Published December 1996
| Version v1
Report
Major LOCA and steam generator pipe break. Thermal-hydraulic and supporting analyses
Description
The thermohydraulic analyses were aimed at determining the maximum pressures in the system of location of a combined accident. The probability of steam generator pipe break during the rupture of the main circulation piping and the probability of a simultaneous occurrence of initiation events of the two accidents were estimated. The resulting frequency of a simultaneous occurrence is 10-9. The RELAP5 and MELCOR codes were used for the calculation. (M.D.)
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech RepublicAdditional details
Additional titles
- Original title (Czech)
- Velka LOCA a prasknuti trubky PG. Termohydraulicke a podpurne analyzy
Publishing Information
- Imprint Pagination
- [204 p.]
- Report number
- UJV--10834-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 30020694
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- DUKOVANY-1 REACTOR; LOSS OF COOLANT; M CODES; MATHEMATICAL MODELS; PIPES; PRESSURE SUPPRESSION; PROBABILITY; R CODES; RUPTURES; SAFETY ANALYSIS; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 12 tabs., 218 figs., 11 refs.