A study on concrete degradation during molten core / concrete interactions
Creators
- 1. Inst. Atomnoj Ehnergij, Kurchatov (Kazakhstan)
- 2. Natsional'nyj Yadernyj Tsentr, Kurchatov (Kazakhstan)
- 3. NUPEC, (Japan)
Description
A series of MCCI tests was performed in COTELS project at NUPEC to examine concrete degradation characteristics during MCCI with and without water addition onto the debris. Molten stainless steel or a mixture composed of UO2, ZrO2, Zr and stainless steel was slumped into a two-dimensional concrete trap, where volumetric decay heat generation was simulated by an induction heating technique. The results of dry MCCI tests implied that concrete ablation was dominated by melting of aggregates when the debris was crusted and cement was thermally weaker than aggregates. Without presence of stable crust, unmolten aggregates were possible to relocate upward due to the density difference from the debris. Concrete responses under a wet condition showed a tendency that water migrated into thermally degraded concrete. A preliminary water migration model was incorporated into COCO code for transient heat conduction. The prediction by COCO code agreed with the tendency of concrete thermal responses observed in the dry and wet MCCI tests. (author)
Additional details
Additional titles
- Original title (Russian)
- Изучение деградации бетона в процессе взаимодействия кориума с бетоном (MCCI)
Publishing Information
- Journal Title
- Vestnik Natsional'nogo Yadernogo Tsentra Respubliki Kazakhstan
- Journal Volume
- 1
- Journal Issue
- 17
- Journal Page Range
- p. 99-107
- ISSN
- 1729-7516
INIS
- Country of Publication
- Kazakhstan
- Country of Input or Organization
- Kazakhstan
- INIS RN
- 36106396
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ABLATION; C CODES; CONCRETES; CORIUM; INTERACTIONS; MELTDOWN; REACTOR ACCIDENTS; REACTOR SAFETY; STAINLESS STEELS; URANIUM OXIDES; WATER COOLED REACTORS; ZIRCONIUM; ZIRCONIUM OXIDES
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; BUILDING MATERIALS; CARBON ADDITIONS; CHALCOGENIDES; COMPUTER CODES; ELEMENTS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; METALS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTORS; SAFETY; STEELS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; TRANSITION ELEMENTS; URANIUM COMPOUNDS; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- 24 refs., 14 figs.