Test Facility Design for Integrated Digital Nuclear Reactor Protection System

2010 ◽  
Author(s):  
Huasheng Xiong ◽  
Duo Li ◽  
Liangju Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Verification And Validation ◽  
Protection System ◽  
Normal Operation ◽  
Test Facility ◽  
Acceptance Test ◽  
Independent Verification ◽  
Reactor Protection System

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.

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.

I&C Integrated Test Phase of the Mochovce Nuclear Power Plant, Units 3 and 4

2014 ◽  
Author(s):  
Antonio Ciriello ◽  
Stefan Kümmerling
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Slovak Republic ◽  
Reactor Power ◽  
Test Phase ◽  
Acceptance Test ◽  
Safety Systems ◽  
And Control ◽  
Reactor Protection System

This paper briefly introduces the safety instrumentation and control (I&C) system (Teleperm® XS) designed for the nuclear power plant in Mochovce units 3 and 4 (Slovak Republic). The overall I&C architecture of the concerned nuclear power plant is shortly introduced as well. An overview is given on the different test phases for the hardware and software I&C modules. The integrated I&C test concept and its implementation is presented as well as the description of the integrated test phase in the test bay in Erlangen (Germany). After a successful completion of the integrated test phase for unit 3, the Factory Acceptance Test (FAT) and the erection phase have been started for the concerned I&C safety systems (e.g., the Reactor Protection System and the Reactor Power Limitation System). This paper will also present the significant advantages and specifics of performing the concerned I&C tests in the aforementioned test bay.

Applying Engineering Simulator to Verification and Validation of Digital I&C in Nuclear Power Plant

2009 ◽  
Author(s):  
Meng Lin ◽  
Zongwei Yang ◽  
Dong Hou ◽  
Pengfei Liu
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Water Level ◽  
Control Systems ◽  
Nuclear Power ◽  
Verification And Validation ◽  
Level Control ◽  
Actuation System ◽  
Reactor Protection System

In China, more and more Nuclear Power Plant (NPP) will be constructed in the near future years, and Main Control Room (MCR) will introduce digital Instrumentation and Controls systems (I&C) technique. I&C system of nuclear power plant consists of Control Systems, Reactor Protection System and Engineered Safety Feature (ESF) Actuation System. For example, I&C system of LinAo Phase II NPP has adopted SIEMENS TXP and TXS I&C, which is being constructed in Guangdong province, China. In this engineering project, Chinese engineers are responsible for all the configuration of actual analog and logic diagram. Before the phase of real plant testing on the reactor, engineers want to make sure that configuration is right and control functions can be accomplished, so primary Verification and Validation (V&V) of I&C works were done. One way is checking the diagram configuration one by one according to the original design. There are two main disadvantages. One is diagram is so complex that workload is very large and engineers will make mistake. Another is even engineers have read every logic, but they still cannot know the final results and function of a complex control system. So another effective V&V way is applying NPP engineering simulator to do virtual test. According to LinAo Phase II NPP design, we develop one simulator to construct a virtual NPP model as a basis, which can provide plant operation parameters and can also accept control signal from I&C, then give response to it. Through this way, we don’t need to know the exact diagram, and just observe input and output of I&C to make sure that the final results is right and functions have been accomplished. In this way, it is need to transfer signals between simulator and I&C. For keeping the original software and hardware structures of SIEMENS Distributed Control System (DCS), we use one set of data acquisition (DAQ) equipments to build a connection between the engineering simulator (software) and SIEMENS DCS I/O cabinet (hardware), and the interface is standard 4–20mA direct current and 0–48V direct voltage. This way is convenient for expansion to other digital I&C V&V. After these two V&V works, we can then build the confidence of digital I&C control function. As an application research, we mainly focus on V&V of digitalized control systems and selected several Reactor Control (RRC) systems as examples, including pressurizer pressure and water level control, steam generator water level control. In this paper, we will introduce the way of applying engineering simulator to do V&V works, the structure of our simulator, the function of different block, and primary V&V results. Moreover, we will have ideas on the future application of this methodology to V&V of Reactor Protection System and ESF Actuation System.

Analysis of DAS and ATWS Mitigation System in Nuclear Power Plant

2013 ◽  
Vol 397-400 ◽  
pp. 1383-1386
Author(s):  
Wan Ye Yao ◽  
Jin Bai
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Structure And Function ◽  
Normal Operation ◽  
Common Cause Failure ◽  
Actuation System ◽  
Similarities And Differences ◽  
And Function ◽  
Reactor Protection System

As the backup systems of RPS (reactor protection system), Diverse Actuation System and ATWS( Anticipated transients without scram) mitigation system are diversely designed from RPS system so as to offer protection for the normal operation of nuclear power plant. Both of the systems bear the function of mitigating the anticipated transients without scram events. Being isolated from RPS system, the design of DAS and ATWS system meeting the requirement of diversity and influences of CCFs (common cause failure) are effectively prevented. This article mainly analyzed the structure and function of the two systems and the similarities and differences between them.

scholarly journals Efficiency of Using the Auxiliary Boiler for Peak Power Generation by a Steam Turbine of NPP

2021 ◽  
Vol 64 (1) ◽  
pp. 78-90
Author(s):  
V. A. Khrustalev ◽  
M. V. Garievskii
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Steam Turbine ◽  
Nuclear Power ◽  
Power Plants ◽  
Normal Operation ◽  
Heat Output ◽  
Generation Process ◽  
System Effect ◽  
Industrial Enterprises

The article presents the technique of an estimation of efficiency of use of potential heat output of an auxiliary boiler (AB) to improve electric capacity and manoeuvrability of a steam turbine unit of a power unit of a nuclear power plant (NPP) equipped with a water-cooled water-moderated power reactor (WWER). An analysis of the technical characteristics of the AB of Balakovo NPP (of Saratov oblast) was carried out and hydrocarbon deposits near the NPP were determined. It is shown that in WWER nuclear power plants in Russia, auxiliary boilers are mainly used only until the normal operation after start-up whereas auxiliary boiler equipment is maintained in cold standby mode and does not participate in the generation process at power plants. The results of research aimed to improve the systems of regulation and power management of power units; general principles of increasing the efficiency of production, transmission and distribution of electric energy, as well as the issues of attracting the potential of energy technology sources of industrial enterprises to provide load schedules have been analyzed. The possibility of using the power complex NPP and the AB as a single object of regulation is substantiated. The authors’ priority scheme-parametric developments on the possibility of using the thermal power of the auxiliary boilers to increase the power of the steam turbine of a nuclear power plant unit equipped with WWER reactors unit during peak periods, as well as the enthalpy balance method for calculating heat flows, were applied. The surface area of the additional heater of the regeneration “deaerator – high pressure heaters” system and its cost were calculated. On the basis of calculations, it was shown that the additional power that can be obtained in the steam turbine of the NPP with a capacity of 1200 MW due to the use of heat of the modernized auxiliary boiler in the additional heat exchanger is 40.5 MW. The additional costs for the implementation of the heat recovery scheme of the auxiliary boiler at different prices for gas fuel and the resulting system effect were estimated in an enlarged way. Calculations have shown the acceptability of the payback period of the proposed modernization.

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