AbstractWe describe a comparative analysis of different tools used to assess safety-critical software used in nuclear power plants. To enhance the credibility of safety assessments and to optimize safety justification costs, Electricité de France (EDF) investigates the use of methods and tools for source code semantic analysis, to obtain indisputable evidence and help assessors focus on the most critical issues. EDF has been using the PolySpace tool for more than 10 years. Currently, new industrial tools based on the same formal approach, Abstract Interpretation, are available. Practical experimentation with these new tools shows that the precision obtained on one of our shutdown systems software packages is substantially improved. In the f...
Nuclear power plant safety is granted through the demonstration that regulatory acceptance criteria...
As digital instrumentation in Nuclear Power Plants (NPPs) is becoming increasingly complex, both att...
This paper presents a method for the quantification of software failures in a reactor protection sys...
International audienceWe describe a comparative analysis of different tools used to assess safety-cr...
AbstractWe describe a comparative analysis of different tools used to assess safety-critical softwar...
In regulated domains, such as nuclear power, a documented justification of safety is demanded for li...
In regulated domains, such as nuclear power, a documented justification of safety is demanded for li...
Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1 (Quality Assurance for Safety-...
Abstract Many teams at CERN, develop their own software to solve their tasks. This software may be...
Currently, no consensus approach is available for assessing safety and reliability of digital I&...
The work documented in this report was performed in support of the US Nuclear Regulatory Commission ...
Digitalization of the instrumentation and control systems in nuclear power plant entails some new fe...
This report presents the results of a study which devises an Integrated Formal Approach (IFA) for im...
This paper presents a documentation and development method to facilitate the certification of scient...
Digital instrumentation and control (I&C) systems have several specific characteristics as compa...
Nuclear power plant safety is granted through the demonstration that regulatory acceptance criteria...
As digital instrumentation in Nuclear Power Plants (NPPs) is becoming increasingly complex, both att...
This paper presents a method for the quantification of software failures in a reactor protection sys...
International audienceWe describe a comparative analysis of different tools used to assess safety-cr...
AbstractWe describe a comparative analysis of different tools used to assess safety-critical softwar...
In regulated domains, such as nuclear power, a documented justification of safety is demanded for li...
In regulated domains, such as nuclear power, a documented justification of safety is demanded for li...
Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1 (Quality Assurance for Safety-...
Abstract Many teams at CERN, develop their own software to solve their tasks. This software may be...
Currently, no consensus approach is available for assessing safety and reliability of digital I&...
The work documented in this report was performed in support of the US Nuclear Regulatory Commission ...
Digitalization of the instrumentation and control systems in nuclear power plant entails some new fe...
This report presents the results of a study which devises an Integrated Formal Approach (IFA) for im...
This paper presents a documentation and development method to facilitate the certification of scient...
Digital instrumentation and control (I&C) systems have several specific characteristics as compa...
Nuclear power plant safety is granted through the demonstration that regulatory acceptance criteria...
As digital instrumentation in Nuclear Power Plants (NPPs) is becoming increasingly complex, both att...
This paper presents a method for the quantification of software failures in a reactor protection sys...