-
1
-
-
33845724406
-
Computational Fluid Dynamics Modeling of Two-phase Flow in a Boiling Water Reactor Fuel Assembly
-
American Nuclear Society, Avignon, France. Sept
-
A.Tentncr, S.Lo, A.Ioilev, M.Samigulin, V.Ustincnko, "Computational Fluid Dynamics Modeling of Two-phase Flow in a Boiling Water Reactor Fuel Assembly", Proceedings of the International Conference on Mathematics and Computations, American Nuclear Society, Avignon, France. Sept. 2005.
-
(2005)
Proceedings of the International Conference on Mathematics and Computations
-
-
Tentncr, A.1
Lo, S.2
Ioilev, A.3
Samigulin, M.4
Ustincnko, V.5
-
2
-
-
70349155497
-
Advances in computational fluid dynamics modeling of two phase flow in a boiling water reactor fuel assembly
-
Miami, Florida, USA, July 17-20
-
A.Tentncr, S.Lo, A.Ioilev, M.Samigulin, V.Ustincnko, V.Melnikov, V.Kozlov, "Advances in computational fluid dynamics modeling of two phase flow in a boiling water reactor fuel assembly", Proc. Int. Conf. Nuclear Engineering ICONE-14, Miami, Florida, USA, July 17-20, 2006.
-
(2006)
Proc. Int. Conf. Nuclear Engineering ICONE-14
-
-
Tentncr, A.1
Lo, S.2
Ioilev, A.3
Samigulin, M.4
Ustincnko, V.5
Melnikov, V.6
Kozlov, V.7
-
3
-
-
84885304340
-
-
STAR-CD Version 3.20 Methodology Manual, Chapter 13,CD-adapco, UK. 2004.
-
STAR-CD Version 3.20 Methodology Manual, Chapter 13,CD-adapco, UK. 2004.
-
-
-
-
4
-
-
44349101575
-
Development and Validation of an Extended Two-Phase CFD Model for the analysis of Boiling Flow in Reactor Fuel Assemblies
-
Nice, France, May 13-18
-
A.Tentner, W.D.Pointer, T.Sofu, D.Weber, "Development and Validation of an Extended Two-Phase CFD Model for the analysis of Boiling Flow in Reactor Fuel Assemblies", Proc. Int. Conf. Advances in Nuclear Power Plants, Nice, France, May 13-18, 2007.
-
(2007)
Proc. Int. Conf. Advances in Nuclear Power Plants
-
-
Tentner, A.1
Pointer, W.D.2
Sofu, T.3
Weber, D.4
-
6
-
-
84885328086
-
-
V.Ustinenko, M.Samigulin, A.Ioilev, S.Lo, A.Tentner, A.Lychagin, A.Razin, V.Girin, Ye.Vanyukov, Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis. OECD/NEA International Workshop on The Benchmarking of CFD Codes for Application to Nuclear Reactor Safety (CFD4NRS), Garching, Germany, September 5-7, 2006 (Nuclear Engineering and Design, 2007, in press)
-
V.Ustinenko, M.Samigulin, A.Ioilev, S.Lo, A.Tentner, A.Lychagin, A.Razin, V.Girin, Ye.Vanyukov, "Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis." OECD/NEA International Workshop on The Benchmarking of CFD Codes for Application to Nuclear Reactor Safety (CFD4NRS), Garching, Germany, September 5-7, 2006 (Nuclear Engineering and Design, 2007, in press)
-
-
-
-
7
-
-
44349109601
-
Advances in the modeling of cladding heat transfer and critical heat flux in boiling water reactor fuel assemblies
-
Pittsburgh, Pennsylvania, USA, September 30-October 4
-
th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburgh, Pennsylvania, USA, September 30-October 4, 2007.
-
(2007)
th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12)
-
-
Ioilev, A.1
Samigulin, M.2
Ustinenko, V.3
Kucherova, P.4
Tentner, A.5
Lo, S.6
Splawski, A.7
-
8
-
-
0042456372
-
Study of Two-Phase Flow Patterns by simultaneous X-ray and flash photography
-
February
-
G.F.Hewitt, D,N,Roberts, "Study of Two-Phase Flow Patterns by simultaneous X-ray and flash photography", Atomic Energy Research Establishment Harwell, AERE-M 2159, February 1969.
-
(1969)
Atomic Energy Research Establishment Harwell, AERE-M
, pp. 2159
-
-
Hewitt, G.F.1
Roberts, D.N.2
-
10
-
-
0006240593
-
Flow Visualization Studies of Boiling at High Pressure
-
A.Bennett, G.Hewitt, H.Kearsey, R.Keeys, P.Lacey, "Flow Visualization Studies of Boiling at High Pressure", Proc. Inst. Mech. Eng. 1965, Vol 180, Pt.3C, p.260-270.
-
(1965)
Proc. Inst. Mech. Eng
, vol.180
, Issue.PART.3C
, pp. 260-270
-
-
Bennett, A.1
Hewitt, G.2
Kearsey, H.3
Keeys, R.4
Lacey, P.5
-
11
-
-
0036722782
-
Flow stricture and bubble characteristics of steam-water two-phase flow in large- diameter pipe
-
K.Yoneda, A.Yasuo, T.Okawa. "Flow stricture and bubble characteristics of steam-water two-phase flow in large- diameter pipe", Nucl. Eng. Des., 2002, Vol.217, p.267-281.
-
(2002)
Nucl. Eng. Des
, vol.217
, pp. 267-281
-
-
Yoneda, K.1
Yasuo, A.2
Okawa, T.3
-
12
-
-
0026222455
-
Analysis of phase distribution in fully developed laminar bubbly two phase flow
-
S.P.Antal., R.T.Lahey, J.E.Flaherty, "Analysis of phase distribution in fully developed laminar bubbly two phase flow", Int. J. Multiphase Flow, 1991. No.7, p.635-652.
-
(1991)
Int. J. Multiphase Flow
, Issue.7
, pp. 635-652
-
-
Antal, S.P.1
Lahey, R.T.2
Flaherty, J.E.3
-
13
-
-
0347355290
-
What is entrainment in vertical two-phase churn flow?
-
B.J.Azzopardi, E.Wren. "What is entrainment in vertical two-phase churn flow?", Int. J. Multiphase Flow, 2004, Vol.30, p. 89-103.
-
(2004)
Int. J. Multiphase Flow
, vol.30
, pp. 89-103
-
-
Azzopardi, B.J.1
Wren, E.2
|