Published September 2001
| Version v1
Report
Analysis of a severe accident management procedure at VVER-1000 reactor units: effect on the degradation of the containment ground slab and on the magnitude of the source term
Description
The procedure involves opening of the two doors closing the tunnel between the downcomer and the neighbouring room GA302 in a time before failure of the reactor vessel bottom. It is assumed that the progress of concrete degradation by action of the molten material will be appreciably slower in the case of an extensive and shallow melt basin, providing certain time for additional remedial provisions capable of preventing containment damage or, at least, mitigating radiological consequences of the accident. The aims of the study was: (a) investigate if melt spreading will bring about slower melt penetration through the concrete, and if so, to what extent, and (b) ascertain how the source term will be thereby affected. (P.A.)
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.czAdditional details
Additional titles
- Original title (Czech)
- Analyza postupu pro zvladani tezkych havarii na bloku VVER-1000: vliv na degradaci zakladove desky kontejnmentu a na velikost zdrojoveho clenu
Publishing Information
- Imprint Pagination
- [175 p.]
- Report number
- UJV--11619-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 37015938
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; FISSION PRODUCTS; LOSS OF COOLANT; M CODES; MATHEMATICAL MODELS; MELTDOWN; PRIMARY COOLANT CIRCUITS; PROBABILISTIC ESTIMATION; REACTOR COMPONENTS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; SAFETY ANALYSIS; SOURCE TERMS; TUNNELS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; POWER REACTORS; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; UNDERGROUND FACILITIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Developed within the Czech Ministry of Industry and Trade project 'Increasing the efficiency and safety of operation of nuclear power plants'. 8 tabs., 129 figs.