Published 2009
| Version v1
Miscellaneous
LIVE test FSt4. Experimental results and simulation by CONV code
Creators
- 1. Forschungszentrum Karlsruhe (FZK), Eggenstein-Leopoldshafen (Germany)
- 2. Nuclear Safety Inst. of Russian Academy of Sciences (IBRAE), Moscow (Russian Federation)
Description
3-D thermohydraulic CFD code CONV was applied to the simulation of FSt4 LIVE water test. Two calculations were performed: in the first one the homogeneous heating of liquid was assumed, in the second one the spiral heaters actually used in the test were modelled. The results of these two calculations were compared with each other and with the experimental data. The obtained results shows that there is no critical difference in the heat flux distribution at the vessel wall for these two cases, indicating that the LIVE facility adequately represents thermal conditions of the homogeneously heated liquid. (author)
Additional details
Publishing Information
- Imprint Title
- NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
- Imprint Pagination
- [4617 p.]
- Journal Page Range
- [13 p.]
Conference
- Title
- 13. international topical meeting on nuclear reactor thermal hydraulics
- Acronym
- NURETH-13
- Dates
- 27 Sep - 2 Oct 2009
- Place
- Kanazawa, Ishikawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43093540
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; CORIUM; HEAT FLUX; HYPOTHETICAL ACCIDENTS; MELTDOWN; NATURAL CONVECTION; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1076.pdf; 7 refs., 16 figs.