Software has been used to digitalize many instrumentation and control (I&C) systems in nuclear power plants (NPPs). Since software failure induces the common cause failure of the processor modules, the reliability of the software used in NPP safety-critical I&C systems must be quantified and verified with proper test cases and environment. In this study, a software testing method using the simulation-based software test-bed is proposed. In the test-bed, the microprocessor architecture of the programmable logic controller (PLC) used in NPP safety-critical applications is emulated and the execution behavior of the microprocessor at each machine instruction line is captured. The effectiveness of the proposed method is demonstrated with...
Software reliability to evaluate the safety of digital I&C systems was assumed as extremely low ...
Field-programmable gate arrays (FPGAs) have received much attention from the nuclear industry as an ...
Over the years, the probabilistic safety assessment (PSA) of digital reactor protection systems (RPS...
Recently, a software program has been used in nuclear power plants (NPPs) to digitalize many instrum...
An issue on incorporating the software reliability within the NPP PRA model has been emerged in the ...
Digitalization of the instrumentation and control systems in nuclear power plant entails some new fe...
Digital instrumentation and control (I&C) systems have several specific characteristics as compa...
The objective of this project is to develop a method to predict the potential reliability of softwar...
Existing nuclear power plants (NPPs) are switching from analog to digital control systems, and digit...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.Page 242 ...
Abstract: Software qualification includes such activities as a software Verification and Validation...
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...
Currently, no consensus approach is available for assessing safety and reliability of digital I&...
AbstractField-programmable gate arrays (FPGAs) have received much attention from the nuclear industr...
Software reliability to evaluate the safety of digital I&C systems was assumed as extremely low ...
Field-programmable gate arrays (FPGAs) have received much attention from the nuclear industry as an ...
Over the years, the probabilistic safety assessment (PSA) of digital reactor protection systems (RPS...
Recently, a software program has been used in nuclear power plants (NPPs) to digitalize many instrum...
An issue on incorporating the software reliability within the NPP PRA model has been emerged in the ...
Digitalization of the instrumentation and control systems in nuclear power plant entails some new fe...
Digital instrumentation and control (I&C) systems have several specific characteristics as compa...
The objective of this project is to develop a method to predict the potential reliability of softwar...
Existing nuclear power plants (NPPs) are switching from analog to digital control systems, and digit...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.Page 242 ...
Abstract: Software qualification includes such activities as a software Verification and Validation...
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...
Currently, no consensus approach is available for assessing safety and reliability of digital I&...
AbstractField-programmable gate arrays (FPGAs) have received much attention from the nuclear industr...
Software reliability to evaluate the safety of digital I&C systems was assumed as extremely low ...
Field-programmable gate arrays (FPGAs) have received much attention from the nuclear industry as an ...
Over the years, the probabilistic safety assessment (PSA) of digital reactor protection systems (RPS...