The paper describes the application of computational fluid dynamics (CFD) in simulating density wave oscillations in triangular and square pitch rod bundles. The FLUENT code is used for this purpose, addressing typical conditions proposed for supercritical water reactor (SCWR) conceptual design. The RELAP5 code and an in-house 1D linear stability code are also adopted to compare the results for instability thresholds obtained by different techniques. Transient analyses are performed both by the CFD code and RELAP5, with increasing heating rates and constant pressure drop across the channel, up to the occurrence of unstable behavior. The obtained results confirm that the density wave mechanism is similar in rod bundle and in axisymmetric configurations.
Issue Section:
Nuclear Power
1.
Squarer
, D.
, Schulenberg
, T.
, Struwe
, D.
, Oka
, Y.
, Bittermann
, D.
, Aksan
, N.
, Maraczy
, C.
, Kyrki-Rajamäki
, R.
, Souyri
, A.
, and Dumaz
, P.
, 2003, “High Performance Light Water Reactor
,” Nucl. Eng. Des.
, 221
(1–3
), pp. 167
–180
. 0029-54932.
Yamada
, K.
, Ookawa
, M.
, Asanuma
, Y.
, Sakurai
, S.
, Kitou
, K.
, and Oka
, Y.
, 2007, “Recent Activities and Future Plan of Thermal-Spectrum SCWR Development in Japan
,” Third International Symposium on SCWR—Design and Technology
, Shanghai, China.3.
Dobashi
, K.
, Oka
, Y.
, and Koshizuka
, S.
, 1998: “Conceptual Design of a High Temperature Power Reactor Cooled and Moderated by Supercritical Light Water
,” Proceedings of the Sixth International Conference on Nuclear Engineering, ICONE6
, ASME
, New York
.4.
Heusener
, G.
, Mueller
, U.
, and Squarer
, D.
, 2000, “High Performance Light Water Reactor (HPLWR)
,” Nucl. Europe Worldscan
, XX
(1/2
), pp. 59
–60
.5.
Heusener
, G.
, Mueller
, U.
, Schulenberg
, T.
, and Squarer
, D.
, 2000, “European Development Program for a High Performance Light Water Reactor (HPLWR)
,” SCR-2000
, The University of Tokyo, Tokyo, Japan.6.
Oka
, Y.
, 2000, “Review of High Temperature Water and Steam Cooled Reactor Concepts
” Proceedings of the First International Symposium on Supercritical Water-Cooled Reactors
, Design and Technology, SCR-2000, The University of Tokyo, Tokyo, Japan.7.
Zuber
, N.
, 1966, “An Analysis of Thermally Induced Flow Oscillations in the Near-Critical and Super-Critical Thermodynamic Region
,” Research and Development Center, General Electric Company, Schenectady, NY, Report No. NASA-CR-80609.8.
Yi
, T. T.
, Koshizuka
, S.
, and Oka
, Y.
, 2004, “A Linear Stability Analysis of Supercritical Water Reactors, (I) Thermal-Hydraulic Stability
,” J. Nucl. Sci. Technol.
0022-3131, 41
(12
), pp. 1166
–1175
.9.
Zhao
, J.
, Saha
, P.
, and Kazimi
, M.
, 2005, “Stability of Supercritical Water-Cooled Reactor During Steady-State and Sliding Pressure Start-Up
,” 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11)
, Popes’ Palace Conference Center, Avignon, France, Paper No. 106.10.
Chatoorgoon
, V.
, Voodi
, A.
, and Fraser
, D.
, 2005, “The Stability Boundary for Supercritical Flow in Natural Convection Loops, Part I: H2O Studies
,” Nucl. Eng. Des.
, 235
, pp. 2570
–2580
. 0029-549311.
Ortega
, T. G.
, Class
, A.
, Lahey
, R. T.
, and Schulenberg
, T.
, 2006, “Stability Analysis of a Uniformly Heated Channel With Supercritical Water
,” 14th International Conference on Nuclear Engineering (ICONE 14–89733)
, Miami, FL.12.
Ambrosini
, W.
, and Sharabi
, M. B.
, 2006, “Dimensionless Parameters in Stability Analysis of Heated Channels With Fluids at Supercritical Pressures
,” 14th International Conference on Nuclear Engineering (ICONE 14–89862)
, Miami, FL.13.
Ambrosini
, W.
, 2007, “On the Analogies in the Dynamic Behaviour of Heated Channels With Boiling and Supercritical Fluids
,” Nucl. Eng. Des.
, 237
(11
), pp. 1164
–1174
. 0029-549314.
Ambrosini
, W.
, and Sharabi
, M. B.
, 2007, “Assessment of Stability Maps for Heated Channels With Supercritical Fluids Versus the Predictions of a System Code
,” Nuclear Eng. and Technol.
, 3
(5
), pp. 591
–682
.15.
Sharabi
, M. B.
, Ambrosini
, W.
, and He
, S.
, 2008, “Prediction of Unstable Behaviour in a Heated Channel With Water at Supercritical Pressure by CFD Models
,” Ann. Nucl. Energy
, 35
(5
), pp. 767
–782
. 0306-454916.
Fluent Inc., 2004, “
Fluent User Guide
.”17.
Ambrosini
, W.
, Di Marco
, P.
, and Susanek
, A.
, 1999, “Prediction of the Boiling Channel Stability by a Finite-Difference Numerical Method
,” Second International Symposium On Two-Phase Flow Modelling and Experimentation
, Pisa, Italy.18.
SCIENTECH Inc., 1999, “
RELAP5/MOD3.3 Code Manual, Code Structure, System Models and Solution Methods
,” The Thermal Hydraulics Group, Idaho, Vol. I, June.19.
Yoo
, J.
, Ishiwatari
, Y.
, Oka
, Y.
, and Liu
, J.
, 2006, “Conceptual Design of Compact Supercritical Water-Cooled Fast Reactor With Thermal Hydraulic Coupling
,” Ann. Nucl. Energy
, 33
, pp. 945
–956
. 0306-454920.
Yamaji
, A.
, Oka
, Y.
, and Koshizuka
, S.
, 2001, “Conceptual Core Design of a 1000 MWe Supercritical Pressure Light Water Cooled and Moderated Reactor
,” ANS/HPS Student Conference
, A&M University, Texas.21.
Kim
, S. E.
, and Choudhury
, D.
, 1995, “A Near-Wall Treatment Using Wall Functions Sensitized to Pressure Gradient
,” Separated and Complex Flows
, ASME, New York, Vol. FED-217
, pp. 273
–280
. 0021-999122.
Issa
, R. I.
, 1986, “Solution of Implicitly Discretized Fluid Flow Equations by Operator-Splitting
,” J. Comput. Phys.
0021-9991, 62
, pp. 40
–65
.23.
Lemmon
, E. W.
, McLinden
, M. O.
, and Hurber
, M. L.
, eds., 2002, NIST Reference Fluid Thermodynamic and Transport Properties—REFPPRO
, Aug., NIST Standard Reference Database 23 (Software and Source), V. 7.0, U.S. Department of Commerce.24.
Yang
, J.
, Oka
, Y.
, Ishiwatari
, Y.
, Liu
, J.
, and Yoo
, J.
, 2007, “Numerical Investigation of Heat Transfer in Upward Flows of Supercritical Water in Circular Tubes and Tight Fuel Rod Bundles
,” Nucl. Eng. Des.
, 237
, pp. 420
–430
. 0029-5493Copyright © 2009
by American Society of Mechanical Engineers
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