scholarly journals Design and Development Framework of Safety-Critical Software in HTR-PM

2017 ◽  
Vol 2017 ◽  
pp. 1-9 ◽  
Author(s):  
Chao Guo ◽  
Huasheng Xiong ◽  
Xiaojin Huang ◽  
Duo Li

With the development of information technology, the instrumentation and control system of nuclear power plant nowadays rely heavily on the massive and complex software to ensure the safe and efficient operation of the power plant. The improvement of the software design and development for the safety systems has been a research focus for its decisive impact on the nuclear safety. The framework of the software design and development for reactor protection system in High Temperature Gas-Cooled Reactor-Pebble bed Module was introduced in this paper. Firstly, during the design period, in addition to multichannel redundancy, grouping of protection variables and diverse 2-out-of-4 logics were adopted by different subsystems of each channel in case of common cause failure. Then a series of development characteristics together with strict software verification and validation were performed. Thirdly, during the software test period, an improved software reliability growth model based on the Goel-Okumoto model according to the analysis of fault severity was proposed to help in estimating the reliability of the software product and identifying the software release time.

Author(s):  
Qinfang Zhang ◽  
Guoxu Zhang ◽  
Zilong Wang ◽  
Qi Dong ◽  
Guofeng Tang

Significance determination process (SDP) is one of important application tools in the scheme of risk-informed and performance based regulation. It is used to help the analyst evaluate the risk significance of a particular safety concerned event. By referring to the design and development of SDP system, this paper gives a brief introduction on the design and development of the system. An autonomously developed PSA quantification engine is incorporated into the SDP system, and it helps to resolve quantification issue for event risk evaluation. From qualified screening to risk significance quantification, SDP system is designed to realize the whole process for event risk analysis. SDP system could potentially help analysts from both regulatory agency and NPP licensees to quickly evaluate the risk significance of a particular event.


Author(s):  
Pengfei Gu ◽  
Shengchao Wang ◽  
Weihua Chen ◽  
Suyuan Yu

Since the digital instrument and control (I&C) system was used in nuclear power plant (NPP), software Verification and Validation (V&V) is becoming more and more important for ensuring the safety function to be correctly implemented by the safety system. According to the classification of different safety functions of I&C system, with the use of digital technology, software classification needs further discussion to determine. And different classification of software performs different testing. Software V&V processes can be divided into different stages by reference to the standard IEEE 1012-2004, and each stage focuses on different contents. In China, software V&V on the NPP has been started from LingAo Phase II project and strongly done on other CPR1000 projects, which is a Generation II + pressurized water reactor. Based on the practice about YangJiang units 5 and 6 projects, combined with the relevant laws and regulation standards, this study summarizes the characteristics of the independent third party software V&V, analyzes the key points and methods of V&V activities in the software development process. As a result, it is also benefit to the design, operation and maintenance of safety I&C System as technical reference.


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