Published December 1995
| Version v1
Report
Results of calculation of a ''rupture of several steam lines'' accident at a WWER-440/213 type NPP
Description
The calculation addresses the possibility of separating steam and feedwater leaks, the effect of reactor unit aftercooling, and impacts of the planned modification of the ''main steam header rupture'' signal. The core cooling was impaired in none of the cases analyzed. Where the secondary circuit fails completely, the primary circuit is aftercooled by spontaneous or controlled feed-and-bleed. A high safety margin was found by the calculation for the WWER-440/213 reactor. (M.D.). 327 figs., 6 refs
Availability note (English)
Available from Ustav jaderneho vyzkumu Rez, a.s., 250 68 Rez, Czech Republic.Additional details
Additional titles
- Original title (Czech)
- Vysledky vypoctu havarie s ''prasknutim vice parovodu'' JE s VVER-440/213
Publishing Information
- Imprint Pagination
- [462 p.].
- Report number
- UJV--10593-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 28064796
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data, Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; COOLING; DEPARTURE NUCLEATE BOILING; HEAT TRANSFER; R CODES; REACTOR ACCIDENTS; REACTOR CORES; RUPTURES; SAFETY ANALYSIS; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; THEORETICAL DATA; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BOILERS; BOILING; COMPUTER CODES; COOLING SYSTEMS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; INFORMATION; NUCLEATE BOILING; NUMERICAL DATA; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS