Reliability Modeling and Analysis of Digital Reactor Protection System in Nuclear Power Plant

Author(s):  
Wei Zhang
Author(s):  
Sun Na ◽  
Shi Gui-lian ◽  
Xie Yi-qin ◽  
Li Gang ◽  
Jiang Guo-jin

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.


Author(s):  
Huasheng Xiong ◽  
Duo Li ◽  
Liangju Zhang

Reactor protection system is one of the most important safety systems in nuclear power plant and shall be designed with very high reliability. Digital computer-based Reactor Protection System (RPS) takes great advantages over its conventional counterpart based on analog technique and faces the issues how to effectively demonstrate and confirm the completeness and correctness of the software that performs reactor safety functions in the same time. It is commonly accepted that the essential way to solve safety software issues in a digital RPS is to pass a strict and independent Verification and Validation (V&V) process, in which integrated RPS testing play an important role to form a part of the overall system validation. Integrated RPS testing must be carried out rigorously before the system is delivered to nuclear power plant. The integrated testing are often combined with the factory acceptance test (FAT) to form a single testing activity, during which the RPS is excited by emulated static and dynamic input signals. The integration testing should simulate normal operation, anticipated operational occurrences and accident conditions, as well as anticipated faults on the inputs to the DRPS such as sensors out of range or ambiguous input readings. All safety function requirements of digital RPS should be confirmed by representative testing. The design and development of a test facility to carry out the integrated RPS testing are covered in this paper, which is merged in the research on a digital RPS engineering prototype for a nuclear power plant. The test facility is based on PXI platform and LabVIEW software development environment and its architecture design also takes into account the test functions future extensions such as hardware upgrades and software modules enhancement. The test facility provides the digital RPS with redundant, synchronized and multi-channel emulated signals that are produced to emulate all protection signals from 1E class sensors and transmitters with time varied value within their possible ranges, which would put integrated RPS testing into practice to confirm the digital RPS has fully met its predefined safety functionality requirements. The designed test facility can provide an independent verification and validation process for the research of digital RPS with scientific methods and authentic data to evaluate the RPS performance thoroughly and effectively, such as measuring threshold precision and trip response time, analyzing system statistical reliability and so on.


Author(s):  
Youngsun Jang ◽  
Taeyoung Kim ◽  
Jongbo Lee ◽  
Jonghak Kim

This study is a part of research project ‘the practicality of the 3-D Full Model in the SSI (Soil-Structure Interaction) Analysis on the Nuclear Power Plant’ from June 2006 to May 2009. The purpose of the project is getting advanced and more accurate results with the practicality of Full Model SSI analysis. The SSI analyses of the NPP were being performed for the APR1400 (Advanced Power Reactor 1400MWe) design because the APR1400 was developed as a Standard NPP concept enveloping suitable soil conditions. The soil properties of SSI analyses were from lower bound characteristics to firm condition. The Standard NPP that was developed in early 1990 had the rigid foundation assumption because rigid mat had many advantages, simple modeling and quick calculation. But this assumption may create licensing issue because the rigid mat could include uncertainties in the modeling and analysis procedure. Now, the advanced computing capacities can offer the calculating environment using Full Model in the SSI analysis, and through this study the Full Model SSI analysis may be applied to the NI (Nuclear Island) of APR1400. The full modeling concept can be distinguished into two methods. First one is the Full Model about excavated soil part below the ground surface only, the super structures can be beam sticks. Another modeling is the Full Model about excavated soil part below ground surface together with the super structure. Finally, the Full Model of excavated soil part with the super structure was built, each structure of the Full Model was verified.


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