Development of neutron flux measurement module for research reactors based on FPGA. Part-1-Model development and generic verification
Many Instrumentation and Control (I&C) systems of Research reactors experience aging difficulties that necessitate optimizing operations and safety systems. Therefore, great attention paid to FPGA-based I&C use particularly in safety systems; this is due to the FPGAs' notable simplicity...
| Main Authors: | , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2020-12-01
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| Series: | Alexandria Engineering Journal |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1110016820303367 |
| _version_ | 1818663270845775872 |
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| author | Mjzoob I. Ibrahim Magdy M. Zaky Mohamed H. Hassan Mohammad Nagy |
| author_facet | Mjzoob I. Ibrahim Magdy M. Zaky Mohamed H. Hassan Mohammad Nagy |
| author_sort | Mjzoob I. Ibrahim |
| collection | DOAJ |
| description | Many Instrumentation and Control (I&C) systems of Research reactors experience aging difficulties that necessitate optimizing operations and safety systems. Therefore, great attention paid to FPGA-based I&C use particularly in safety systems; this is due to the FPGAs' notable simplicity and advantages. This work aims to develop a prototype FPGA-Based Nuclear Instrumentation Module to use it as part of the nuclear instrumentation of Egypt Second Research Reactor (ETRR-2) based on Zynq-7000 FPGA. This phase focusses on using a model-based design approach for FPGA customization by the Xilinx system generator tool, with embedded MATLAB/Simulink to implement the neutron flux parameter algorithms. Thus, a model of Digital Neutron Flux Module (DNFM) developed to digitize the neutron flux as obtained from the processed signal of the Compensated Ionization Chamber (CIC). Substantial quantities of the neutron flux of the ETRR-2 operating power range calculated. The amounts include the neutron flux in the logarithmic range, the reactor power as a percentage of the full power in the linear range and the rate of change of the neutron flux. Generic verification got done using simulated current signals, followed by direct verification methods using real ETRR-2's CIC output current signal. The results of the FPGA-based DNFM model is consistent with the ETRR-2's neutron flux measurements. |
| first_indexed | 2024-12-17T05:14:11Z |
| format | Article |
| id | doaj.art-07828b42ca234281a5501a2eb4740675 |
| institution | Directory Open Access Journal |
| issn | 1110-0168 |
| language | English |
| last_indexed | 2024-12-17T05:14:11Z |
| publishDate | 2020-12-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Alexandria Engineering Journal |
| spelling | doaj.art-07828b42ca234281a5501a2eb47406752022-12-21T22:02:10ZengElsevierAlexandria Engineering Journal1110-01682020-12-0159641074120Development of neutron flux measurement module for research reactors based on FPGA. Part-1-Model development and generic verificationMjzoob I. Ibrahim0Magdy M. Zaky1Mohamed H. Hassan2Mohammad Nagy3Nuclear and Radiation Engineering Department, Alexandria University, Alexandria 21544, Egypt; Corresponding author at: Nuclear and Radiation Engineering Department, Alexandria University, Alexandria 21544, Egypt.ETRR-2, Egyptian Atomic Energy Authority (EAEA), Abou Zabal 13759, EgyptNuclear and Radiation Engineering Department, Alexandria University, Alexandria 21544, EgyptNuclear and Radiation Engineering Department, Alexandria University, Alexandria 21544, EgyptMany Instrumentation and Control (I&C) systems of Research reactors experience aging difficulties that necessitate optimizing operations and safety systems. Therefore, great attention paid to FPGA-based I&C use particularly in safety systems; this is due to the FPGAs' notable simplicity and advantages. This work aims to develop a prototype FPGA-Based Nuclear Instrumentation Module to use it as part of the nuclear instrumentation of Egypt Second Research Reactor (ETRR-2) based on Zynq-7000 FPGA. This phase focusses on using a model-based design approach for FPGA customization by the Xilinx system generator tool, with embedded MATLAB/Simulink to implement the neutron flux parameter algorithms. Thus, a model of Digital Neutron Flux Module (DNFM) developed to digitize the neutron flux as obtained from the processed signal of the Compensated Ionization Chamber (CIC). Substantial quantities of the neutron flux of the ETRR-2 operating power range calculated. The amounts include the neutron flux in the logarithmic range, the reactor power as a percentage of the full power in the linear range and the rate of change of the neutron flux. Generic verification got done using simulated current signals, followed by direct verification methods using real ETRR-2's CIC output current signal. The results of the FPGA-based DNFM model is consistent with the ETRR-2's neutron flux measurements.http://www.sciencedirect.com/science/article/pii/S1110016820303367Neutron flux monitoringResearch reactorETRR-2Nuclear instrumentationFPGAZynq-7000 |
| spellingShingle | Mjzoob I. Ibrahim Magdy M. Zaky Mohamed H. Hassan Mohammad Nagy Development of neutron flux measurement module for research reactors based on FPGA. Part-1-Model development and generic verification Alexandria Engineering Journal Neutron flux monitoring Research reactor ETRR-2 Nuclear instrumentation FPGA Zynq-7000 |
| title | Development of neutron flux measurement module for research reactors based on FPGA. Part-1-Model development and generic verification |
| title_full | Development of neutron flux measurement module for research reactors based on FPGA. Part-1-Model development and generic verification |
| title_fullStr | Development of neutron flux measurement module for research reactors based on FPGA. Part-1-Model development and generic verification |
| title_full_unstemmed | Development of neutron flux measurement module for research reactors based on FPGA. Part-1-Model development and generic verification |
| title_short | Development of neutron flux measurement module for research reactors based on FPGA. Part-1-Model development and generic verification |
| title_sort | development of neutron flux measurement module for research reactors based on fpga part 1 model development and generic verification |
| topic | Neutron flux monitoring Research reactor ETRR-2 Nuclear instrumentation FPGA Zynq-7000 |
| url | http://www.sciencedirect.com/science/article/pii/S1110016820303367 |
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