Development and verification of dynamics code for Molten Salt Reactors

Proceedings of the International Conference on Nuclear Engineering (ICONE12)

Volumn 1, Issue , 2004, Pages 629-634

  Krepel, Jiri ^a   Grundmann, Ulrich ^a   Rohde, Ulrich ^a  

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

Author keywords

[No Author keywords available]

Indexed keywords

ACCELERATION; BREEDER REACTORS; DECELERATION; ENTHALPY; NEUTRONS; PERTURBATION TECHNIQUES; PRESSURIZED WATER REACTORS;

FUEL VELOCITY; MOLTEN SALT REACTORS (MSR); PRECURSORS; REACTIVITY INSERTION;

TRANSIENTS;

EID: 10644274205     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/icone12-49130     Document Type: Conference Paper

References (10)

1. U. Grundmann, U. Rohde, S. Mittag: "DYN3D - Three-Dimensional Core Model for Steady-State and Transient Analysis of Thermal Reactors," Proc. of Int. Topl. Mtg. on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR2000), Pittsburgh (USA), May, 7-11, 2000.
2. Rosenthal, M.W., et al.: "Advances in the development of MSBR," Proceedings of the Fourth International Conference on the Peaceful Uses of Atomic Energy, A/Conf.49/P/048, Geneva, 1971.
3. U. Grundmarav: "HEXNEM - A Nodal Method for the Solution of the Neutron Diffusion Equation in Hexagonal Geometry", Proceedings of the M&C'99 Conference on Mathematics and Computations in Nuclear Applications, pp. 1086-1095, Madrid, September, 27 - 30, 1999.
4. Kasten, P.R., et al.: "Graphite behavior and its effects on MSBRE performance." ORNL, USA, 1968.
5. U. Rohde: "Ein theoretisches Model für Zweiphasenströmung in wassergekühlten Kernreaktoren und seine Anwendung zur Analyse des Naturumlaufs im Heizreaktor AST-500", Dissertation, Zentralinstitut für Kernforschung Rossendorf bei Dresden. Juli 1986.
6. B. E. Prince, J. R. Engel, S. J. Ball, P. N. Haubenreich, T. W. Kerlin: "Zero-Power Physical Experiments on Molten-Salt Reactor Experiment'', ORNL-4233, 1968.
7. P. N. Haubenreich: "Molten-Salt Reactor Experiments", ORNL-4396, 1970.
8. M. Delpech, S. Dulla, C. Garzenne, J. Kophazi, J. Krepel, C. Lebrun, D. Lecarpentier, F. Mattioda, P. Ravetto, A. Rineiski, M. Schikorr, M. Szieberth: "Benchmark of Dynamic Simulation Tools for Molten Salt Reactors", Proceedings of the international conference GLOBAL 2003, 2182-2187, New Orleans. LA, November 2003.
9. R. SANCHEZ et Al., "APOLLO II: a User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations", Proceedings of the Congress on Advances in Reactor Physics, Mathematics and Computation, Paris, 1, 1563-1577, 1987.
10. Rosenthal, M.W., et al.: "Molten-Salt Reactor Program Semiannual Progress Report." ORNL-4449, 1969