Research on Digital Instrumentation and Control System in Nuclear Power Plant Using Mixed Redundant Model

Author(s):  
Zhiwu Ke ◽  
Xianling Li ◽  
Rui Yu ◽  
Rui Xiang

Reliability is the most important factor in instrumentation and control (I&C) system for nuclear power plant (NPP). Now in order to reach high reliability, static redundant and dynamic redundant technique is in common use. Static redundant method can keep out the failure of one module, but could not detect the mistake. Dynamic redundant mean would examine the mistake of the working unit, but can not ward off the failure. In this study, our main purpose is to develop the advanced redundant way which includes the advantage of static redundancy and dynamic redundancy means by mixed redundant model (MRM). Utilizing logic order in the relationship between unit and system using reliable diagram, analyzing the reliability of MRM by the way of probability, the result has obvious effect upon improving the system reliability compared with above two models. MRM can be applied for safety critical I&C.

Author(s):  
I-Hsin Chou ◽  
Hsueh-Wei Hsiao ◽  
Che-An Chang

As Nuclear Power Plant (NPP) adopted software-based Digital Instrumentation and Control (DI&C) System, the Software Configuration Management (SCM) is becoming more and more important for NPP. The main reason is the inherent changeability and invisibility which of software often causes unpredictable problems and results are difficult to manage. In addition, the DI&C system has always been constructed by multiple vendors and each vendor of the DI&C has its own development artifacts. Therefore, it is great challenge for NPP staff to maintain the consistency and integrity of software Configuration Items (CI) among multiple vendors. The software CIs include software products delivered to customers and items required to create the software products such as software design document, source code, database, test report, compiler, etc. In general, Software Configuration Management System (SCMS) is usually developed to support SCM activities, such as storing CI, controlling change, and accounting and auditing throughout the entire software lifecycle. However, most existing file-based SCMS typically deal with those artifacts of individual files without providing the more detailed configuration and change information among CIs. Based on the nuclear SCM related regulations, this paper proposes a developing SCMS for the DI&C system of a NPP. Its main goal is to meet the regulatory requirements, and enhance the visibility, tractability and integrate ability to manage the heterogeneous subsystems within the DI&C system. This paper provides the more detailed descriptions about regulation requirements analysis, system design and the development process. Finally, a prototype system is presented.


Author(s):  
Shengchao Wang ◽  
Pengfei Gu ◽  
Wangping Ye ◽  
Weihua Chen

Digital instrumentation and control (I&C) system has been widely applied in nuclear power plant (NPP), which brings some new problems like software failure. The software failure is easy to come into being the common cause failure (CCF), leading to the failure of the whole protection system for NPP, thus endangering the safety of the NPP. In order to obtain the high quality software for computer important to safety, it is necessary to implement the software verification and validation (V&V) to guarantee that the software can completely and correctly meet the expected requirements of safety functions and performances. Moreover, for the guidance of software V&V and to strengthen the reliability of the software, laws and regulation standards related to the software V&V, were analyzed. On the basis of requirements of the laws and regulations standards and the results of analysis, a technical architecture about nuclear safety digital instrumentation and control system (DCS) software V&V was proposed, which consists of a technical model of software V&V and a general quality assurance (QA) system. The technical model of software V&V mainly illustrated some problems and discussed how to deal with it on the specific implementation of V&V activities and tasks. Meanwhile, in order to support the software V&V activities and tasks carried out efficiently, the general QA system, corresponding to the technical model of software V&V, was established which can supply the visual evidence for quality control process. At this point, it is expected that the results as studied above can provide some technical references in the transformation, formulating or modifying related standards of China and to promote the quality of nuclear safety DCS software.


2014 ◽  
Vol 687-691 ◽  
pp. 751-754 ◽  
Author(s):  
Hao Ran Li ◽  
Xu Hong Yang

First of all, the most important thing in introducing the digitization to the instrumentation and control system of nuclear power plant is its reliability. Then, what needs to do is designing each part of the system combined with the digital characteristic. Only through the system design of redundancy and diversification can the system of instrumentation and control be secure to run.


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