Published September 2000
| Version v1
Report
Thermal hydraulic analysis of a LOCA 200 mm equivalent leak hole diameter at the hot leg for PTS evaluation
Description
The analysis was performed for the Dukovany NPP with VVER-440/V-213 reactors. The accident analyzed can cause pressurized thermal shock of the reactor pressure vessel, primarily due to a strong Emergency Core Cooling System injection. The RELAP5 thermal hydraulic code and a 6-loop input model of the Dukovany NPP were used. The behavior of the hermetic compartment was calculated by means of the MELCOR code, whereas the 2D CATHARE code was employed to analyze the mixing in the reactor downcomer
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)
- Termohydraulicka analyza havarie s unikem chladiva z horke vetve s ekvivalentnim prumerem unikoveho otvoru 200 mm pro potreby PTS
- Augmented title (English)
- [Pressurized Thermal Shock. Dukovany NPP]
Publishing Information
- Imprint Pagination
- [163 p.]
- Report number
- UJV--11494-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 37002752
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- C CODES; COMPUTER CALCULATIONS; DUKOVANY-1 REACTOR; LOSS OF COOLANT; M CODES; R CODES; REACTOR ACCIDENTS; THERMAL HYDRAULICS; THERMAL SHOCK
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 4 tabs., 117 figs., 10 refs.