Thermal hydraulic effect of porous blockage in fuel subassembly of sodium cooled fast reactor

Author:

Govindha Rasu N.,Velusamy K.,Sundararajan T.,Chellapandi P.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference20 articles.

1. CFD-Expert, 2009. Zeus Numerix Pvt. Ltd., Mumbai-400076.

2. A comparative study of the MATRA-LMR-FB calculation with the SABRE result for the flow blockage accident in the sodium cooled fast reactor;Chang;Nucl. Eng. Des.,2011

3. Fluid flow through packed columns;Ergun;Chem. Eng. Prog.,1952

4. Fontana, M.H., Macpherson, R.E., Gnadt, P.A., Parsly, L.F., Kress, T.S., Wantland, J.L., 1973. Effect of partial blockages in simulated LMFBR fuel assemblies. Contract no. W-7405-eng-26, Oak Ridge Natl. Lab., Oak Ridge, Tennessee-37830.

5. George, M.A., Dobson, G.P., 1990. Fast reactor subassembly blockage studies-calculations of temperatures within a blockage, in the wake of a blockage and at thermocouple detector locations. 4, Int. Fast Reac. Safety Meeting.

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