Conclusions of the ISP-47 'containment thermal-hydraulics'

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12

Volumn , Issue , 2007, Pages

  Vendel, J ^a   Malet, J ^a   Bentaib, A ^a   Allelein, H J ^b   Schwarz, S ^b   Studer, E ^c   Paillere H ^c   Fischer, K ^d   Houkema, M ^e  

^a INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

^b Gesellschaft für Anlagen und Reaktorsicherheit ^*  (Germany)

^c DIF   (France)

^d Germany   (Germany)

^e NUCLEAR RESEARCH AND CONSULTANCY GROUP NRG   (Netherlands)

Author keywords

[No Author keywords available]

Indexed keywords

BENCHMARKING; BOUNDARY CONDITIONS; CONCENTRATION (PROCESS); HYDRAULICS;

DENSITY STRATIFICATION; LUMPED PARAMETER (LP);

COMPUTATIONAL FLUID DYNAMICS;

EID: 44349107102     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (10)

1. Chen C. J., Rodi W., Vertical Turbulent Buoyant Jets, A review of Experimental Data, The Science and Applications of Heat and Mass Transfer, Volume 4, Pergamon Press, 1980
2. th Int. Topical Meeting on Nuclear Thermal-Hydraulics , NURETH-10, Seoul 2003
3. th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Avignon, France, October 2005
4. th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Avignon, France, October 2-6, 2005
5. OECD State-Of-the-Art Report on Containment Thermal-hydraulics and Hydrogen Distribution, Nuclear Safety, NEA/CSNI/R(99)16, 1999
6. Porcheron E., J. Malet, A. Nuboer, L. Bouilloux, J. Vendel Experimental study of helium distribution inside the TOSQAN vessel in presence of steam filmwise condensation, International Heat Transfer Conference, Sydney, Australia 2006
7. th Int. Topical Meeting on Nuclear Thermal-Hydraulics , NURETH-10, Seoul 2003
8. Studer E., Dabbene F., Magnaud J.P., Blumenfeld L., Quillico J.J. and Paillere H., On the use of the MISTRA Coupled Effect Test Facility for the validation of Containment Thermal-Hydraulics codes, Proc. Int. Topical Meeting on Nuclear Thermal-Hydraulics, NURETH-10, Seoul, Korea, 5-9 October 2003
9. Tkatschenko I., Studer E. and Paillere H., MISTRA Facility for Containment Lumped Parameter and CFD code validation: Example of the International Standard Problem ISP47, Proc. Int. Conf. Nuclear Energy for New Europe, Bled, Slovenia, September 5-8, 2005
10. th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9, 2003