Design verification enhancement of field programmable gate array-based safety-critical I&C system of nuclear power plant

2017 ◽  
Vol 317 ◽  
pp. 232-241 ◽  
Author(s):  
Ibrahim Ahmed ◽  
Jaecheon Jung ◽  
Gyunyoung Heo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Field Programmable Gate Array ◽  
Nuclear Power ◽  
Design Verification ◽  
Safety Critical ◽  
Field Programmable ◽  
Gate Array

scholarly journals Reliability program plan for field programmable gate array-based I&C system of nuclear power plant

2019 ◽  
Author(s):  
Restu Maerani ◽  
Arya Adhyaksa Waskita ◽  
Satrio Pradana ◽  
Saharudin ◽  
Deswandri ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Field Programmable Gate Array ◽  
Nuclear Power ◽  
Field Programmable ◽  
Program Plan ◽  
Gate Array

scholarly journals Survey of Field Programmable Gate Array Design Guides and Experience Relevant to Nuclear Power Plant Applications

2007 ◽  
Author(s):  
Miljko Bobrek ◽  
Don Bouldin ◽  
David Eugene Holcomb ◽  
Stephen M Killough ◽  
Stephen Fulton Smith ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Field Programmable Gate Array ◽  
Nuclear Power ◽  
Array Design ◽  
Field Programmable ◽  
Gate Array

Criticality analysis for safety-critical software in nuclear power plant distributed control system

Kerntechnik ◽  
2021 ◽  
Vol 86 (5) ◽  
pp. 343-352
Author(s):  
J. Cui ◽  
Y. Cai ◽  
Y. Wu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Application Process ◽  
Software Module ◽  
Critical System ◽  
Safety Critical ◽  
Plant Safety ◽  
Safety Integrity Level ◽  
Criticality Analysis

Abstract Software criticality analysis examines the degree of contribution that each individual failure mode of a software component has on the reliability of software. Higher safety integrity levels are assigned to software modules whose failures cause an unacceptable impact on the operation of the system, and these levels require the implementation of more rigorous software quality assurance measures as defined in IEEE Std 1012 and in the customer’s system requirements specification. In this paper, a novel software criticality analysis method is proposed, the results of which can be used to guide the development of newly developed software and the procurement of Commercial-Off-The-Shelf (COTS) software. The software structure is first analyzed and the software is divided into modules according to their functions. Then the criticality levels of software components are preliminarily classified by means of a safety criticality preliminary analysis tree, followed by their verification through the software hazard and operability analysis (HAZOP). Finally, the target Safety Integrity Level (SIL) of each software module is determined based on its criticality level and the overall safety objective (i. e., SIL) of the system it resides in. As an example, this proposed method is applied to a nuclear power plant safety-critical system to demonstrate the detail application process and to verify the feasibility of the method. Compared with the existing software criticality analysis methods, this method has better operability and verifiability, and can be utilized as a technical guidance for the software criticality analysis of nuclear power plant digital control systems.

Quality assurance for a nuclear power plant simulator by applying standards for safety-critical software

2014 ◽  
Vol 70 ◽  
pp. 128-133 ◽  
Author(s):  
Ye Cheng ◽  
Ni Chao ◽  
Zheng Tian ◽  
Zhang Zhicheng ◽  
Zhang Ronghua
Keyword(s):  
Quality Assurance ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Critical

Design Verification for Control Logic in Nuclear Power Plant

2018 ◽  
Vol 4 (4) ◽  
Author(s):  
Hui Li ◽  
Guangxin Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Control Function ◽  
Logic Design ◽  
Design Verification ◽  
Control Logic ◽  
Design Data ◽  
Logic Diagram ◽  
And Control

The control function for process, heating, ventilation, and air conditioning, and electrical systems in nuclear power plant (NPP) are represented by control logic diagram. To develop distributed control system (DCS), the designer and supplier should complete the activities of control logic configuration, testing, and verification, which are based on control logic diagram. Design verification is an effective method to ensure the correctness of control logic design. This paper represents a system, which is capable of implementing control logic design verification automatically for NPP instrumentation and control (I&C) system, as well as an overview of the procedure and some examples by using this system. With the design data (including control requirements and control logic diagrams in computer-readable format) and simulation technology, this system automatically performs design verification based on different rules and confirms the design outputs meet the inputs—the control requirements of plant's systems. Finally, a conclusion about the design verification system and future scenarios is given.

Nuclear Power Plant Design Verification Based on the Analyzer

2013 ◽  
Author(s):  
Hanlin Wang ◽  
Mingguang Zheng ◽  
Tunfeng Qi
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Design Verification ◽  
Plant Design ◽  
Improve Design ◽  
Verification Methods ◽  
Basic Concepts

In this paper, the current nuclear power plant (abbreviated as NPP) design verification methods are analyzed, and employing nuclear power plant design analyzer (abbreviated as NPPDA,) is proposed to improve design verification. The main points include: the basic concepts of NPPDA, a detailed discussion of the principles of how NPPDA could play a role in design verification, and extended considerations on application of NPPDA in NPP design verification.

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