Design and development of FPGA based simplified DNBR calculation algorithm for APR 1400 NPPs
•The simplified algorithm was developed by MATLAB and then converted to VHSIC Hardware Description Language (VHDL) code by using MATLAB HDL coder.•The complexity was measured using Hardware Description Language (HDL) resources that are required to implement the current and simplified algorithms.•Thi...
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| Published in: | Nuclear engineering and design Vol. 352; p. 110134 |
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| Main Authors: | , |
| Format: | Journal Article |
| Language: | English |
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Amsterdam
Elsevier B.V
01.10.2019
Elsevier BV |
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| ISSN: | 0029-5493, 1872-759X |
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| Abstract | •The simplified algorithm was developed by MATLAB and then converted to VHSIC Hardware Description Language (VHDL) code by using MATLAB HDL coder.•The complexity was measured using Hardware Description Language (HDL) resources that are required to implement the current and simplified algorithms.•This new approach can successfully reduce the HDL resources by 29.51% as average value for all HDL resources.
Nuclear Power Plant Instrumentation and Control Systems are beginning to move towards Field Programmable Gate Array (FPGA) applications. This paper presents a new, simplified Departure from Nucleate Boiling Ratio (DNBR) calculation algorithm for Advanced Power Reactor (APR 1400). This new approach was implemented using FPGA based system to replace the current Core Protection Calculator System (CPCS) which uses Programmable Logic Controller (PLC). Three channels modeling were used to predict the mass flux and enthalpy distributions in hot channel, rather than four channel modeling. The simplified algorithm was developed by MATLAB and then converted to VHSIC Hardware Description Language (VHDL) code by using MATLAB HDL coder. Minimum DNBR values were calculated at 100%, 75%, and 50% reactor power levels. The accuracy of DNBR calculation for this new approach was evaluated and verified by comparing the results with KEPCO E&C APR 1400 CPCS test facility. The complexity was measured using Hardware Description Language (HDL) resources that are required to implement the current and simplified algorithms. This new approach can successfully reduce the HDL resources by 29.51% as average value for all HDL resources. |
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| AbstractList | •The simplified algorithm was developed by MATLAB and then converted to VHSIC Hardware Description Language (VHDL) code by using MATLAB HDL coder.•The complexity was measured using Hardware Description Language (HDL) resources that are required to implement the current and simplified algorithms.•This new approach can successfully reduce the HDL resources by 29.51% as average value for all HDL resources.
Nuclear Power Plant Instrumentation and Control Systems are beginning to move towards Field Programmable Gate Array (FPGA) applications. This paper presents a new, simplified Departure from Nucleate Boiling Ratio (DNBR) calculation algorithm for Advanced Power Reactor (APR 1400). This new approach was implemented using FPGA based system to replace the current Core Protection Calculator System (CPCS) which uses Programmable Logic Controller (PLC). Three channels modeling were used to predict the mass flux and enthalpy distributions in hot channel, rather than four channel modeling. The simplified algorithm was developed by MATLAB and then converted to VHSIC Hardware Description Language (VHDL) code by using MATLAB HDL coder. Minimum DNBR values were calculated at 100%, 75%, and 50% reactor power levels. The accuracy of DNBR calculation for this new approach was evaluated and verified by comparing the results with KEPCO E&C APR 1400 CPCS test facility. The complexity was measured using Hardware Description Language (HDL) resources that are required to implement the current and simplified algorithms. This new approach can successfully reduce the HDL resources by 29.51% as average value for all HDL resources. Nuclear Power Plant Instrumentation and Control Systems are beginning to move towards Field Programmable Gate Array (FPGA) applications. This paper presents a new, simplified Departure from Nucleate Boiling Ratio (DNBR) calculation algorithm for Advanced Power Reactor (APR 1400). This new approach was implemented using FPGA based system to replace the current Core Protection Calculator System (CPCS) which uses Programmable Logic Controller (PLC). Three channels modeling were used to predict the mass flux and enthalpy distributions in hot channel, rather than four channel modeling. The simplified algorithm was developed by MATLAB and then converted to VHSIC Hardware Description Language (VHDL) code by using MATLAB HDL coder. Minimum DNBR values were calculated at 100%, 75%, and 50% reactor power levels. The accuracy of DNBR calculation for this new approach was evaluated and verified by comparing the results with KEPCO E&C APR 1400 CPCS test facility. The complexity was measured using Hardware Description Language (HDL) resources that are required to implement the current and simplified algorithms. This new approach can successfully reduce the HDL resources by 29.51% as average value for all HDL resources. |
| ArticleNumber | 110134 |
| Author | Jung, Jaechon Awad, Ibrahim Fathy |
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| References | Bickel (b0005) 2008 Pant, Bourai, Rana, Yadav (b0035) 2015 IAEA Nuclear Energy Series No. NP-t-3.17 (b0015) 2016 Bickel (10.1016/j.nucengdes.2019.05.030_b0005) 2008 IAEA Nuclear Energy Series No. NP-t-3.17 (10.1016/j.nucengdes.2019.05.030_b0015) 2016 Pant (10.1016/j.nucengdes.2019.05.030_b0035) 2015 |
| References_xml | – year: 2008 ident: b0005 article-title: Risk Implications of Digital Reactor Protection System Operating Experience – year: 2016 ident: b0015 article-title: Application of Field Programmable Gate Array in Instrumentation and publication-title: Control Syst. Nucl. Power Plants – year: 2015 ident: b0035 article-title: Conversion of MATLAB code in VHDL using HDL Coder & Implementation of Code on FPGA – year: 2016 ident: 10.1016/j.nucengdes.2019.05.030_b0015 article-title: Application of Field Programmable Gate Array in Instrumentation and publication-title: Control Syst. Nucl. Power Plants – year: 2015 ident: 10.1016/j.nucengdes.2019.05.030_b0035 – year: 2008 ident: 10.1016/j.nucengdes.2019.05.030_b0005 |
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| Snippet | •The simplified algorithm was developed by MATLAB and then converted to VHSIC Hardware Description Language (VHDL) code by using MATLAB HDL coder.•The... Nuclear Power Plant Instrumentation and Control Systems are beginning to move towards Field Programmable Gate Array (FPGA) applications. This paper presents a... |
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| SubjectTerms | Algorithms Control equipment Control systems Enthalpy Field programmable gate arrays Hardware description languages Instrumentation Language Matlab Modelling Nuclear energy Nuclear power plants Nucleate boiling Programmable calculators Programmable logic arrays Programmable logic controllers Reactors VHSIC (circuits) |
| Title | Design and development of FPGA based simplified DNBR calculation algorithm for APR 1400 NPPs |
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