Dynamic approach for scenario quantification of combined event of internal flooding and earthquake in nuclear power plant
Description
The study aims to develop probabilistic risk assessment (PRA) methodology for the combination event of an earthquake and internal flooding. The seismic impact on the safety-related systems is taken into account by considering seismic fragility under various ground accelerations and implemented in a fault tree to evaluate failure probability of safety-related equipment. The internal flooding impact is considered by evaluating the probability of loss of safety function based on a calculation of water level in rooms where safety equipment is installed. The water level in each room is calculated by a flood propagation model. Based on the Markov process, the probability of loss of safety function in next time step is calculated based on current water level. Monte Carlo method is used to evaluate uncertainties in initial leak rate, and broken area of the water barrier. As a result, combined event of seismic and internal flooding is evaluated. A new methodology is a useful approach for quantification of interactive accident scenarios which consider event progression. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)
- Imprint Pagination
- 2573 p.
- Journal Page Range
- 7 p.
Conference
- Title
- 2017 international congress on advances in nuclear power plants
- Acronym
- ICAPP2017
- Dates
- 24-25 Apr 2017; 26-28 Apr 2017
- Place
- Fukui (JP); Kyoto (JP)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49033675
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONTAINMENT BUILDINGS; EARTHQUAKES; FAILURE MODE ANALYSIS; FEEDWATER; FLOODS; GROUND MOTION; MARKOV PROCESS; MASS BALANCE; MONTE CARLO METHOD; NUCLEAR POWER PLANTS; POWER SUPPLIES; PROBABILISTIC ESTIMATION; REACTOR CORES; REACTOR SAFETY; RISK ASSESSMENT; TURBINES
- Descriptors DEC
- BUILDINGS; CALCULATION METHODS; CONTAINMENT; ELECTRONIC EQUIPMENT; EQUIPMENT; HYDROGEN COMPOUNDS; MACHINERY; MOTION; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; REACTOR COMPONENTS; SAFETY; SEISMIC EVENTS; STOCHASTIC PROCESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; TURBOMACHINERY; WATER
Optional Information
- Notes
- Available as CD-ROM Data in PDF format. Folder Name: pdf; Paper ID: 17757.pdf; 8 refs., 13 figs., 3 tabs.