Dynamics of molten salt reactors

Nuclear Technology

Volumn 164, Issue 1, 2008, Pages 34-44

  Krepel, Jiri ^a   Rohde, Ulrich ^b   Grundmann, Ulrich ^b   Weiss, Frank Peter ^b  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

^b INSTITUTE OF ION BEAM PHYSICS AND MATERIALS RESEARCH   (Germany)

Author keywords

Dynamics; Molten salt; MSR

Indexed keywords

CODES (SYMBOLS); DYNAMICS; FUELS; FUSED SALTS; GRAPHITE; LIGHT WATER REACTORS; MOLTEN MATERIALS; NUCLEAR REACTORS; TRANSIENTS;

DELAYED NEUTRON PRECURSOR; FULL THREE-DIMENSIONAL; GRAPHITE-MODERATED; MOLTEN SALT; OAK RIDGE NATIONAL LABORATORY; REACTIVITY INSERTION; TEMPERATURE INCREASE; THERMAL HYDRAULICS;

MOLTEN SALT REACTOR;

EID: 55949090926     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT08-A4006     Document Type: Conference Paper

References (13)

1. H. G. MacPHERSON, "The Molten Salt Reactor Adventure," Nucl. Sci. Eng., 90, 374 (1985).
2. P. N. HAUBENREICH, "Molten-Salt Reactor Experiments," ORNL-4396, Oak Ridge National Laboratory (1970).
3. M. W. ROSENTHAL et al., "Advances in the Development of MSBR," Proc. 4th Int. Conf. Peaceful Uses of Atomic Energy, Geneva, Switzerland, September 6-12, 1971, A/Conf.49/P/048 (1971).
4. "A Technology Roadmap for Generation IV Nuclear Energy Systems," GIF-002-00, U.S. Department of Energy Nuclear Energy Research Advisory Committee and the Generation IV International Forum (Dec. 2002).
5. J. KREPEL, "Dynamics of Molten Salt Reactors," Doctoral Thesis, prepared at Forschungszentrum Rossendorf (June 2006), defended at Czech Technical University, Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering (2006).
6. M. DELPECH, S. DULLA, C. GARZENNE, J. KOPHAZI, J. KREPEL, C. LEBRUN, D. LECARPENTIER, F. MATTIODA, P. RAVETTO, A. RINEISKI, M. SCHIKORR, and M. SZIEBERTH, "Benchmark of Dynamic Simulation Tools for Molten Salt Reactors," Proc. GLOBAL 2003: Atoms for Prosperity: Updating Eisenhower's Global Vision for Nuclear Energy, New Orleans, Louisiana, November 16-20, 2003, American Nuclear Society (2003) (CD-ROM).
7. K. MIKITYUK, S. PELLONI, P. CODDINGTON, E. BUBELIS, and R. CHAWLA, "FAST: An Advanced Code System for Fast Reactor Transient Analysis," Ann. Nucl. Energy, 32, 1613 (2005).
8. U. GRUNDMANN, U. ROHDE, S. MITTAG, and S. KLIEM, "DYN3D Version 3.2, Code for Light Water Reactors (LWR) with Hexagonal or Quadratic Fuel Elements, Description of Models and Methods," FZR-434, ISSN 1437-322X, Forschungszentrum Rossendorf (2005).
9. J. KREPEL, U. GRUNDMANN, U. ROHDE, and F.-P. WEISS: "DYN3D-MSR Spatial Dynamics Code for Molten Salt Reactors," Ann. Nucl. Energy, 34, 449 (2007).
10. J. KREPEL, U. GRUNDMANN, U. ROHDE, and F.-P. WEISS, "DYN1D-MSR Dynamics Code for Molten Salt Reactors," Ann. Nucl. Energy, 32, 1799 (2005).
11. U. ROHDE, "Ein theoretisches Model für Zweiphasen-strömung in wassergekühlten Kernreaktoren und seine Anwendung zur Analyse des Naturumlaufs im Heizreaktor AST-500," Dissertation, Zentralinstitut für Kernforschung Rossendorf bei Dresden (July 1986).
12. B. E. PRINCE, J. R. ENGEL, S. J. BALL, P. N. HAUBENREICH, and T. W. KERLIN, "Zero-Power Physics Experiments on Molten-Salt Reactor Experiment," ORNL-4233, Oak Ridge National Laboratory (1968).
13. R. SANCHEZ et al., "APOLLO II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations," Proc. Congress on Advances in Reactor Physics, Mathematics and Computation, Paris, France, April 21-30, 1987, p. 1563 (1987).