 307-327
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....Pages 329-349
Back Matter....Pages 351-359