Implications of Extension of Station Blackout Cooping Capability on Nuclear Power Plant Safety
Creators
- 1. Jozef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia)
Description
The safety of the nuclear power plant depends on the availability of the continuous and reliable sources of electrical energy during all modes of operation of the plant. The station blackout corresponds to a total loss of all alternate current (AC) power as a result of complete failure of both offsite and on-site AC power sources. The electricity for the essential systems during station blackout is provided from the batteries installed in the nuclear power plant. The results of the probabilistic safety assessment show that station blackout is one of the main and frequently the dominant contributor to the core damage frequency. Results of the analysis of the implications of the strengthening of the SBO mitigation capability on safety of the NPP will be presented. The assessment is done with state-of-art deterministic and probabilistic methods and tolls with application on reference models of nuclear power plants. The safety analysis is done on reference model of the nuclear power plant. Obtained results show large decrease of the core damage frequency with strengthening of the station blackout mitigation capability. The time extension of blackout coping capability results in the delay of the core heat up for at least the extension time interval. Availability and operation of the steam driven auxiliary feedwater system maintains core integrity up to 72 h after the successful shutdown, even in the presence of the reactor coolant pumps seal leakage. The largest weighted decrease of the core damage frequency considering the costs for the modification is obtained for the modification resulting in extension of the station blackout coping capability. The importance of the common cause failures of the emergency diesel generators for the obtained decrease of the core damage frequency and overall safety of the plant is identified in the obtained results. (authors)
Files
46066613.pdf
Files
(1.8 MB)
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Additional details
Publishing Information
- Imprint Title
- Robustness of Electrical Systems of Nuclear Power Plants in Light of the Fukushima Daiichi Accident (ROBELSYS). Workshop Proceedings, Paris, France, 1-4 April 2014 - Robustness of Electrical Systems of NPP's in Light of the Fukushima Daiichi Accident. ROBELSYS Workshop Proceedings
- Imprint Pagination
- 394 p.
- Journal Page Range
- p. 147-176
- Report number
- NEA-CSNI-R--2015-4
Conference
- Title
- ROBELSYS Workshop on the Robustness of Electrical Systems of NPP's in Light of the Fukushima Daiichi Accident
- Dates
- 1-4 Apr 2014
- Place
- Paris (France)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 46066613
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Quality check status
- Yes
- Descriptors DEI
- AC SYSTEMS; COMPUTERIZED SIMULATION; DETERMINISTIC ESTIMATION; ELECTRIC GENERATORS; ELECTRICAL TRANSIENTS; EMERGENCY PLANS; FAILURE MODE ANALYSIS; LOSS OF COOLANT; MITIGATION; OUTAGES; POWER SUPPLIES; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; R CODES; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RISK ASSESSMENT; SAFETY ANALYSIS; SAFETY MARGINS;
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; COOLING SYSTEMS; ELECTRICAL EQUIPMENT; ELECTRONIC EQUIPMENT; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; POWER REACTORS; POWER SYSTEMS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; TRANSIENTS; VOLTAGE DROP; WATER COOLED REACTORS; WATER MODERATED REACTORS;
Optional Information
- Lead record
- nh5cc-h1212
- Notes
- 14 refs.