scholarly journals Research and Implementation of SVDU Simulator Based on Emulation Technology

2021 ◽  
Vol 2021 ◽  
pp. 1-9
Author(s):  
Yanqun Wu ◽  
Mingxing Liu ◽  
Qi Chen ◽  
Xu Zhang ◽  
Xufeng Tian ◽  
...  
Keyword(s):  
Embedded System ◽  
Nuclear Power ◽  
Engineering Application ◽  
Security Level ◽  
Safety Level ◽  
Operator Training ◽  
Safety Control ◽  
Safety Parameters ◽  
Application Requirements ◽  
Reactor Protection System

The safety video display unit (SVDU), as the display machine of the reactor protection system, performs the functions of displaying the reactor’s safety parameters and sending safety control commands. In order to meet the needs of nuclear power safety-level digital control system (DCS), like designing verification, operator training, and accidental drills, for the SVDU in the NASPIC platform developed independently by China National Nuclear Corporation, a virtual embedded system technology based on the micro x86 industrial host is proposed to make software simulation to the SVDU physical controller with exactly the same hardware appearance of the original one. The SVDU stimulator realized by this research can achieve 100% simulation of the logical functions of the SVDU physical equipment and the synchronized upgrading function between stimulator and the real equipment. With the development of multiple engineering application requirements, such as configuration verification and operator training, this stimulator has been applied in several virtual security level DCS projects.

Application of Monte Carlo Methods in Reactor Protection System Reliability Research

2018 ◽  
Author(s):  
Duo Li ◽  
Zhaojun Hao ◽  
Shuqiao Zhou ◽  
Chao Guo
Keyword(s):  
Monte Carlo ◽  
Reliability Analysis ◽  
Monte Carlo Methods ◽  
Nuclear Power ◽  
Power Plants ◽  
Fault Tree Analysis ◽  
Engineering Application ◽  
Protection System ◽  
System States ◽  
Reactor Protection System

Digital Reactor Protection System (RPS) is one of the most important systems in instrumentation and control systems of Nuclear Power Plants (NPP). The reliability analysis of RPS plays an important role both in theory and engineering application. Traditional reliability methods, such as fault tree analysis and Markov chain theory, have many limitations in the research of RPS reliability, since the number of system states increases exponentially with the growth of system complexity. Aiming at the reliability analysis of complex system like RPS, the Monte Carlo method simulates the system behaviors and obtains the reliability calculations through a large number of simulations. This paper takes a preliminary research of RPS reliability based on Monte Carlo Methods, including static reliability analysis based on Monte Carlo simulation of the behavior of every equipment in the RPS, and dynamic characters of the RPS based on the simulation of RPS period tests.

Research on Evaluation Model of Aviation Ordnance Safety Performance

2014 ◽  
Vol 556-562 ◽  
pp. 4171-4177
Author(s):  
Zhi Hua Xiao ◽  
Wei Shi Xie ◽  
Jian Tang
Keyword(s):  
Performance Evaluation ◽  
Evaluation Model ◽  
Safety Performance ◽  
Security Level ◽  
Inherent Safety ◽  
Safety Criterion ◽  
Safety Level ◽  
Research On Evaluation ◽  
Safety Design ◽  
Safety Parameters

Security is the main direction of ammunition for future development. Depending on the security level that ammunition relative to its life process may suffer major environmental stimuli factors, raising ammunition’s safety criterion, introducing safety parameters, establishing a theoretical model of ammunition safety performance evaluation. In the model, based on the value of the safety of ammunition, we divides the security level of ammunition. Based on this evaluation model to calculate the conventional bomb safety performance of the changing Mk-82’s insensitivity. We analyzed the influence of unexploded ordnance (UXO) on the overall safety performance of ammunition from the failure of the design. The results show that the end of unexploded failure design can significantly improve the safety level of ammunition. This model better reflects the inherent safety performance of ammunition, can provide theoretical guidance for the safety design of ammunition and safety performance evaluation.

The Failure Analysis and Processing of Digital Reactor Protection System

2013 ◽  
Author(s):  
Jun Zhao ◽  
Xing Zhou ◽  
Jin Hu ◽  
Yanling Yu
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Phase 1 ◽  
Protection System ◽  
Pressurized Water Reactor ◽  
Communication Failure ◽  
Pressurized Water ◽  
Power Failure ◽  
Self Test ◽  
Reactor Protection System

The Qinshan Nuclear Power Plant phase 1 unit (QNPP-1) has a power rating of 320 MWe generated by a pressurized water reactor that was designed and constructed by China National Nuclear Corporation (CNNC). The TELEPERM XS I&C system (TXS) is to be implemented to transform analog reactor protection system (RPS) in QNPP-1. The paper mainly describes the function, structure and characteristic of RPS in QNPP-1. It focuses on the outstanding features of digital I&C, such as strong online self-test capability, the degradation of the voting logic processing, interface improvements and CPU security. There are some typical failures during the operation of reactor protection system in QNPP-1. The way to analyze and process the failures is different from analog I&C. The paper summarizes typical failures of the digital RPS in the following types: CPU failure, communication failure, power failure, Input and output (IO) failure. It discusses the cause, risk and mainly processing points of typical failure, especially CPU and communication failures of the digital RPS. It is helpful for the maintenance of the system. The paper covers measures to improve the reliability of related components which has been put forward effective in Digital reactor protection system in QNPP-1. It will be valuable in nuclear community to improve the reliability of important components of nuclear power plants.

Design of the Communication Independence for ACPR1000 Nuclear Power Plant Digital Safety I&C System

2017 ◽  
Author(s):  
Sun Na ◽  
Shi Gui-lian ◽  
Xie Yi-qin ◽  
Li Gang ◽  
Jiang Guo-jin
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Communication Networks ◽  
Nuclear Power ◽  
Protection System ◽  
Plant Safety ◽  
Safety And Reliability ◽  
Digital Protection ◽  
Architecture And Design ◽  
Reactor Protection System

Communication independence is one of the key criteria of digital safety I&C system design. This paper mainly analyzes the requirements for communication independence in safety regulations and standards, and then introduces the architecture and design features, including communication failure processing measures, of communication networks of ACPR1000 nuclear power plant safety digital protection system based on FirmSys platform developed by CTEC. The communication design meets the regulations requirements and effectively improves the safety and reliability of the system, and it is successfully applied in reactor protection system (RPS) of Yang Jiang nuclear power plant unit 5&6. In addition this design can provide reference for communication designs of other NPPs and industries.

ANALYSIS OF THE RADIOLOGICAL SAFETY CONTROL LEVEL VERSUS THE EXPOSURE OF RADIATION WORKERS IN SOUTH KOREA FROM 2008–17

2018 ◽  
Vol 184 (1) ◽  
pp. 98-108
Author(s):  
Sang-Tae Kim ◽  
Jaeryong Yoo
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Radiation Safety ◽  
Safety Management ◽  
Control Level ◽  
Radioactive Isotopes ◽  
Safety Control ◽  
Level Versus ◽  
Radiation Workers

Abstract In this study, the radiation exposure of workers at workplaces registered and licensed between 2008 and 2017 for the production/sale/use of radioactive isotopes (RI) and radioactive generators (RG) was analysed to evaluate the quality of radiation safety management controls in use. The number of facilities using RIs increased by ~26% from 2008 to 2017 whereas the number of facilities using RGs increased by ~166% over the same period. There were 33 029 radiation workers in all fields in 2008, and the number increased by ~32% to 43 467 by 2017. However, the collective effective dose of radiation received by workers decreased in all industries except for those working in nuclear power plants. In other words, the quality of radiation safety management improved over that same time period due to the systematic, continuous introduction of safety mechanisms by the regulatory authority.

Composition of Safety and Cyber Security Analysis Techniques and Tools for NPP I&C System Assessment

2020 ◽  
pp. 204-220
Author(s):  
Ievgen Babeshko ◽  
Kostiantyn Leontiiev
Keyword(s):  
Cyber Security ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Security Analysis ◽  
Assessment Method ◽  
Assessment Methods ◽  
Assessment Process ◽  
Safety Level ◽  
Methods And Techniques ◽  
And Control

Safety assessment of nuclear power plant instrumentation and control systems (NPP I&Cs) is a complicated and resource-consuming process that is required to be done so as to ensure the required safety level and comply to normative regulations. A lot of work has been performed in the field of application of different assessment methods and techniques, modifying them, and using their combinations so as to provide a unified approach in comprehensive safety assessment. Performed research has shown that there are still challenges to overcome, including rationale and choice of the safety assessment method, verification of assessment results, choosing and applying techniques that support safety assessment process, especially in the nuclear field. This chapter presents a developed framework that aggregates the most appropriate safety assessment methods typically used for NPP I&Cs.

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