An Overview of the Pressurized Thermal Shock Issue in the Context of the NURESIM Project

Lucas, D.; Bestion, D.; Bodèle, E.; Coste, P.; Scheuerer, M.; D'Auria, F.; Mazzini, D.; Smith, B.; Tiselj, I.; Martin, A.; Lakehal, D.; Seynhaeve, J.-M.; Kyrki-Rajamäki, R.; Ilvonen, M.; Macek, J.

doi:10.1155/2009/583259

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An Overview of the Pressurized Thermal Shock Issue in the Context of the NURESIM Project

Lucas, D. Forschungszentrum Dresden-Rossendorf, e.V. (FZD), Institute of Safety Reseach, P.O. Box 510 199, 01454 Dresden, Germany
Bestion, D. Commissariat à l'Énergie Atomique (CEA), Centre d'Études Nucléaires de Grenoble, 17 Rue des Martyrs, 38054 Grenoble, France
Bodèle, E. Forschungszentrum Dresden-Rossendorf, e.V. (FZD), Institute of Safety Reseach, P.O. Box 510 199, 01454 Dresden, Germany
Coste, P. Commissariat à l'Énergie Atomique (CEA), Centre d'Études Nucléaires de Grenoble, 17 Rue des Martyrs, 38054 Grenoble, France
Scheuerer, M. Gesellschaft für Anlagen- und Reaktorsicherheit mbH(GRS), 85748 Garching, Germany
D'Auria, F. Dipartmento di Ingengeria Meccanica, Nucleare e della produzione, Università di Pisa, Via Diotisalvi 2, 56126 Pisa, Italy
Mazzini, D. Dipartmento di Ingengeria Meccanica, Nucleare e della produzione, Università di Pisa, Via Diotisalvi 2, 56126 Pisa, Italy
Smith, B. Paul Scherrer Institute, 5232 Villigen-PSI, Switzerland
Tiselj, I. Jožef Stefan Institute (JSI), 1000 Ljubljana, Slovenia
Martin, A. Fluid Dynamics Power Generation Department, Recherche et Développement, Électricité de France (EDF), 6 quai Watier, 78400 Chatou, France
Lakehal, D. ASCOMP GmbH, Technoparkstrass 1, 8005 Zurich, Switzerland
Seynhaeve, J.-M. Université Catholique de Louvain La Neuve (UCL), Place du levant.2, 1348 Louvain-La-Neuve, Belgium
Kyrki-Rajamäki, R. Lappeenranta University of Technology (LUT), Skinnarilankatu 34, 53851 Lappeenranta, Finland
Ilvonen, M. VTT Industrial Systems, PL 1000, 02044 VTT, Finland
Macek, J. Nuclear Research Institute Rez plc (NRI), Husinec-Rez 130, 25068 Rez, Czech Republic

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Science and Technology of Nuclear Installations. - Hindawi Limited. - 2009, vol. 2009, p. 1-13

Nuclear Energy and Engineering

English Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident scenarios for Pressurized Water Reactors may cause Emergency Core Coolant injection into the cold leg leading to PTS situations. They imply the formation of temperature gradients in the thick vessel walls with consequent localized stresses and the potential for propagation of possible flaws present in the material. This paper focuses on two-phase conditions that are potentially at the origin of PTS. It summarizes recent advances in the understanding of the two-phase phenomena occurring within the geometric region of the nuclear reactor,that is, the cold leg and the downcomer, where the “PTS fluid-dynamics" is relevant. Available experimental data for validation of two-phase CFD simulation tools are reviewed and the capabilities of such tools to capture each basic phenomenon are discussed. Key conclusions show that several two-phase flow subphenomena are involved and can individually be simulated at least at a qualitative level, but the capability to simulate their interaction and the overall system performance is still limited. In the near term, one may envisage a simplified treatment of two-phase PTS transients by neglecting some effects which are not yet well controlled, leading to slightly conservative predictions.

Language

English

Open access status

gold

Identifiers

DOI 10.1155/2009/583259
ISSN 1687-6075

Persistent URL

https://sonar.ch/global/documents/133523

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