Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)
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Kyung Bae Jang
Abstract
Nuclear terrorism is studied by the complex algorithm with Analytic Hierarchy Process (AHP) and neural networking method. For the modeling, the modified crisis response is incorporated with the AHP level structure of five detections. It is applied to select the nine ranks with an input layer, hidden layer, and output layer in a neural networking algorithm containing the operator’s thinking. For 60 years, the range of the secure operation is between 0.01972 in the 18th year and 0.02099 in the 41st year, which means the highest range of security is about 1.064 times higher than that of the lowest value in this study. For the graphics, the highest and lowest values are seen as detection #5 and #1 respectively. The five sites differ in a dynamic manner where the #5 site is more than that of #1. This anti-terrorism study could be applied to energy or chemical plants in the future.
Funding source: National Research Foundation of Korea (NRF)
Award Identifier / Grant number: 2022M2B5A108069611
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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 the National Research Foundation of Korea (NRF) grant funded by the Korea Ministry of Science and ICT (2022M2B5A108069611).
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Conflict of interest statement: The authors declared no potential conflicts of interest with respect to the research, authorship, and/or publication of this article.
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Articles in the same Issue
- Frontmatter
- Effect of engraved concentric circles on pool boiling of water
- Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method
- Effect of metal layer height on heat transfer inside molten pool
- Transient analysis of MTR research reactor during fast and slow loss of flow accident
- Determination of heat flux leading to the onset of flow instability in MTR reactors
- Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water
- Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code
- Computational fluid dynamics simulation of material testing reactor spent fuel cooling in wet storage
- The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses
- Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA
- Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)
- Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor
- Calendar of events
