Reliability analysis of digital reactor protection systems in floating nuclear power plants
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Xi-Wen Xie
Abstract
This paper presents a reliability model for digital reactor protection systems (RPSs) in floating nuclear power plants (FNPPs) that accounts for both the internal characteristics of RPS and the external environment. The internal characteristics of RPS include independent failures and common-cause failures (CCFs) of components, repair behavior, and actuation logic degradation. For the external environment, we incorporated a parts-pressure method and used the environmental factors to describe the impact of marine environment at component level. Detailed Monte Carlo simulation (MCS) algorithm was proposed to solve the reliability models with different environmental factors, and the results showed that the maximum value of the environmental factor was 3.2 under the requirements that the probability for RPS failing to generate the trip signal does not exceed 1 × 10−5 and the spurious trip frequency does not exceed one time per year. Reliability indexes, such as failure probability and spurious trip frequency, were also derived. The 90 % confidence intervals of these two indexes were further calculated in the uncertainty analysis by using the kernel density estimation (KDE) approach.
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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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Competing interests: The authors state no conflict of interest.
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Research funding: None declared.
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Data availability: The raw data can be obtained on request from the corresponding author.
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Articles in the same Issue
- Frontmatter
- Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor
- Comparison of modeling methods for the effective diffusivities of IO3− estimated in compacted bentonite using through-diffusion tests under aerobic conditions
- Analysis of initial core and time dependent fuel burnup for high temperature testing reactors (HTTRs)
- A detection and defense security system design for nuclear waste storage against stealth terrorists attack
- Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation
- Fuzzy reliability algorithm for the shutdown system of research reactor
- System theory safety analysis of network malfunction in nuclear power plant distributed control systems
- Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction
- Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE
- Reliability analysis of digital reactor protection systems in floating nuclear power plants
- Study on comprehensive evaluation method of mental workload level
- Integrating reliability analysis into MBSE for FPGA-based safety critical I&C system design in nuclear power plants
- Calendar of events
