Development of a three-dimensional time-dependent calculation scheme for molten salt reactors and validation of the measurement data of the molten salt reactor experiment

Nuclear Science and Engineering

Volumn 163, Issue 2, 2009, Pages 118-131

  Kophazi J ^a   Lathouwers, D ^b   Kloosterman, J L ^b  

^a BUDAPEST UNIVERSITY OF TECHNOLOGY AND ECONOMICS   (Hungary)

^b DELFT UNIVERSITY OF TECHNOLOGY   (Netherlands)

Author keywords

[No Author keywords available]

Indexed keywords

DEBRIS; FUELS; FUSED SALTS; HEAT CONDUCTION; MOLTEN MATERIALS; NUCLEAR REACTORS; TEMPERATURE;

CALCULATION SCHEME; CHANNEL BLOCKING; DIFFUSION THEORY; HEAT CONDUCTION EQUATIONS; HIGH TEMPERATURE GRADIENT; MEASUREMENT DATA; NATURAL CIRCULATION; THERMAL HYDRAULICS;

MOLTEN SALT REACTOR;

EID: 70350367348     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE163-118     Document Type: Article

References (21)

1. B. E. PRINCE, S. J. BALL, J. R. ENGEL, P. N. HAUBEN- REICH, and T. W. KERLIN, "Zero-Power Physics Experiments on the Molten-Salt Reactor Experiment, " ORNL-4233, Oak Ridge National Laboratory (1968).
2. R. C. ROBERTSON, "Conceptual Design Study of a Single- Fluid Molten-Salt Breeder Reactor, " ORNL-4541, Oak Ridge National Laboratory (1971).
3. G. LAPENTA and P. RAVETTO, "Basic Reactor Physics Problems in Fluid-Fuel Recirculated Reactors, " Kerntechnik, 65, 250 (2000).
4. J. KREPEL, U. GRUNDMANN, U. ROHDE, and F. WEISS, "DYN1D-MSR Dynamics Code for Molten Salt Reactors, " Ann. Nucl. Energy, 32, 1799 (2005).
5. S. DULLA, M. M. ROSTAGNO, and R RAVETTO, "Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems, " Trans. Am. Nucl. Soc, 89, 446 (2003).
6. S. DULLA and P. RAVETTO, "Analysis of the Role of Fluid-Dynamic Phenomena in the Neutronics of Molten-Salt Systems, " Proc. Int. Topi. Mtg. Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C2005), Avignon, France, September 12-15, 2005 (2005).
7. D. LECARPENTIER and V. CARPENTIER, "A Neutronic Program for Critical and Nonequilibrium Study of Mobile Fuel Reactors: The CinsflD Code, " Nucl. Sci. Eng., 143, 33 (2003).
8. C. RENAULT, M. DELPECH, C LE BRUN, D. LECARPENTIER, C. GARZENNE, R. J. M. KONINGS, P. HOSNEDL, O. MATAL, and J. UHLIR, "The MOST Project: Key-Points and Challenges for the Feasibility of Molten Salt Reactors, " Proc. Int. Congress Advances Nuclear Power Plants (ICAPP 05), Seoul, South Korea, June 15, 2005, paper 5208 (2005).
9. C. NICOLINO, G. LAPENTA, S. DULLA, and P. RAVETTO, "Coupled Dynamics in the Physics of Molten Salt Reactors, " Ann. Nucl. Energy, 35, 314 (2008).
10. K. KREPEL, U. ROHDE, U. GRUNDMANN, and F.-P. WEISS, "DYN3D-MSR Spatial Dynamics Code for Molten Salt Reactors, " Ann. Nucl. Energy, 34, 449 (2007).
11. J. J. DUDERSTADT and L. J. HAMILTON, Nuclear Reactor Analysis, Wiley, New York (1976).
12. C. HIRSCH, "Numerical Computation of Internal and External Flows, " Computational Methods for Inviscid and Viscous Flows, Vol.2, John Wiley & Sons, New York (2002).
13. B. BOER, D. LATHOUWERS, M. DING, and J. L. KLOOSTERMAN, "Coupled Neutronics/Thermal-Hydraulics Calculations for High Temperature Reactors with the DALTON- THERMIX Code System, " Proc. Int. Conf. Physics of Reactors (PHYSOR'08), Interlaken, Switzerland, September 14-19, 2008 (2008) (CD-ROM).
14. B. BOER, A. M. OUGOUAG, J. L. KLOOSTERMAN, and G. K. MILLER, "Stress Analysis of Coated Particle Fuel in Graphite of High-Temperature Reactors, " Nucl. Technol, 162, 276 (2008).
15. W. VAN ROOIJEN and D. LATHOUWERS, "Sensitivity Analysis for Delayed Neutron Data, " Ann. Nucl. Energy, 35, 2186 (2008).
16. D. F. WILLIAMS, L. M. TOTH, K. T. CLARNO, and C. W. FORSBERG, "Assessment of Candidate Liquid Salt Coolants for the Advanced High Temperature Reactor (AHTR), " ORNL/GEN4/LTR-05-1001, Oak Ridge National Laboratory (June 30, 2005).
17. W. M. ROHSENOW, J. P. HARTNETT, and Y. I. CHO, Handbook of Heat Transfer, 3rd ed., McGraw-Hill Book Company, New York (1998).
18. Y. S. MUZYCHKA and M. M. YOVANOVICH, "Laminar Forced Convection Heat Transfer in the Combined Entry Region of Non-Circular Ducts, " J. Heat Transfer, 126, 1, 54 (2004).
19. "SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing, Evaluations, " ORNL/TM-2005/39, Version 5, Vols. I-III, Oak Ridge National Laboratory; available from Radiation Safety, Information Computational Center at Oak Ridge National Laboratory as CCC-725 (Apr. 2005).
20. C. LE BRUN et al., "Review of Molten Salt Technology- Reactor Physics Study, Design Review and Nominal Operating Conditions, NonProliferation Issues, " FIKW-CT-2001-2006, Euratom.
21. P. N. HAUBENREICH, "Molten-Salt Reactor Experiments, " ORNL-4396, Oak Ridge National Laboratory (1970).