The aim of the project is to generate high quality experimental data that will be used for improving the modelling and validation of computational fluid dynamics (CFD) and lumped parameter (LP) computer codes designed to predict post-accident containment thermal-hydraulic conditions. The unique and complementary instrumentation used in the PANDA and MISTRA facilities and the different size and configuration of the two installations will contribute to address a variety of measured parameters, configurations and scale, thus enhancing the value of the data for code applications. Relevant containment phenomena and separate effects will be studied in the programme, including the effects of jets, natural convection, the effect of containment coolers, the effect of sprays etc. The experiments will not only support CFD and LP code validation for current operating reactors but also simulate conditions specific to advanced reactor designs.
A kick-off meeting for the project was held in June 2007. The detailed test specifications are currently being formulated and first results are expected by early 2008. In parallel, analytical activities will be conducted by participants for the benchmarking and qualification of their computer codes.
Project participants |
Nuclear Research Institute, Czech Republic |
Valtion Teknillinen Tutkimuskeskus, Finland |
| Commissariat à l'Énergie Atomique, France |
Electricité de France, France |
Korea Atomic Energy Research Institute, Republic of Korea |
Strålsäkerhetsmyndigheten, Sweden |
Paul Scherrer Institute, Switzerland |
Jozef Stefan Institute, Slovenia |
D. Paladino, R. Zboray and P. Benz, Horizontal Jets Impinging on the Vertical Wall of a Containment Compartment, Paper 7357, 2007 International Congress on Advances in Nuclear Power Plants (ICAPP'07), Nice, France, 13-18 May 2007.
D. Paladino, R. Zboray, P. Benz and M. Andreani (2007), Three gas mixture plume inducing
mixing and stratification in a multi compartment containment, Paper 195, 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburgh, USA.
2007-2010
US$ 3.2 million
Nuclear
Safety Research in OECD Countries: Summary Report of Major Facilities
and Programmes at Risk
(pdf, 238 kb)
Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR)
(pdf, 664 kb)
*PANDA: PAssive Nachwaermeabfuhr und DruckAbbau Testanlage (passive decay heat removal and depressurisation test facility).
**MISTRA: Mitigation and STRAtification facility.
Last updated: 21 August 2008
Nuclear Research Institute, Czech Republic
Valtion Teknillinen Tutkimuskeskus, Finland
Institut de Radioprotection et de Sûreté Nucléaire, France
Electricité de France, France
Gesellschaft für Anlagen- und Reaktorsicherheit, Germany
Japan Nuclear Energy Safety Organisation, Japan
Korea Atomic Energy Research Institute, Republic of Korea
Strålsäkerhetsmyndigheten, Sweden
Paul Scherrer Institute, Switzerland
Jozef Stefan Institute, Slovenia