Failure Probability of NPP Communication Bridge under the Extreme Loads

2014 ◽  
Vol 617 ◽  
pp. 81-85 ◽  
Author(s):  
Juraj Králik ◽  
Juraj Kralik
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Input Data ◽  
Steel Bridge ◽  
Advantages And Disadvantages ◽  
Extreme Loads ◽  
Load Factors ◽  
Extreme Load ◽  
Safety And Reliability

Safety and reliability of the communication steel bridge of the nuclear power plant under extreme loads is considered in this paper. The extreme load from the wind and the earthquake is defined for the probability of exceedance 10-4 per year on the base of the last results from the investigation in Slovakia. The deterministic and the probabilistic assessments to verify the safety and reliability of the structure are presented. The uncertainties of the input data and the calibration of the load factors are discussed. The advantages and disadvantages of the probabilistic analysis are discussed. The advantages of the utilization the LHS method to analyze the safety and reliability of the structures is presented.

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.

scholarly journals Human Reliability Studies With Microworld Simulators

2019 ◽  
Vol 63 (1) ◽  
pp. 1829-1833 ◽  
Author(s):  
Ronald Boring ◽  
Thomas Ulrich ◽  
Roger Lew ◽  
Martin Rasmussen Skogstad
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Data Collection ◽  
Nuclear Power ◽  
Human Error ◽  
Data Sources ◽  
Human Reliability ◽  
Reliability Data ◽  
Experimental Control ◽  
Advantages And Disadvantages

The authors have recently developed a microworld, a simplified process control simulator, to simulate a nuclear power plant. The microworld provides an environment that can be readily manipulated to gather data using a range of participants, from students to fully qualified operators. Because the microworld represents a simplified domain, it is possible to have more precise experimental control compared with the complex and confounding environment afforded by a full-scope simulator. In this paper, we discuss collecting human reliability data from a microworld. We review the generalizability of human error data from the microworld compared to other data sources like full-scope simulator studies and compare advantages and disadvantages of microworld simulator studies to support human reliability data collection needs.

Hitachi-GE Advanced Construction Management Technologies

2008 ◽  
Author(s):  
Kimiharu Onda ◽  
Masatoshi Takada ◽  
Hisako Okada ◽  
Kazuto Tatehora
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Construction Management ◽  
Nuclear Power ◽  
New Technologies ◽  
Personal Digital Assistant ◽  
Safety And Reliability ◽  
Planning Function ◽  
Under Construction ◽  
A Site

Hitachi has so far developed the construction management system with information technology since more than twenty years ago. As the recent results, we developed the advanced new functions and applied them to the Nuclear Power Plant (NPP)’s under construction. RFID-applied construction management method with personal digital assistant (PDA) could realize more reliable and efficient construction control on a site. By enhancing an Integrated Schedule Planning function, the construction scheme could be more accurately and speedily developed, which made it possible to realize the standardization of schedule planning, the linkage with other systems, and the improvement of operability. By applying these new technologies to Hitachi construction management, Hitachi can supply the nuclear power plant with higher quality, safety, and reliability.

scholarly journals Model Intercomparison of Atmospheric 137 Cs From the Fukushima Daiichi Nuclear Power Plant Accident: Simulations Based on Identical Input Data

2018 ◽  
Vol 123 (20) ◽  
pp. 11,748-11,765 ◽  
Author(s):  
Yousuke Sato ◽  
Masayuki Takigawa ◽  
Tsuyoshi Thomas Sekiyama ◽  
Mizuo Kajino ◽  
Hiroaki Terada ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Input Data ◽  
Model Intercomparison ◽  
Nuclear Power Plant Accident ◽  
Fukushima Daiichi

scholarly journals Deterministic and Probabilistic Analysis of NPP Communication Bridge Resistance Due to Extreme Loads

2014 ◽  
Vol 14 (2) ◽  
pp. 54-63 ◽  
Author(s):  
Juraj Králik ◽  
Juraj Králik
Keyword(s):  
Probabilistic Analysis ◽  
Probability Analysis ◽  
Steel Bridge ◽  
Bridge Structure ◽  
Advantages And Disadvantages ◽  
Extreme Loads ◽  
Safety And Reliability ◽  
Bridge Resistance

Abstract This paper presents the experiences from the deterministic and probability analysis of the reliability of communication bridge structure resistance due to extreme loads - wind and earthquake. On the example of the steel bridge between two NPP buildings is considered the efficiency of the bracing systems. The advantages and disadvantages of the deterministic and probabilistic analysis of the structure resistance are discussed. The advantages of the utilization the LHS method to analyze the safety and reliability of the structures is presented

Methods of Control of Inaccuracy in Calculation of Nuclear Power Plant Decommissioning Parameters

2009 ◽  
Author(s):  
Frantisˇek Ondra ◽  
Vladimi´r Danisˇka ◽  
Ivan Reha´k ◽  
Vladimi´r Necˇas
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Analytical Model ◽  
Nuclear Power ◽  
Input Data ◽  
Analytical Methodology ◽  
Model Calculations ◽  
Methods Of Control

The aim of the article is a development of analytical methodology for evaluation of input data inaccuracies impact on calculation of cost and other output decommissioning parameters. This methodology is based on analytical model calculations using the OMEGA code and taking into account the probability of input data inaccuracies occurrence also.

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