The thesis researches the safety infonnation and control system （SICS） design principle and introduces engineering application in CPR1000 nuclear power station in China. The SICS provides sufficient control and moni...The thesis researches the safety infonnation and control system （SICS） design principle and introduces engineering application in CPR1000 nuclear power station in China. The SICS provides sufficient control and monitoring means to bring and maintain the plant in a safe state as a backup of main computerized control mean （MCM）, in any plant conditions that are probable during a planed or unplanned unavailability of the MCM. The successful engineering applications of SICS in different digital I＆C system platform are introduced in the paper. The thesis gives the research conclusion for new general SICS of digital I＆C system.展开更多
Nuclear industries have faced the unfavorable circumstance such as components obsolescence and aging of instrumentation and control system, therefore, nuclear society is striving to resolve this issue fundamentally. V...Nuclear industries have faced the unfavorable circumstance such as components obsolescence and aging of instrumentation and control system, therefore, nuclear society is striving to resolve this issue fundamentally. Various studies have been conducted to address components obsolescence of instrumentation and control system. Intuitively FPGA （field programmable gate arrays） technology is replacing the high level of micro-processor type equipped with various software and hardware which causes acceleration of the aging and obsolescence in I ＆ C （instrumentation and control） system in nuclear power plants. FPGAs are highlighted as an alternative means for obsolete control systems. When engineers design the control system of NPPs （nuclear power plants） with FPGAs, it is important to meet the system development life cycles and conduct the verification and validation activities regarding to FPGA-based applications for use in NPPs. Because the verification and validation process is more important than the design process, engineer should consider the characteristics of FPGA, HDL （hardware description language） programming, faults mode, and optimization technique. And also these characteristics should be reflected in verification and validation activities. As a minimum requirement, system designers require that HDL-programmed applications should be developed in accordance with system development life cycle and HPD design process. In the verification and validation processes, a review, test, and analysis activities should be properly conducted.展开更多
To achieve excellent production capability and maintain high security for nuclear power stations, equipment reliability is studied as a key issue. As the main branch, equipment reliability management is considered as ...To achieve excellent production capability and maintain high security for nuclear power stations, equipment reliability is studied as a key issue. As the main branch, equipment reliability management is considered as an effective approach to make plant management strategy and organize routine work. Some achievements on research and application of equipment reliability management at Daya Bay Nuclear Power Station are introduced in this paper. By studying and implementing 1NPO （Institute of Nuclear Power Operations） AP-913 equipment reliability process, reliability-centered maintenance （RCM）, critical component management （CCM）, and many other similar methods, equipment reliability management system has been established at Daya Bay. And by continuous effort on improving application effect of these technologies, some innovation has also been made. Some innovative products, such as iSOM Intelligent Expert System, reliability and technique centered maintenance （RtCM）, predictive maintenance system （PdM）, and so on, have been developed. Based on these achievements, Daya Bay Nuclear Power Station has achieved excellent operation performance and won several prizes in WANO （World Association of Nuclear Operators） competition every year.展开更多
文摘The thesis researches the safety infonnation and control system （SICS） design principle and introduces engineering application in CPR1000 nuclear power station in China. The SICS provides sufficient control and monitoring means to bring and maintain the plant in a safe state as a backup of main computerized control mean （MCM）, in any plant conditions that are probable during a planed or unplanned unavailability of the MCM. The successful engineering applications of SICS in different digital I＆C system platform are introduced in the paper. The thesis gives the research conclusion for new general SICS of digital I＆C system.
文摘Nuclear industries have faced the unfavorable circumstance such as components obsolescence and aging of instrumentation and control system, therefore, nuclear society is striving to resolve this issue fundamentally. Various studies have been conducted to address components obsolescence of instrumentation and control system. Intuitively FPGA （field programmable gate arrays） technology is replacing the high level of micro-processor type equipped with various software and hardware which causes acceleration of the aging and obsolescence in I ＆ C （instrumentation and control） system in nuclear power plants. FPGAs are highlighted as an alternative means for obsolete control systems. When engineers design the control system of NPPs （nuclear power plants） with FPGAs, it is important to meet the system development life cycles and conduct the verification and validation activities regarding to FPGA-based applications for use in NPPs. Because the verification and validation process is more important than the design process, engineer should consider the characteristics of FPGA, HDL （hardware description language） programming, faults mode, and optimization technique. And also these characteristics should be reflected in verification and validation activities. As a minimum requirement, system designers require that HDL-programmed applications should be developed in accordance with system development life cycle and HPD design process. In the verification and validation processes, a review, test, and analysis activities should be properly conducted.
文摘To achieve excellent production capability and maintain high security for nuclear power stations, equipment reliability is studied as a key issue. As the main branch, equipment reliability management is considered as an effective approach to make plant management strategy and organize routine work. Some achievements on research and application of equipment reliability management at Daya Bay Nuclear Power Station are introduced in this paper. By studying and implementing 1NPO （Institute of Nuclear Power Operations） AP-913 equipment reliability process, reliability-centered maintenance （RCM）, critical component management （CCM）, and many other similar methods, equipment reliability management system has been established at Daya Bay. And by continuous effort on improving application effect of these technologies, some innovation has also been made. Some innovative products, such as iSOM Intelligent Expert System, reliability and technique centered maintenance （RtCM）, predictive maintenance system （PdM）, and so on, have been developed. Based on these achievements, Daya Bay Nuclear Power Station has achieved excellent operation performance and won several prizes in WANO （World Association of Nuclear Operators） competition every year.
