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
Main Authors: Awad, Ibrahim Fathy, Jung, Jaechon
Format: Journal Article
Language:English
Published: 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.
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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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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StartPage 110134
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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