scholarly journals Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Yankee Rowe nuclear power plant

1979 ◽  
Author(s):  
V.R. Latorre ◽  
B.G. Mayn
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Low Temperature ◽  
Nuclear Power ◽  
Control Design ◽  
Protection System ◽  
Technical Evaluation ◽  
And Control

Overview on the Design Approach for the CVCS I & C of the EPR™ Nuclear Power Plant in Taishan

2013 ◽  
Author(s):  
Antonio Ciriello ◽  
Daniela Kohler ◽  
Terry Morton ◽  
Thomas Lang
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Engineering Design ◽  
Nuclear Power ◽  
Control Design ◽  
Volume Control ◽  
Functional Safety ◽  
Control Loop ◽  
And Control

The I & C (Instrumentation and Control) design of the CVCS (Chemical and Volume Control System) for the EPR™ nuclear power plant in Taishan (TSN NPP) is shortly introduced and the corresponding I & C module assignment procedure, according to the functional safety class principle, is described. An example of the I & C module assignment procedure is given for a control loop of the CVCS. In addition, the corresponding advantages and drawbacks are described and discussed. The approach described introduces a new method for the concerned I & C design by improving the interface between the system, process, and I & C engineering design. In fact, a fruitful collaboration was reached between the system and I & C design for the EPR™ project in Taishan, for the concerned interface.

Overview on the Standard Requirements for the Separation Measures and Practical Implementation in the I&C Design: Return of Experience

2016 ◽  
Author(s):  
Antonio Ciriello ◽  
Stefan Kümmerling ◽  
Johannes Pickelmann
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Control Design ◽  
Design Approach ◽  
Practical Implementation ◽  
Future Scenarios ◽  
Short Overview ◽  
Technical Solutions ◽  
And Control

After giving a short overview about the published instrumentation and control standards worldwide with regard to the separation measures, as released by the different safety authorities, this paper provides a first assessment of the different needs and requirements to be considered in the frame of separation measures which are to be implemented in the instrumentation and control design. According to this analysis the corresponding design aspects and features are derived and analyzed. The experience gained both in nuclear power plant modernization projects and new builds show that there are margins both for interpretation possibilities and for possible technical solutions, which can be proposed to the customer in order to fulfill the concerned standards. A conclusion about the design approach and solutions as well as possible future scenarios is given.

scholarly journals Dynamic modelling, simulation, and control design of a pressurized water-type nuclear power plant

2020 ◽  
Vol 370 ◽  
pp. 110901 ◽  
Author(s):  
Vineet Vajpayee ◽  
Victor Becerra ◽  
Nils Bausch ◽  
Jiamei Deng ◽  
S.R. Shimjith ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Dynamic Modelling ◽  
Control Design ◽  
Water Type ◽  
Pressurized Water ◽  
Simulation And Control ◽  
And Control ◽  
Modelling Simulation

Design of the Communication Independence for ACPR1000 Nuclear Power Plant Digital Safety I&C System

2017 ◽  
Author(s):  
Sun Na ◽  
Shi Gui-lian ◽  
Xie Yi-qin ◽  
Li Gang ◽  
Jiang Guo-jin
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Communication Networks ◽  
Nuclear Power ◽  
Protection System ◽  
Plant Safety ◽  
Safety And Reliability ◽  
Digital Protection ◽  
Architecture And Design ◽  
Reactor Protection System

Communication independence is one of the key criteria of digital safety I&C system design. This paper mainly analyzes the requirements for communication independence in safety regulations and standards, and then introduces the architecture and design features, including communication failure processing measures, of communication networks of ACPR1000 nuclear power plant safety digital protection system based on FirmSys platform developed by CTEC. The communication design meets the regulations requirements and effectively improves the safety and reliability of the system, and it is successfully applied in reactor protection system (RPS) of Yang Jiang nuclear power plant unit 5&6. In addition this design can provide reference for communication designs of other NPPs and industries.

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