Numerical simulation of an explosion in a simple scale model of a nuclear reactor

  • Marie-France Robbe CEA Saclay, SEMT-DYN
  • Michel Lepareux CEA Saclay, SEMT-DYN
  • Eloi Treille Socotec Industrie
  • Yves Cariou Novatome, NVPM

Abstract

In the case of a Hypothetical Core Disruptive Accident (HCDA) in a Liquid Metal Fast Breeder Reactor, it is assumed that the core of the nuclear reactor has melted partially and that the chemical 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, thus endangering the safety of the nuclear plant. The experimental test MARA 8 simulates the explosive phenomenon in a mock-up enclosed in a flexible vessel with a flexible roof. This paper presents a numerical simulation of the test and a comparison of the computed results with the experimental results and previous numerical ones.

Keywords

References

[1] D. Acker, A. Benuzzi, A. Yerkess, J. Louvet. MARA 01/02 - Experimental validation of the SEURBNUK and SIRIUS containment codes. In: J. Rastoin, ed., 6th Int. Conf. on Structural Mechanics In Reactor Technology, paper E3/6. Int. Association for Structural Mechanics in Reactor Technology and Commission of the European Communities, Luxembourg, 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 SIRlUS computer code. In: J . Rastoin, ed., Proc. 6th Int. Conf. on Structural Mechanics In Reactor Technology, paper B8/8. Int. Association for Structural Mechanics in Reactor Technology and Commission of the European Communities, Luxembourg, 1981.
[5] C. Bour, M. Sperandio, J . Louvet, C. Rieg. LMFBR's core disruptive accident. Mechanical study of the reactor block. In: A.H. Hadjian, ed., Pmc. 10th Int. Conf. on Structural Mechanics In Reactor Technology, Vol. E, 281-287. American Association for Structural Mechanics in Reactor Technology, Los Angeles, USA, 1989.
Published
Feb 20, 2023
How to Cite
ROBBE, Marie-France et al. Numerical simulation of an explosion in a simple scale model of a nuclear reactor. Computer Assisted Methods in Engineering and Science, [S.l.], v. 9, n. 4, p. 489-517, feb. 2023. ISSN 2956-5839. Available at: <https://cames.ippt.pan.pl/index.php/cames/article/view/1115>. Date accessed: 14 nov. 2024.
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Articles