Commenced in January 2007
Frequency: Monthly
Edition: International
Paper Count: 33093
Determination of Temperature and Velocity Fields in a Corridor at a Central Interim Spent Fuel Storage Facility Using Numerical Simulation
Authors: V. Salajka, J. Kala, P. Hradil
Abstract:
The presented article deals with the description of a numerical model of a corridor at a Central Interim Spent Fuel Storage Facility (hereinafter CISFSF). The model takes into account the effect of air flows on the temperature of stored waste. The computational model was implemented in the ANSYS/CFX programming environment in the form of a CFD task solution, which was compared with an approximate analytical calculation. The article includes a categorization of the individual alternatives for the ventilation of such underground systems. The aim was to evaluate a ventilation system for a CISFSF with regard to its stability and capacity to provide sufficient ventilation for the removal of heat produced by stored casks with spent nuclear fuel.Keywords: Temperature fields, Spent Fuel, Interim storage facility, CFD.
Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1057293
Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 1399References:
[1] ┼áimonis V, ┼ámaižys A, Po┼íkas P. Thermal analysis of new casks for spent nuclear fuel storage at the new ignalina NPP storage facility. Energetika. 2011;8(3):163-71.
[2] Völzke H, Wolff D. In: Safety aspects of long dry interim cask storage of spent fuel in Germany. 13th international high-level radioactive waste management conference 2011, IHLRWMC 2011; ; 2011. p. 712-9.
[3] Huang P, Chen X, Jia L. In: Introduction of interim storage of SNF in INET. International conference on nuclear engineering, proceedings, ICONE; ; 2010.
[4] Fedorovich ED, Karyakin YE, Mikhailov VE, Astafieva VO, Pletnev AA. In: Modeling of heatmass transfer in "wet" and "dry" storages for spent nuclear fuel. 2010 14th international heat transfer conference, IHTC14; ; 2010. p. 303-10.
[5] Ilas G, Gauld IC. SCALE analysis of CLAB decay heat measurements for LWR spent fuel assemblies. Ann Nucl Energy. 2008;35(1):37-48.