Published November 1996
| Version v1
Journal article
Calculation of heating-up and oxidation of a fuel assembly under conditions of the CORA-W2 experiment
Description
Developed mathematical model was used to study the stage of fuel assembly heating-up with account of oxidation of fuel cans in the CORA-W2 experiment, simulating WWER-1000 core degradation at severe accident. Results of correlation of obtained design characteristics with experimental data for temperatures of fuel cans and casing, as well as for hydrogen generation rate are presented. 10 refs., 9 figs
Additional details
Additional titles
- Original title (Russian)
- Расчет разогрева и окисления тепловыделяыхщей сборки в условиях эксперимента CORA-W2
Publishing Information
- Journal Title
- Teplofizika Vysokikh Temperatur
- Journal Volume
- 34
- Journal Issue
- 6
- Journal Page Range
- p. 957-964.
- ISSN
- 0040-3644
- CODEN
- TVYTAP
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 28061970
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ARGON; COMPUTERIZED SIMULATION; COOLANTS; FUEL ASSEMBLIES; FUEL CANS; FUEL ELEMENTS; HEATING; HYDROGEN; MATHEMATICAL MODELS; OXIDATION; REACTOR ACCIDENTS; TEMPERATURE DISTRIBUTION; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; TIME DEPENDENCE; WATER VAPOR; WWER TYPE REACTORS; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; ELEMENTS; ENRICHED URANIUM REACTORS; FLUIDS; GASES; METALS; NONMETALS; POWER REACTORS; PWR TYPE REACTORS; RARE GASES; REACTOR COMPONENTS; REACTORS; SIMULATION; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENTS; VAPORS; WATER COOLED REACTORS; WATER MODERATED REACTORS