Multi-hazard performance of reinforced concrete dry casks subjected to chloride attack and tip-over impact
Not Available
Hanifehzadeh, Mohammad↗
SEARCH · Engineering Papers
Results for “Cask”
Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.
Added mass effect for tip-over analysis of dry cask composite structures at two different scales
Not Available
Champiri, Masoud Dehghani (ORCID:0000000236792535)↗
Criticality and uncertainty assessment of assembly misloading in BWR transportation cask
Not Available
Radaideh, Majdi I.↗
Dynamic response of dry cask storage systems for spent nuclear fuel to near field blast loading
Not Available
Hanifehzadeh, Mohammad↗
Interaction of cosmic ray muons with spent nuclear fuel dry casks and determination of lower detection limit
Not Available
Chatzidakis, S.↗
Dynamic structural response of reinforced concrete dry storage casks subjected to impact considering material degradation
Not Available
Hanifehzadeh, Mohammad↗
Probabilistic analysis of vertical concrete dry casks subjected to tip-over and aging effects
Not Available
Ebad Sichani, Majid (ORCID:0000000304943287)↗
Effect of basket/rail gap on temperature prediction in the TN-32 cask under storage and drying conditions
Not provided.
Nuclear Science & Technology↗
Optimization of dry cask loadings for used nuclear fuel management strategies
Not Available
Spencer, Kristina Yancey (ORCID:0000000304480411)↗
Validation of the GAMMA-PC methodology for dry cask loading optimization
Not Available
Spencer, Kristina Yancey (ORCID:0000000304480411)↗
Probabilistic seismic analysis of concrete dry cask structures
Not Available
Ebad Sichani, Majid (ORCID:0000000304943287)↗
Evaluation of Microwave Cavity Gas Sensor for In-Vessel Monitoring of Dry Cask Storage Systems
Explore the source record for details and available documents.
Bakhtiari, S.↗
COBRA-SFS thermal-hydraulic analysis code for spent fuel storage and transportation casks: Models and methods
COBRA-SFS, a thermal-hydraulics code developed for steady-state and transient analysis of multi-assembly spent-fuel storage and transportation systems, has been incorporated into the Used Nuclear Fuel-Storage, Transportation and Disposal Analysis Resource and Data System tool as a module devoted to spent fuel package thermal analysis. This paper summarizes the basic formulation of the equations and models used in the COBRA-SFS code, showing that COBRA-SFS fully captures the important physical behavior governing the thermal performance of spent fuel storage systems, with internal and external natural convection flow patterns, and heat transfer by convection, conduction, and thermal radiation. Of particular significance is the capability for detailed thermal radiation modeling within the fuel rod array.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Application of muon tomography to fuel cask monitoring
Explore the source record for details and available documents.
Muon tomography spent nuclear fuel↗
Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator.
Abstract not provided.
Pulido, Ramon↗
SPENT FUEL TRANSPORTATION RISK ASSESSMENT: CASK IMPACT ANALYSES.
Abstract not provided.
Ammerman, Douglas James↗