Analyses of the unavailability dynamics of emergency core cooling system
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Mita Farcasiu
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Cristina Constantinescu
Abstract
The Probabilistic Safety Assessment (PSA) studies can be used to evaluate the time-dependence of the safety systems availability. The purpose of this work is to analyze the unavailability dynamics of the Emergency Core Cooling System (ECCS). Using the PSA methodology, the ECCS was modeled. In order to show how the unavailability of the system varies as function of time (mission time, test interval and component ageing), sensitivity analyses are carried out. Following these analyses, polynomial functions of ECCS unavailability as function of time have been obtained. These functions allow to estimate the unavailability without modelling other ECCS fault trees being a simplified estimation of the system unavailability. In the same time, taking into account that the ECCS unavailability must be less than 10−2, the best time variations can be established to have the unavailability complied with this criterion. Also, the best time variations could be similarly established for any safety systems having the unavailability less than 10−3.
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Research ethics: Not applicable.
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Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission.
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Conflict of interest statement: The authors state no conflict of interest.
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Research funding: None declared.
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Data availability: Not applicable.
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Artikel in diesem Heft
- Frontmatter
- Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code
- Analyses of the unavailability dynamics of emergency core cooling system
- Study on spent fuel heatup during spent fuel pool complete loss of coolant accident
- Numerical simulation analysis of high-temperature bent sodium heat pipes
- Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger
- Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
- Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators
- Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant
- Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor
- A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis
- CTAB modification bentonite for enhanced Re adsorption and diffusion suppression
- Study on advection–dispersion behavior for simulation of 3H, 99Tc, and 90Sr transport in crushed sandstone of column experiments
- Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering
- Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code
- Analyses of the unavailability dynamics of emergency core cooling system
- Study on spent fuel heatup during spent fuel pool complete loss of coolant accident
- Numerical simulation analysis of high-temperature bent sodium heat pipes
- Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger
- Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
- Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators
- Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant
- Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor
- A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis
- CTAB modification bentonite for enhanced Re adsorption and diffusion suppression
- Study on advection–dispersion behavior for simulation of 3H, 99Tc, and 90Sr transport in crushed sandstone of column experiments
- Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering
- Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production
- Calendar of events
