Simulation of the MARA 10 test representing a core disruptive accident

  • Marie-France Robbe CEA Saclay
  • Michel Lepareux CEA Saclay, SEMT-DYN
  • Folco Casadei JRC Ispra, IPSC, T.P.

Abstract

In the case of a Hypothetical Core Disruptive Accident in a Liquid Metal Fast Breeder Reactor, the core of the nuclear reactor is assumed to have partially melted, and the interaction between molten fuel and liquid sodium creates a high-pressure gas bubble in the core. The violent expansion of this bubble loads and deforms the reactor vessel and the internal structures, thus endangering the safety of the nuclear plant. The MARA 10 experimental test simulates a HCDA in a l/30-scale mock-up schematising simply a reactor block. The vessel is filled with water, topped with an air blanket. The test is fired using an explosive charge. This paper presents the numerical models implemented in the EUROPLEXUS code, and a numerical simulation of the test. The evolution of the fluid flows and the deformations of structures are analysed in detail to understand the progress of the explosive phenomenon.

Keywords

accident, simulation, dynamic, mechanics, nuclear, reactor, explosion,

References

[1] D. Acker, A. Benuzzi, A. Yerkess, J. Louvet. MARA 01/02 - Experimental validation of the SEURBNUK and SIRIUS containment codes. Proc. 6th Int. Coni. on Structural Mechanics In Reactor Technology, paper E 3/6. Paris, France, 1981.
[2] C. Albertini, et al. The JRC-COVA programme: Final Report. Commission of the European Communities, Report EUR 8705. Nuclear Science and Technology, 1- 182, 1984.
[3] A. Benuzzi. Comparison of different LMFBR primary containment codes applied to a benchmark problem. Nuclear Engineering and Design, 100: 239-249, 1987.
[4] Y. Blanchet, P. Obry, J . Louvet. Treatment of fluid-structure interaction with the SIRIUS computer code. Proc. 6th Int. Conf. on Structural Mechanics In Reactor Technology, paper B 8/8. Paris, France, 1981.
[5] C. Bour, M. Spérandio, J. Louvet, C. Rieg. LMFBR's core disruptive accident. Mechanical study of the reactor block. Proc. 10th Int. Conf. on Structural Mechanics In Reactor Technology, Vol. E, 281-287. Anaheim, USA, August 1989.
Published
Nov 17, 2022
How to Cite
ROBBE, Marie-France; LEPAREUX, Michel; CASADEI, Folco. Simulation of the MARA 10 test representing a core disruptive accident. Computer Assisted Methods in Engineering and Science, [S.l.], v. 13, n. 2, p. 269-304, nov. 2022. ISSN 2956-5839. Available at: <https://cames.ippt.gov.pl/index.php/cames/article/view/951>. Date accessed: 23 dec. 2024.
Section
Articles

Most read articles by the same author(s)