Experimental modelling and computer simulation of core debris dispersal
Description
Dispersal of core debris following a postulated high pressure failure of a PWR pressure vessel has been studied experimentally and by computer simulation. This two-part programme aims to improve estimates of the degree of dispersal and the containment pressurisation caused by rapid transfer of chemical and thermal energy from the dispersed debris. The experiments address only the fluid-dynamical aspects of dispersal using a 1/25-scale model of the reactor cavity. The computer model, CORDE, combines the fluid dynamics with the important oxidation and heat transfer processes which would take place in the event of hot debris being ejected into the cavity. The methods employed in the experimental modelling and computer simulation are outlined and some preliminary results from both parts of the programme are presented. (author). 9 refs, 4 figs, 2 tabs
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna (Austria)
- ISBN
- 92-0-020288-8
- Imprint Title
- Severe accidents in nuclear power plants
- Imprint Pagination
- 772 p.
- Series
- Proceedings series.
- Journal Page Range
- v. 2 p. 109-124.
Conference
- Title
- International symposium on severe accidents in nuclear power plants.
- Dates
- 21-25 Mar 1988.
- Place
- Sorrento (Italy).
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 20034867
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; CONTAINMENT; CORIUM; FAILURES; HEAT TRANSFER; MOCKUP; OXIDATION; PLANNING; PRESSURE VESSELS; PRESSURIZATION; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; RESEARCH PROGRAMS
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; COMPUTER CODES; CONTAINERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-SM--296/70.