Currently, concrete canisters are in use for an interim storage of spent fuels of pressurized heavy water reactors. A major factor in spent fuel dry storage design and key thermal safety issue is the dissipation of the residual heat generated by the spent fuel. Also the spent fuel temperature, in a dry storage canister, must be kept below 160 °C to avoid fuel oxidation. In this research, CFD modeling has been done to evaluate the temperature distribution in radial and vertical directions of the spent fuel cask. The temperature distribution inside the fuel basket is obtained using ANSYS and FLUENT for CFD analysis. The results suggest that when the effects of conduction and convection are combined and the ambient temperature is taken as ...
In this study, the heat flow characteristics and thermal performance of a dry storage cask were inve...
A full-sized model for the horizontally oriented metal cask containing 21 spent fuel assemblies has ...
In a nuclear reactor, an array of fuel rods containing stacked uranium dioxide pellets clad with zir...
Currently, concrete canisters are in use for an interim storage of spent fuels of pressurized heavy ...
One of the interim storage configurations being considered for aluminum-clad foreign research reacto...
This project deals with the thermal analyses of the wet and dry storages of the spent nuclear fuel. ...
A dry storage facility based on the concept of using the concrete canister has been suggested as a s...
The article describes the thermo-hydraulic analysis of a dry cask storage building that is used for ...
The computational fluid dynamics (CFD) code CFDS-FLOW3D (version 3.3) has been utilized to model a t...
In this paper, a calculation chain for the analysis of spent nuclear fuel in long-term interim dry s...
Peak Cladding Temperature (PCT) becomes the reference parameter when assessing the safety during the...
DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear f...
Loading requirements for dry cask storage of spent nuclear fuel are driven primarily by decay heat c...
Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizh...
The analysis of the thermal condition of spent FA (fuel assembly) of BN-350 reactor in a six-place c...
In this study, the heat flow characteristics and thermal performance of a dry storage cask were inve...
A full-sized model for the horizontally oriented metal cask containing 21 spent fuel assemblies has ...
In a nuclear reactor, an array of fuel rods containing stacked uranium dioxide pellets clad with zir...
Currently, concrete canisters are in use for an interim storage of spent fuels of pressurized heavy ...
One of the interim storage configurations being considered for aluminum-clad foreign research reacto...
This project deals with the thermal analyses of the wet and dry storages of the spent nuclear fuel. ...
A dry storage facility based on the concept of using the concrete canister has been suggested as a s...
The article describes the thermo-hydraulic analysis of a dry cask storage building that is used for ...
The computational fluid dynamics (CFD) code CFDS-FLOW3D (version 3.3) has been utilized to model a t...
In this paper, a calculation chain for the analysis of spent nuclear fuel in long-term interim dry s...
Peak Cladding Temperature (PCT) becomes the reference parameter when assessing the safety during the...
DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear f...
Loading requirements for dry cask storage of spent nuclear fuel are driven primarily by decay heat c...
Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizh...
The analysis of the thermal condition of spent FA (fuel assembly) of BN-350 reactor in a six-place c...
In this study, the heat flow characteristics and thermal performance of a dry storage cask were inve...
A full-sized model for the horizontally oriented metal cask containing 21 spent fuel assemblies has ...
In a nuclear reactor, an array of fuel rods containing stacked uranium dioxide pellets clad with zir...