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.

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.

Application of a Large-Scale Database System for the Analysis and Design of the US EPR™ Standard Nuclear Power Plant

2012 ◽  
Author(s):  
Se-Kwon Jung ◽  
Joseph Harrold ◽  
Nawar Alchaar
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Database System ◽  
Database Management System ◽  
Plane Shear ◽  
Analysis And Design ◽  
Shear Design ◽  
The U.S

Due to the increased size and complexity of large-scale commercial and industrial structures, it is increasingly challenging to manage key engineering data including analysis and design results of these structures. This paper presents a novel approach of using large-scale database systems as a means to gather, organize and manage key analysis and design results of a large-scale structure. Specifically, this paper describes in detail the development process of the backend database management system (DBMS) for the U.S. EPR™ Standard Nuclear Power Plant (NPP) Nuclear Island (NI) structures. The database system consists of three parent database tables to represent three representative groups of load combinations applicable to the U.S. EPR™ Standard NPP. Inheriting all characteristics of an applicable parent table, a primary child table in the database system represents a particular U.S. EPR™ NI Safety-Related structure in its entirety while a secondary child table a group of slabs or walls of the structure. Each secondary table is comprised of database fields that are representative of various structural demands, section capacities, reinforcing ratios, and demand-to-capacity ratios for three reinforced concrete design conditions (i.e., combined axial force and bending design, in-plane shear design, and out-of-plane shear design). The complete database system with fully populated tables is a central repository where all analysis and design results for the U.S. EPR™ NI Common Basemat structures are stored and sorted. To facilitate data queries from the developed backend database system, this paper introduces a user-friendly frontend interface program developed using Visual Basic Application (VBA) with Excel. Potential benefits of the developed database system are demonstrated with simple application examples involving simple data queries only followed by complex engineering tasks that require a more advanced form of data queries.

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