Published August 1999
| Version v1
Report
Safety analysis of main coolant pump failure after I and C system upgrading. Rev. 1
Description
The situation in the event of failure of 3 from the 6 main coolant pumps which are active during Dukovany reactor unit operation at the full power level is analyzed with a view to identifying the effect of instrumentation and control (I and C) system upgrading by comparison with the same analysis performed in 1998. The conservatism of the analysis is aimed at the departure from nucleate boiling ratio. The I and C system upgrading was found to be beneficial because the DNBR criterion is met now even if the power limiter does not work and the hot channel factor is 1.83
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)
- Bezpecnostni analyza vypadku HCC po obnove SKR. Revize 1
- Augmented title (English)
- Dukovany NPP
Publishing Information
- Imprint Pagination
- [32 p.]
- Report number
- UJV--11256-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 31065762
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; COOLANTS; D CODES; DEPARTURE NUCLEATE BOILING; DESIGN BASIS ACCIDENTS; DUKOVANY-1 REACTOR; FAILURES; PRIMARY COOLANT CIRCUITS; PUMPS; REACTOR CONTROL SYSTEMS; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; BOILING; COMPUTER CODES; CONTROL SYSTEMS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 3 tabs., 21 figs., 19 refs.