Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant
This work studied the feasibility of digitalizing the analog Ex-Core Neutron Flux Monitoring System (ENFMS) being used for APR1400 nuclear power plants (NPPs) and as to which strategies and steps must be taken. A fission chamber neutron flux detection and instrumentation model were designed. Its acc...
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| Format: | Article |
| Language: | English |
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MDPI AG
2020-11-01
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| Series: | Applied Sciences |
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| Online Access: | https://www.mdpi.com/2076-3417/10/23/8331 |
| _version_ | 1797546927426895872 |
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| author | Young Baik Kim Felipe P. Vista Seung Bin Cho Kil To Chong |
| author_facet | Young Baik Kim Felipe P. Vista Seung Bin Cho Kil To Chong |
| author_sort | Young Baik Kim |
| collection | DOAJ |
| description | This work studied the feasibility of digitalizing the analog Ex-Core Neutron Flux Monitoring System (ENFMS) being used for APR1400 nuclear power plants (NPPs) and as to which strategies and steps must be taken. A fission chamber neutron flux detection and instrumentation model were designed. Its accuracy was evaluated and proven by comparing the model data with data gathered from tests and plant operations. A conceptual design was proposed through a combined structure that digitalizes only part of the system. The detector signal pre-amplification remains in analog form while the other functions such as reactor power calculation as well as signal conditioning and processing will be digitalized. Simulations showed that the true mean squared voltage (MSV) of the digitalized ENFMS maintained a linear relationship between real and estimated reactor power in the wide range compared to averaged magnitude squared value of analog ENFMS. Extended Kalman Filter (EKF) was also utilized for estimating reactor power and reactor period from measurement signals that are contaminated with gamma ray interaction and electric noise. This study proved that the ENFMS can be successfully digitalized as proposed wherein all functional and performance requirements are satisfied. Simulations results demonstrated that the functions and performance can be improved through the use of digital processing algorithms such as EKF and MSV. |
| first_indexed | 2024-03-10T14:37:21Z |
| format | Article |
| id | doaj.art-d9e6e5d473a24c8eadd8d93fd049928f |
| institution | Directory Open Access Journal |
| issn | 2076-3417 |
| language | English |
| last_indexed | 2024-03-10T14:37:21Z |
| publishDate | 2020-11-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Applied Sciences |
| spelling | doaj.art-d9e6e5d473a24c8eadd8d93fd049928f2023-11-20T22:08:17ZengMDPI AGApplied Sciences2076-34172020-11-011023833110.3390/app10238331Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power PlantYoung Baik Kim0Felipe P. Vista1Seung Bin Cho2Kil To Chong3Electronic Engineering Department, Jeonbuk National University, Jeonju 54896, KoreaAdvanced Electronic Research Information Center, Jeonbuk National University, Jeonju 54896, KoreaElectronic Engineering Department, Jeonbuk National University, Jeonju 54896, KoreaElectronic Engineering Department, Jeonbuk National University, Jeonju 54896, KoreaThis work studied the feasibility of digitalizing the analog Ex-Core Neutron Flux Monitoring System (ENFMS) being used for APR1400 nuclear power plants (NPPs) and as to which strategies and steps must be taken. A fission chamber neutron flux detection and instrumentation model were designed. Its accuracy was evaluated and proven by comparing the model data with data gathered from tests and plant operations. A conceptual design was proposed through a combined structure that digitalizes only part of the system. The detector signal pre-amplification remains in analog form while the other functions such as reactor power calculation as well as signal conditioning and processing will be digitalized. Simulations showed that the true mean squared voltage (MSV) of the digitalized ENFMS maintained a linear relationship between real and estimated reactor power in the wide range compared to averaged magnitude squared value of analog ENFMS. Extended Kalman Filter (EKF) was also utilized for estimating reactor power and reactor period from measurement signals that are contaminated with gamma ray interaction and electric noise. This study proved that the ENFMS can be successfully digitalized as proposed wherein all functional and performance requirements are satisfied. Simulations results demonstrated that the functions and performance can be improved through the use of digital processing algorithms such as EKF and MSV.https://www.mdpi.com/2076-3417/10/23/8331Ex-core Neutron Flux Monitoring Systemnuclear power plantAPR1400extended Kalman filtermean squared voltage |
| spellingShingle | Young Baik Kim Felipe P. Vista Seung Bin Cho Kil To Chong Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant Applied Sciences Ex-core Neutron Flux Monitoring System nuclear power plant APR1400 extended Kalman filter mean squared voltage |
| title | Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant |
| title_full | Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant |
| title_fullStr | Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant |
| title_full_unstemmed | Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant |
| title_short | Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant |
| title_sort | digitalization of the ex core neutron flux monitoring system for apr1400 nuclear power plant |
| topic | Ex-core Neutron Flux Monitoring System nuclear power plant APR1400 extended Kalman filter mean squared voltage |
| url | https://www.mdpi.com/2076-3417/10/23/8331 |
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