Thermal analyses of TN-24P dry storage cask with heterogeneous fuel assembly modeling

2021 ◽  
Vol 137 ◽  
pp. 103771
Author(s):  
Hyungju Yun ◽  
Jaebin Shin ◽  
Chiyeong Song ◽  
Kwangheon Park
Author(s):  
Mark Nutt ◽  
Robert Howard ◽  
Ingrid Busch ◽  
Joe Carter ◽  
Alexcia Delley ◽  
...  

Preliminary system-level analyses of the interfaces between at-reactor used fuel management, consolidated storage facilities, and disposal facilities, along with the development of supporting logistics simulation tools, have been initiated to provide the U.S. Department of Energy (DOE) and other stakeholders with information regarding the various alternatives for managing used nuclear fuel (UNF) generated by the current fleet of light water reactors operating in the United States. An important UNF management system interface consideration is the need for ultimate disposal of UNF assemblies contained in waste packages that are sized to be compatible with different geologic media. Thermal analyses indicate that waste package sizes for the geologic media under consideration by the Used Fuel Disposition Campaign may be significantly smaller than the canisters being used for on-site dry storage by the nuclear utilities. Therefore, at some point along the UNF disposition pathway, there could be a need to repackage fuel assemblies already loaded and being loaded into the dry storage canisters currently in use. The implications of where and when the packaging or repackaging of commercial UNF will occur are key questions being addressed in this evaluation. The analysis demonstrated that thermal considerations will have a major impact on the operation of the system and that acceptance priority, rates, and facility start dates have significant system implications.


Author(s):  
S. R. Suffield ◽  
D. J. Richmond ◽  
J. A. Fort

Abstract Different thermal analysis models were developed to simulate the dry cask simulator (DCS). The DCS is an experiment designed to simulate dry storage of a single boiling water reactor fuel assembly under a variety of heat loads and internal pressures. The DCS was set up and tested in both a vertical and horizontal configuration to determine cladding temperatures in vertical and horizontal dry cask storage systems. The models included a detailed STAR-CCM+ model with the fuel assembly geometry explicitly modeled, a porous STAR-CCM+ model with the fuel assembly geometry modeled as a porous media region with calculated effective properties, and a COBRA-SFS model. COBRA-SFS is a thermal-hydraulic code developed for steady-state and transient analysis of multi assembly spent-fuel storage and transportation systems. STAR-CCM+ is a commercial computational fluid dynamics (CFD) code. Both a detailed and porous STAR-CCM+ model were developed to look at the effective thermal conductivity (keff) approach to modeling a fuel assembly. A keff fuel model is typically modeled in CFD thermal analyses due to its significantly lower computational costs. The models were run for a combination of low and high canister pressures (100 kPa and 800 kPa) and low and high internal heat loads (0.5 kW and 5 kW). Results from all three models were compared against experimental data taken from the DCS for the peak cladding temperature (PCT) and inlet air mass flow.


2016 ◽  
Vol 94 ◽  
pp. 189-207 ◽  
Author(s):  
Grzegorz Kępisty ◽  
Jerzy Cetnar ◽  
Przemysław Stanisz

Author(s):  
D. S. Lawson

Careful consideration of the requirements for an A.G.R. fuelling system leads to the adoption of a fuelling machine capable of handling a single fuel assembly and a short shielded sealing plug. Examination of active handling and maintenance leads to a combination of several functions in one facility in order to save cost. Dry storage of irradiated fuel is preferable to storage in a pond.


2012 ◽  
Author(s):  
R. Sindelar ◽  
P. Leeper ◽  
M. Dunsmuir
Keyword(s):  

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