In cooperation with the Iranian Nuclear Society
Document Type : Scientific Note
Authors
Highlights
2. M. Asgari, M. R. Abdi, M. Talebi, H. Ahmadikia, Thermal hydvaulic simalation of fluid flow and heat transfer around fuel bundle of PWR reactor and sarvey the effect of spacer grids, 19th International Medanic Conterence, 15-16 (2010).
3. K. Ikeda, M. Hoshi, Development of Mitsubishi high thermal performance grid, JSME International Journal, 45(3) (2002).
4. E. Baglietto, H. Ninokata, A turbulence model study for simulating flow inside tight lattice rod bundles, Nuclear Engineering and Design, 235 (2005) 773–784.
5. D. Chang, S. Tavoularis, Simulations of turbulence, heat transfer and mixing across narrow gaps between rod-bundle subchannels, Nuclear Engineering and Design, 238 (2008) 109–123.
6. F. Baratto, S. Bailey, S. Tavoularis, Measurements of frequencies and spatial correlations of coherent structures in rod bundle flows, Nuclear Engineering and Design, 236 (2006) 1830–1837.
7. A. Aszodi, S. Toth, “CFD study on coolant mixing in VVER-440 fuel rod bundles and fuel assembly heads, Nuclear Engineering and Design, 240 (2009) 2194–2205.
8. A. Aszódi, S. Tóth, CFD analysis of flow field in a triangular rod bundle, Nuclear Engineering and Design, 21 (2008) 352–363.
9. C. Tzanos, Performance of k−ε turbulence models in the simulation of LWR fuel-bundle flows, Nuclear Engineering and Design, 84 (2001) 197–199.
10.S. Chang, A. Moon, Phenomenological investigations on the turbulent flow structures in a rod bundle array with mixing devices, Nuclear Engineering and Design, 238 (2006) 600–609.
11.Ansys, Fluent 6.3 user’s guide, (2006).
12.M. M. EL-Wakil, Nuclear energy conversion, 4th Edition, American Nuclear Society (1982).
13.Incropera, F. De Witt, Introduction to heat transfer, 4th Edition, USA (2002).
14.S. Tóth, A. Aszódi, Calculations of Coolant Flow in a VVER-440 Fuel Bundle with the Code Ansys CFX 10.0, Proc. Technical Meeting on Use of CFD Codes for Safety Assessment of Reactor Systems, Pisa Italy.
Keywords
2. M. Asgari, M. R. Abdi, M. Talebi, H. Ahmadikia, Thermal hydvaulic simalation of fluid flow and heat transfer around fuel bundle of PWR reactor and sarvey the effect of spacer grids, 19th International Medanic Conterence, 15-16 (2010).
3. K. Ikeda, M. Hoshi, Development of Mitsubishi high thermal performance grid, JSME International Journal, 45(3) (2002).
4. E. Baglietto, H. Ninokata, A turbulence model study for simulating flow inside tight lattice rod bundles, Nuclear Engineering and Design, 235 (2005) 773–784.
5. D. Chang, S. Tavoularis, Simulations of turbulence, heat transfer and mixing across narrow gaps between rod-bundle subchannels, Nuclear Engineering and Design, 238 (2008) 109–123.
6. F. Baratto, S. Bailey, S. Tavoularis, Measurements of frequencies and spatial correlations of coherent structures in rod bundle flows, Nuclear Engineering and Design, 236 (2006) 1830–1837.
7. A. Aszodi, S. Toth, “CFD study on coolant mixing in VVER-440 fuel rod bundles and fuel assembly heads, Nuclear Engineering and Design, 240 (2009) 2194–2205.
8. A. Aszódi, S. Tóth, CFD analysis of flow field in a triangular rod bundle, Nuclear Engineering and Design, 21 (2008) 352–363.
9. C. Tzanos, Performance of k−ε turbulence models in the simulation of LWR fuel-bundle flows, Nuclear Engineering and Design, 84 (2001) 197–199.
10.S. Chang, A. Moon, Phenomenological investigations on the turbulent flow structures in a rod bundle array with mixing devices, Nuclear Engineering and Design, 238 (2006) 600–609.
11.Ansys, Fluent 6.3 user’s guide, (2006).
12.M. M. EL-Wakil, Nuclear energy conversion, 4th Edition, American Nuclear Society (1982).
13.Incropera, F. De Witt, Introduction to heat transfer, 4th Edition, USA (2002).
14.S. Tóth, A. Aszódi, Calculations of Coolant Flow in a VVER-440 Fuel Bundle with the Code Ansys CFX 10.0, Proc. Technical Meeting on Use of CFD Codes for Safety Assessment of Reactor Systems, Pisa Italy.
