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Application of FPGA to Nuclear Power Plant I&C Systems

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Abstract

This paper presents a Field Programmable Gate Array (FPGA) application for nuclear power plants, and introduces Toshiba FPGA-based Instrumentation and Control (I&C) systems as typical examples. An FPGA is a semiconductor device including more than thousands of logic gates which can be connected to constitute application specific circuits. A notable feature of FPGA is its simplicity. Thanks to this feature, several companies including Toshiba have developed FPGA based-systems for nuclear power plants recently. The simplicity of FPGAs is one of the most notable advantages to provide cost-effective options for I&C systems, ensuring reliable and safe operation of nuclear power plants.

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References

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Acknowledgement

The authors would like to acknowledge engineers of Toshiba who are working for FPGA-based I&C systems.

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Correspondence to Toshifumi Hayashi .

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Nomenclatures

Nomenclatures

ABWR:

Advanced Boiling Water Reactor

ALS:

Advanced Logic System

APRM:

Average Power Range Monitor

ASIC:

Application Specific Integrated Circuit

D/W:

Drywell

DTF:

Digital Trip Function

EdF:

Électricité de France

EEPROM:

Electrically Erasable Programmable Read-Only Memory

EFT/B:

Electrical Fast Transient/Burst

EMC:

Electromagnetic Compatibility

EMI/RFI:

Electromagnetic Interference/Radio-Frequency Interference

EPRI:

Electric Power Research Institute

EQ:

Equipment Qualification

ESD:

Electrostatic Discharge

ESFAS:

Engineering Safety Features Actuation System

FE:

Functional element

FPGA:

Field Programmable Gate Array

HMI:

Human Machine Interface

I&C:

Instrumentation and Control

IEC:

International Electrotechnical Commission

LD:

Load Driver

LPRM:

Local Power Range Monitor

MSFIS:

Main Steam and Feedwater Isolation System

NMS:

Neutron Monitoring System

NPP:

Nuclear power plant

OLU:

Output Logic Unit

PLA:

Programmable Logic Array

PLC:

Programmable Logic Controller

PRNM:

Power Range Neutron Monitor

RMCPS:

Automatic Regulation, Monitoring, Control, and Protection System for Research Reactors

RPCLS:

Reactor Power Control and Limitation System

RPS:

Reactor Protection System

RTIS:

Reactor Trip and Isolation System

RTS:

Reactor Trip System

SEU:

Single event upsets

SPTM:

Suppression Pool Temperature Monitoring Calculation

SRAM:

Static Random Access Memory

SSLC:

Safety System Logic and Control

TC:

Technical Committee

TIP:

Traverse in-core probe

TLF:

Trip Logic Function

USNRC:

United States Nuclear Regulatory Commission

V&V:

Verification and validation

VHDL:

VHSIC (Very High Speed Integrated Circuit) Hardware Description Language

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Hayashi, T., Kojima, A., Miyazaki, T., Oda, N., Wakita, K., Furusawa, T. (2014). Application of FPGA to Nuclear Power Plant I&C Systems. In: Yoshikawa, H., Zhang, Z. (eds) Progress of Nuclear Safety for Symbiosis and Sustainability. Springer, Tokyo. https://doi.org/10.1007/978-4-431-54610-8_5

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  • DOI: https://doi.org/10.1007/978-4-431-54610-8_5

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  • Publisher Name: Springer, Tokyo

  • Print ISBN: 978-4-431-54609-2

  • Online ISBN: 978-4-431-54610-8

  • eBook Packages: EnergyEnergy (R0)

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