1 |
D. Alvarez et al. Three dimensional calculations and experimental investigations of the primary coolant flow in a 900 MW PWR vessel. Proc. NURETH-5, vol. II, pp. 586-592, 1992
|
2 |
Launder, B.E., Reece, G.J., Rodi, W. Progress in the development of a Reynolds-stress turbulence closure. J. Fluid Mech. 68 (3), 537-566, 1975
DOI
ScienceOn
|
3 |
Y. A. Hassan, J. A. Randorf. Stratification Studies in Nuclear Reactor Components. NURETH-8, Kyoto, Japan, Vol 1, pp 449, 1997
|
4 |
T. Hohne, U. Bieder, H.-M. Prasser, S. Kliem. Validation of Trio_U – Numerical Simulations of a ROCOM Buoyancy Driven Test Case. 12th International Conference on Nuclear Engineering, Washington D.C., USA, April 25-29, Book of Abstracts, S. 278, 2004
|
5 |
H.-M. Prasser, G. Grunwald, U. Rohde, S. Kliem, T. Höhne, R. Karlsson, F.-P. Weiss. Coolant mixing in a Pressurized Water Reactor: Deboration Transients, Steam- Line Breaks, and Emergency Core Cooling Injection. Nuclear Technology 143 (1), p.37, 2003
DOI
|
6 |
F. Menter. CFD Best Practice Guidelines for CFD Code Validation for Reactor Safety Applications. ECORA FIKSCT- 2001-00154, 2002
|
7 |
F. Alavyoon, B. Hemstrom, N.G. Andersson, R. Karlsson. Experimental and computational approach to investigating rapid boron dilution transients in PWRs. CSNI Specialist Meeting on Boron Dilution Reactivity Transients, State College, Pennsylvania, USA, October 18-20, 1995
|
8 |
B. Woods. UM 2x4 Loop Experimental Findings on the Effect of Inertial and Buoyancy forces on Annular Flow Mixing for Rapid Boron Dilution Transients. Ph.D. Thesis, University of Maryland, USA, 2001
|
9 |
H.-M. Prasser, A. Bottger, J. Zschau. A new electrode-mesh tomograph for gas-liquid flows. Flow Measurement and Instru-mentation 9. pp. 111-119, 2001
|
10 |
U. Grundmann, U. Rohde. Investigations on a boron dilution accident for a VVER-440 type reactor by the help of the code DYN3D. ANS Topical Meeting on Advances in Reactor Physics, Knoxville, TN. April 11-15, vol. 3, pp. 464-471, 1994
|
11 |
ANSYS CFX.-10 User Manual, ANSYS-CFX, 2005
|
12 |
Rohde, U.; Kliem, S.; Hohne, T.; Karlsson, R.; Hemstrom, B.; Lillington, J.; Toppila, T.; Elter, J.; Bezrukov, Y. Fluid mixing and flow distribution in the reactor circuit - Part 1: Measurement data base. Nuclear Engineering and Design 235, 421-443, 2005
DOI
ScienceOn
|
13 |
K. Umminger, W. Kastner, J. Liebert, T. Mull. Thermal Hydraulics of PWR's with Respect to Boron Dilution Phenomena: Experimental Results from the Test Facilities PKL and UPTF. Ninth Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH–9), San Francisco, California, USA, CD-ROM, 1999
|
14 |
T. Hohne, Numerical Simulation of ISP-43 TEST A with CFX-4. Proceedings of 2002 ANS/ASME Student Conference. Penn State University, CD-ROM, 2002
|
15 |
T. Hohne, Grunwald G., Prasser H.-M. Investigation of coolant mixing in Pressurized Water Reactors at the Rossendorf mixing test facility ROCOM. 8th International Conference on Nuclear Engineering, Baltimore, USA, CD-ROM, 2000
|
16 |
HDR safety program – thermal mixing in the cold leg and downcomer of the HDR test rig, Report PHDR 91-89. FZ Karlsruhe, Germany, 1990
|
17 |
B. Hemstrom et al. Validation of CFD codes based on mixing experiments (Final report on WP4), EU/FP5 FLOMIX-R report, FLOMIX-R-D11. Vattenfall Utveckling (Sweden), 2005
|