MISTRA facility for containment lumped parameter and CFD codes validation. Example of the International Standard Problem ISP47
Creators
- 1. Lab. d'Etudes des Transferts et de Mecanique des Fluides, CEA Saclay, Direction de l'Energie Nucleaire, Commissariat a l'Energie Atomique, Gif sur Yvette Cedex (France)
Description
During a severe accident in a Pressurized Water Reactor (PWR), the formation of a combustible gas mixture in the complex geometry of the reactor depends on the understanding of hydrogen production, the complex 3D thermal-hydraulics flow due to gas/steam injection, natural convection, heat transfer by condensation on walls and effect of mitigation devices. Numerical simulation of such flows may be performed either by Lumped Parameter (LP) or by Computational Fluid Dynamics (CFD) codes. Advantages and drawbacks of LP and CFD codes are well-known. LP codes are mainly developed for full size containment analysis but they need improvements, especially since they are not able to accurately predict the local gas mixing within the containment. CFD codes require a process of validation on well-instrumented experimental data before they can be used with a high degree of confidence. The MISTRA coupled effect test facility has been built at CEA to fulfil this validation objective: with numerous measurement points in the gaseous volume - temperature, gas concentration, velocity and turbulence - and with well controlled boundary conditions. As illustration of both experimental and simulation areas of this topic, a recent example in the use of MISTRA test data is presented for the case of the International Standard Problem ISP47. The proposed experimental work in the MISTRA facility provides essential data to fill the gaps in the modelling/validation of computational tools. (author)
Files
37104747.pdf
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Additional details
Publishing Information
- Publisher
- Nuclear Society of Slovenia
- Imprint Place
- Ljubljana (Slovenia)
- ISBN
- 961-6207-25-3
- Imprint Title
- Proceedings of the International Conference Nuclear Energy for New Europe 2005
- Imprint Pagination
- 114 Megabytes
- Journal Page Range
- [12 p.]
- Report number
- INIS-SI--06-002
Conference
- Title
- International Conference Nuclear Energy for New Europe 2005
- Dates
- 5-8 Sep 2005
- Place
- Bled (Slovenia)
INIS
- Country of Publication
- Slovenia
- Country of Input or Organization
- Slovenia
- INIS RN
- 37104747
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT; FLUID MECHANICS; HYDROGEN; PRODUCTION; PWR TYPE REACTORS; SAFETY ANALYSIS; SHIP PROPULSION REACTORS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ELEMENTS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; NONMETALS; POWER REACTORS; PROPULSION REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs., 5 tabs., 10 figs. Imprint:1280 refs., 206 tabs., 883 figs.