Attack Induced Common-Mode Failures on PLC-Based Safety System in a Nuclear Power Plant: Practical Experience Report

2017 ◽  
Author(s):  
Bernard Lim ◽  
Daniel Chen ◽  
Yongkyu An ◽  
Zbigniew Kalbarczyk ◽  
Ravishankar Iyer
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Practical Experience ◽  
Safety System ◽  
Experience Report ◽  
Common Mode

Reforms and Innovations in a Nuclear Engineering Course: Nuclear Power Plant Systems and Equipment

2020 ◽  
Author(s):  
Shanfang Huang ◽  
Jiageng Wang ◽  
Yisheng Hao ◽  
Guodong Liu ◽  
Minyun Liu ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Engineering Students ◽  
Teaching Strategy ◽  
Public Attitudes ◽  
Safety System ◽  
Nuclear Engineering ◽  
Tsinghua University ◽  
Industry Trends

Abstract The Fukushima nuclear accident in Japan caused a significant impact on the nuclear power industry and public attitudes towards nuclear energy. The decreased public acceptance and the regulatory authorities’ stricter requirements of nuclear safety lead to the popularity of advanced safety technologies in scientific research and engineering projects. The demand for highly qualified human resources increases by the gradual recovery of the nuclear power field in China. In order to meet this demand, a series of course innovations are taken at Tsinghua University. Focusing on the course “Nuclear Power Plant Systems and Equipment,” the paper discusses the innovations of the course stimulated by the current industry trends and demands. A brief introduction to the special commissioned-student program at Tsinghua University is given. The paper investigates the meaning and function of the course in the frame of the curriculum plan for nuclear engineering students at Tsinghua University. The personal career plan, the industry outlook, and even the public attitudes contribute to senior students’ attitudes and demands for the course, which is tied closely to the effect of teaching. The paper addresses that the objective of the innovations is to develop a course fixing different students’ demands and help them build their ability to solve practical engineering problems in their future professional careers. The selection of teaching contents and the teaching strategy are discussed. This course takes Westinghouse AP1000 as the major point. And the nuclear power plant systems are taught in a divided way. One is the operation system, and the other is the safety system. This separation is based on the different functions and roles of these two parts and could have advantages in teaching effect. The paper explains the critical points of the systems and innovations of how to deal with course difficulties. There is a corresponding part of the safety system, and this part gets more challenges due to the industry trends. Lectures, group discussions, homework, and presentation projects are discussed. Besides, the paper considers possible efforts for further development of nuclear engineering courses.

scholarly journals A Dialogic Perspective on Managing Knowledge Differences: Problem-Solving while Building a Nuclear Power Plant Safety System

2021 ◽  
pp. 017084062110618
Author(s):  
Chia-Yu Kou ◽  
Sarah Harvey
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Knowledge Integration ◽  
Safety System ◽  
Problem Situation ◽  
Plant Safety ◽  
Nuclear Power Plant Safety ◽  
Large Scale Project

To manage knowledge differences, existing research has documented two sets of practices: traversing and transcending knowledge boundaries. What research has yet to explore, however, is the dynamics through which traversing or transcending practices emerge in response to a particular problem situation. Using a qualitative, inductive study of the problem episodes encountered by groups of experts working on a large-scale project to build the safety system for a nuclear power plant, we observed that the emergence of traversing or transcending depended on how experts interpreted problems and initiated dialogues around specific problems. Our work provides insight into the condition through which knowledge integration trajectories may emerge.

The Analysis and Design Technology Research of DAS

2013 ◽  
Author(s):  
Quan Ma ◽  
Qi Luo ◽  
Yanyang Liu ◽  
Xiaoming Song ◽  
Zhiqiang Wu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety System ◽  
Analysis And Design ◽  
Actuation System ◽  
Automatic Reactor ◽  
The Common ◽  
Software And Hardware ◽  
Plant Parameter

Now the entire safety I&C system is based on one kind of software and hardware platform, the Common Cause Failure (CCF) may impact the whole safety I&C system becomes to a potential risk. How to mitigate the effect of CCF in safety system and improve the safety of the nuclear power plant is considered by the system designer. Especially after the Fukushima nuclear accident, the Defense-in-Depth and Diversity (D3) should be more concerned by all designers. The diverse actuation system (DAS) plays a very important role in the D3 system. In this paper, the related codes and standards of DAS are analyzed firstly. Then, this paper expounds the approach to demonstrate the D3 analysis for the digital I&C systems applied to the nuclear power plant in detail. In the D3 analysis, all the safety functions of the digital safety system are assumed to be disabled by a CCF. DAS provides diverse automatic reactor trip and diverse safety injection actuation which are not impaired by the postulated CCF. DAS also provides manual actuation functions and plant parameter monitoring functions which can be used to cope with CCF. Finally, the paper takes the DAS of Fujian Fuqing Nuclear Power Plant as an example, introduce how to design the structure of the DAS and calculate the suitable setpoints.

The Comparative Advantages of CAP1400 Nuclear Power Plant Passive Safety System

2017 ◽  
Author(s):  
Ye Cheng ◽  
Wang Minglu ◽  
Qiu Zhongming ◽  
Wang Yong
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Cooling System ◽  
Assessment Method ◽  
Safety System ◽  
Passive Safety ◽  
Passive Safety System ◽  
First Choice ◽  
Comparative Advantages

With the demand for nuclear power increasing, the first choice of almost all countries who want to build a new nuclear power plant is to use generation III technology, primarily because the safety of generation III technology is greatly improved compared with that of generation II and II + technology. The passive safety technology was introduced by the AP1000 and is one of the best applications of generation III technologies. In this study, the representative passive containment cooling system of the CAP1400 (developed based on AP1000) and the containment spray system of a generation II nuclear power plant are compared and analyzed using the Probabilistic Safety Assessment method. The reasons why a passive safety system has comparative advantages are determined by concrete calculations.

Discussion and Application of Passive Hydrogen Recombiner in Qinshan Phase II Nuclear Power Plant

2014 ◽  
Vol 1008-1009 ◽  
pp. 215-220
Author(s):  
Hai Qiao Chen ◽  
Yi Mu Qiu ◽  
Xiao Wei Wang ◽  
Ying Yu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Phase Ii ◽  
Nuclear Power ◽  
Practical Experience ◽  
Hydrogen Elimination ◽  
Surrounding Environment ◽  
Radioactive Substances ◽  
Nuclear Security ◽  
Containment Integrity

A large amount of hydrogen would be generated because of zirconium-water reaction during serious accidents in nuclear power plant (NPP). Hydrogen could be combusted or explode under certain conditions, resulting in damage of the containment integrity and releasing radioactive substances into surrounding environment. Therefore, hydrogen elimination inside the NPP containment is an important subject. According to the requirements of NNSA (National Nuclear Security Administration), enough passive hydrogen recombiners (PHR) had been installed in unit 3&4 of Qinshan phase II NPP to prevent the hydrogen explosion in a serious accident. Additionally, new PHRs for unit 1&2 were also added. This article introduces the practical experience for the PHR modification, the comparisons between unit 1&2 and unit 3&4.

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