Software reliability to evaluate the safety of digital I&C systems was assumed as extremely low or zero. The probability of Software Failure can be evaluated by two specific tests. This work is a part of the project to quantitatively evaluate the software reliability of digital RPS; Software Logic Exhaustive Test and Hardware-Software Integrated Test. This research offers experimental importance during the reliability evaluation to obtain approximate reliability with limited test cases. On the other word, test cases with low importance, which means that the test cases occur rarely, can be screened out according to the results of this research
Recently, instrumentation and control (I&C) systems in nuclear power plants have undergone digitaliz...
Over the years, the probabilistic safety assessment (PSA) of digital reactor protection systems (RPS...
Recently, the input-profile-based testing for safety critical software has been proposed for determi...
Digital instrumentation and control (I&C) systems have several specific characteristics as compa...
Digitalization of the instrumentation and control systems in nuclear power plant entails some new fe...
A new Digital Reactor Protection System (DRPS) based on VME bus Single Board Computer has been devel...
Software has been used to digitalize many instrumentation and control (I&C) systems in nuclear p...
An issue on incorporating the software reliability within the NPP PRA model has been emerged in the ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.Page 242 ...
Since digital technologies have been improved, the analog systems in nuclear power plants (NPPs) hav...
Recently, a software program has been used in nuclear power plants (NPPs) to digitalize many instrum...
The objective of this project is to develop a method to predict the potential reliability of softwar...
Logical expressions are often used to formalize software specifications of safety-critical systems. ...
The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on ...
This paper presents a method for the quantification of software failures in a reactor protection sys...
Recently, instrumentation and control (I&C) systems in nuclear power plants have undergone digitaliz...
Over the years, the probabilistic safety assessment (PSA) of digital reactor protection systems (RPS...
Recently, the input-profile-based testing for safety critical software has been proposed for determi...
Digital instrumentation and control (I&C) systems have several specific characteristics as compa...
Digitalization of the instrumentation and control systems in nuclear power plant entails some new fe...
A new Digital Reactor Protection System (DRPS) based on VME bus Single Board Computer has been devel...
Software has been used to digitalize many instrumentation and control (I&C) systems in nuclear p...
An issue on incorporating the software reliability within the NPP PRA model has been emerged in the ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.Page 242 ...
Since digital technologies have been improved, the analog systems in nuclear power plants (NPPs) hav...
Recently, a software program has been used in nuclear power plants (NPPs) to digitalize many instrum...
The objective of this project is to develop a method to predict the potential reliability of softwar...
Logical expressions are often used to formalize software specifications of safety-critical systems. ...
The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on ...
This paper presents a method for the quantification of software failures in a reactor protection sys...
Recently, instrumentation and control (I&C) systems in nuclear power plants have undergone digitaliz...
Over the years, the probabilistic safety assessment (PSA) of digital reactor protection systems (RPS...
Recently, the input-profile-based testing for safety critical software has been proposed for determi...