Validation of the RALOC-mod.4 thermal-hydraulics code on evaporation transients in the Phebus containment
Creators
- 1. Institut de Protection et de Surete Nucleaire, IPSN/DRS/SEMAR, Saint Paul lez Durance, (France)
- 2. ENEA - Innovative Reactor Dept., Bologna (Italy)
Description
IPSN (Nuclear Protection and Safety Institute) and GRS (Gesellschaft fur Anlagen und Reaktorsicherheit Schwertnergasse 1) are developing the ESCADRE-ASTEC systems of codes devoted to the prediction of the behaviour of water-cooled reactors during a severe accident. The RALOC-mod 4 code belongs to this system and is specifically devoted to containment thermal-hydraulics studies. IPSN has designed a Thermal Hydraulic Containment Test Program in support to the Phebus Fission Product Test Program/2/. Evaporation tests have been recently performed in the Phebus containment test facility. The objective of this work is to assess against these tests the capability of the RALOC -mod 4 code to capture the phenomena observed in these experiments and more particularly the evaporation heat transfer and wall heat transfers. (DM)
Files
30020429.pdf
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Additional details
Publishing Information
- Imprint Title
- CNS proceedings of the 1997 CNA/CNS annual conference on powering Canada's future. Vol. 1, 2
- Imprint Pagination
- [1122 p.]
- Journal Page Range
- v. 2 [3 p.]
- ISSN
- 0227-1907
- Report number
- INIS-CA--0070
Conference
- Title
- Powering Canada's future
- Dates
- 8-11 Jun 1997
- Place
- Toronto, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 30020429
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS EXPERIMENT; EVAPORATION; GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT; HEAT TRANSFER; HYDRAULICS; PHEBUS REACTOR; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; THERMAL ANALYSIS; TRANSIENTS; VALIDATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; GERMAN FR ORGANIZATIONS; NATIONAL ORGANIZATIONS; PHASE TRANSFORMATIONS; POOL TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs.