The modernization of existing and new nuclear power plants with digital instrumentation and control systems (DI&C) is a recent and highly trending topic. However, there lacks strong consensus on best-estimate reliability methodologies by both the United States (U.S.) Nuclear Regulatory Commission (NRC) and the industry. In this work, we develop an approach called Orthogonal-defect Classification for Assessing Software Reliability (ORCAS) to quantify probabilities of various software failure modes in a DI&C system. The method utilizes accepted industry methodologies for quality assurance that are verified by experimental evidence. In essence, the approach combines a semantic failure classification model with a reliability growth model to pre...
Bayesian belief network model was developed in authors' previous research that quantifies the n...
There is so far no consensus on how to develop a reliability model of safety-related digitalinstrume...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.Page 242 ...
The objective of this project is to develop a method to predict the potential reliability of softwar...
The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on ...
Since the digital instrumentation and control systems are expected to play an important role for the...
In recent years, there has been considerable effort to modernize existing and new nuclear power plan...
This paper presents a method for the quantification of software failures in a reactor protection sys...
A method for estimating software reliability for nuclear safety software is proposed in this paper. ...
Digital instrumentation and control systems (I&C) are appearing as upgrades in older nuclear pow...
As the instrumentation and control (I&C) systems in nuclear power plants (NPPs) have been replac...
We present a review of software-induced failures in commercial nuclear power plants (NPPs) and in se...
To assess the risk of nuclear power plant operation and to determine the risk impact of digital syst...
Digital protection and control systems are appearing as upgrades in older nuclear power plants (NPPs...
As the instrumentation and control (I&C) systems in nuclear power plants (NPPs) have been replac...
Bayesian belief network model was developed in authors' previous research that quantifies the n...
There is so far no consensus on how to develop a reliability model of safety-related digitalinstrume...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.Page 242 ...
The objective of this project is to develop a method to predict the potential reliability of softwar...
The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on ...
Since the digital instrumentation and control systems are expected to play an important role for the...
In recent years, there has been considerable effort to modernize existing and new nuclear power plan...
This paper presents a method for the quantification of software failures in a reactor protection sys...
A method for estimating software reliability for nuclear safety software is proposed in this paper. ...
Digital instrumentation and control systems (I&C) are appearing as upgrades in older nuclear pow...
As the instrumentation and control (I&C) systems in nuclear power plants (NPPs) have been replac...
We present a review of software-induced failures in commercial nuclear power plants (NPPs) and in se...
To assess the risk of nuclear power plant operation and to determine the risk impact of digital syst...
Digital protection and control systems are appearing as upgrades in older nuclear power plants (NPPs...
As the instrumentation and control (I&C) systems in nuclear power plants (NPPs) have been replac...
Bayesian belief network model was developed in authors' previous research that quantifies the n...
There is so far no consensus on how to develop a reliability model of safety-related digitalinstrume...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.Page 242 ...