Safety analysis for integrity enhancement in nuclear power plants (NPPs) in case of seashore region site
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Tae Ho Woo
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Chang Hyun Baek
Abstract
It is investigated for the seismic consequences in the nuclear power plant (NPP) where the radiological hazard could be one of critical issues when the safety system is in failure. The artificial learning is done during the calculations of each time step. There are the simulations for the artificial neural networking (ANN) as the precision, sensitivity (recall value), specificity, and accuracy which are 21.48%, 50.53%, 25.47%, and 32.68% respectively. Likewise, the recurrent neural network (RNN) modeling has 23.64%, 54.53%, 25.56%, and 34.17% respectively. In the comparisons for ANN and RNN, the values of ANN’s parameters are lower than those of RNN in all values of precision, recall, specificity, and accuracy. As the designed factors for the nuclear matters increase, the estimations could be better in considering the conditional situations.
Funding source: The Cyber University of Korea
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: This study was supported by a grant of the Cyber University of Korea.
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Conflict of interest statement: The author(s) declared no potential conflicts of interest with respect to the research, authorship, and/or publication of this article.
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- Calendar of events
Articles in the same Issue
- Frontmatter
- A study of RCS depressurization strategy of CPR1000 SAMG
- Drones application scenarios in a nuclear or radiological emergency
- Safety analysis for integrity enhancement in nuclear power plants (NPPs) in case of seashore region site
- Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor
- Improving FNMC for the matrix effect of spherical shell plutonium samples
- Calculation of core neutronic parameters in electron accelerator driven subcritical TRIGA reactor
- Preliminary study on TRU transmutation in VVER-1000 fuel assembly using MCNP6
- Research on the application of 22Na radiolocation detection technology in advanced manufacturing process control
- Coupling MCNP6/ANSYS codes to calculate axial temperature and power distribution in a VVER-1000 fuel assembly
- Experimental and theoretical investigation of forced convection heat transfer with CNTs and CuO water based nano-fluids
- Thermal hydraulic characteristics of silicon irradiation in a typical MTR reactor
- Photon dosimetry using selective data sampling with Particle Swarm optimization algorithm based on NaI(Tl) scintillation detector
- Calendar of events
