New developments in Cathare 2 code
- 1. CEA Centre d'Etudes de Grenoble, 38 (France). Dept. de Thermohydraulique et de Physique
- 2. CISI Ingenierie, 38 - Fontaine (France)
Description
Several thermalhydraulics codes of second generation have been developed during the last ten years. Two fluid six equation models are involved in these codes in which one or three dimensional modules are used. These codes are operational and have proved their efficiency in a wide range of applications in research and development studies as well as in safety studies. CATHARE is the best estimate code, developed by EDF, FRAMATOME and CEA. It is used for Research and Development, licensing and safety studies by the French partners. It is also widely used by industrial and safety institutes in several countries. Thus a new version of CATHARE 2 has been developed. Its main objectives can be divided into 4 topics, as follow: - This new version is fast running, in order to be integrated in the new generation of simulators. - The flexibility has been improved, in particular its robustness because the code is used for industrial studies and safety studies. - The code can be easily couplable with other codes. - A 3 dimensional module has been developed. (authors). 6 tabs., 13 refs., 5 appendix
Availability note (English)
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Additional details
Publishing Information
- Imprint Pagination
- 25 p.
- Report number
- CEA-CONF--11838
Conference
- Title
- 6. International Topical Meeting on Nuclear Reactors Thermal Hydraulics.
- Dates
- 5-8 Oct 1993.
- Place
- Grenoble (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 25074110
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; LOSS OF COOLANT; ONE-DIMENSIONAL CALCULATIONS; PRESSURE VESSELS; PWR TYPE REACTORS; THREE-DIMENSIONAL CALCULATIONS; VECTOR PROCESSING
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; POWER REACTORS; PROGRAMMING; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS