ISO-STANDARD AND IAEA GUIDANCE MATERIAL FOR PACKAGE LOAD ATTACHMENT POINTS ? Current Approaches and Developments
Abstract not provided.
Publications
ISO-STANDARD AND IAEA GUIDANCE MATERIAL FOR PACKAGE LOAD ATTACHMENT POINTS ? Current Approaches and Developments F
Abstract not provided.
Horizontal 30 cm Drop Test on 1/3 Scale ENSA ENUN 32P Dual Purpose Cask
Abstract not provided.
Shock Environments for the Nuclear Fuel Transportation System (Transportation Platform Cask Basket and Surrogate Assemblies) during Ocean Transport
Abstract not provided.
Shock Environments for the Nuclear Fuel Transportation System (Transportation Platform Cask Basket and Surrogate Assemblies) during Heavy-Haul Transport and Handling
Abstract not provided.
Shock Environments for the Nuclear Fuel Transportation System (Transportation Platform Cask Basket and Surrogate Assemblies) during Rail Transport
Abstract not provided.
Shock Environments for the Nuclear Fuel Transportation System (Transportation Platform Cask Basket and Surrogate Assemblies) during Rail Transport
Abstract not provided.
Shock Environments for the Nuclear Fuel Transportation System (Transportation Platform Cask Basket and Surrogate Assemblies) during Specialized Rail Tests
Abstract not provided.
Shock Environments for the Nuclear Fuel Transportation System (Transportation Platform Cask Basket and Surrogate Assemblies) during Ocean Transport
Abstract not provided.
Transportation Work Update
Abstract not provided.
Shock Environments for the Nuclear Fuel Transportation System (Transportation Platform Cask Basket and Surrogate Assemblies) during Heavy-Haul Transport and
Abstract not provided.
Horizontal 30 cm Drop Test of 1/3 Scale ENSA ENUN 32P Dual Purpose Cask
Abstract not provided.
FY19 Update on Modeling Activities for Crystalline Work Package
Abstract not provided.
Update on the Transportation Work
Abstract not provided.
30 cm Horizontal Drop of ENSA ENUN 32P 1/3 Scale Cask
Abstract not provided.
DECOVALEX19 TASK C: GREETStep 3 Hydrology and Geochemical Analysis Update of SNL Team
Abstract not provided.
DECOVALEX19 Task C: GREET (Groundwater Recovery Experiment in Tunnel): Fracture Characterization Modeling of Hydrology Geochemistry and Reactive Transport at the
Abstract not provided.
NTERNATIONAL MULTI-MODAL SPENT NUCLEAR FUEL TRANSPORTATION TEST: THE TRANSPORTATION TEST TRIATHLON
Abstract not provided.
Determination of factors influencing radionuclide transport in fractured crystalline rock
International High-Level Radioactive Waste Management 2019, IHLRWM 2019
Numerical modeling of flow and transport through fractured crystalline rock was conducted to identify major factors that affect migration of radionuclides from a high-level nuclear waste repository. The study was based on data collected at the Mizunami Underground Research Laboratory (URL) in Japan. Distributions of fracture parameters were used to generate a selected number of DFN realizations. For each realization the DFN was upscaled to a continuum mesh to provide permeability and porosity fields. The upscaled permeability and porosity fields were then used to study flow and transport through the fractured rock in a site-scale domain. For the present study the focus is on the effect of domain size and on upscaling of DFN to a continuum system. Simulation results and analysis on various upscaling and boundary condition assumptions are presented.
Transportation Test Results Shaker Table and 30cm Drop
Abstract not provided.
Utilization of Fracture Models for Geologic Disposal of Nuclear Waste in Granitic Host Rocks
Abstract not provided.
DECOVALEX19 WORKSHOP 6
Abstract not provided.
30-CM DROP TEST OF 1/3 SCALE ENSAENUN-32P CASK
Abstract not provided.
Final Results from a System-Theoretic Framework for Mitigating Complex Risks in International Transport of Spent Nuclear Fuel
Abstract not provided.
ENSA CaskTransportationDemo Discussion
Abstract not provided.
Results 26–50 of 124