System Software Safety Assessment Process for Certification of Commercial and Military Aircraft

2005 ◽  
Author(s):  
Rohit P. Sheth
Keyword(s):  
Safety Assessment ◽  
Assessment Process ◽  
System Software ◽  
Military Aircraft ◽  
Software Safety

NPP I&C Safety Assessment by Aggregation of Formal Techniques

2018 ◽  
Author(s):  
Eugene Babeshko ◽  
Vyacheslav Kharchenko ◽  
Kostiantyn Leontiiev ◽  
Oleg Odarushchenko ◽  
Oleksiy Strjuk
Keyword(s):  
Nuclear Power ◽  
Safety Assessment ◽  
Power Plants ◽  
Failure Modes ◽  
Assessment Method ◽  
Assessment Methods ◽  
Assessment Process ◽  
Software Safety ◽  
Safety Level ◽  
Normative Documents

Safety assessment of nuclear power plant instrumentation and control systems (NPP I&Cs) is a complicated and resource consuming process that is required be done so as to ensure the required safety level and comply to normative regulations. A lot of work have been performed in the field of application of different assessment methods and techniques, modifying them and using their combinations so as to provide unified approach in comprehensive safety assessment. Anyway, performed research have shown there are still challenges to overcome, including rationale and choice of the safety assessment method, verification of assessment results, choosing and applying techniques that support safety assessment process, especially in the nuclear field. In our work we present developed framework that aggregates the most appropriate safety assessment methods typically used for NPP I&Cs. Key features that this framework provides are the formal descriptions of all required input information for every safety assessment method, possible data flows between methods, possible output information for every method. Such representation allows to obtain possible paths required to get necessary indicators, analyze the possibility to verify them by application of different methods that provide same indicators etc. During safety assessment of NPP I&Cs it is very important to address software due to its crucial role in I&C safety assurance. Relevant standards like IEC 60880 [1] and IEC 62138 [2] provide requirements for software related activities and supporting processes in the software safety lifecycle of computer-based I&C systems of nuclear power plants performing functions of safety category A, B and C, as defined by IEC 61226 [3]. Requirements and frameworks provided by IEC 60880 and IEC 62138 for the nuclear application sector correspond to IEC 61508, part 3 [4]. These standards define several types of safety related software and specify particular requirements for each software type. So as to verify software and confirm correspondence to required safety level, different techniques are suggested in normative documents. We share our experience obtained during software failure modes and effect analysis (software FMEA) and software fault insertion (software FIT) processes into FPGA-based platform, NPP I&C systems based on that platform, and RPCT, integrated development environment used by RPC Radiy and end users to design user application logic, specify hardware configuration etc. We apply software FIT to outputs of RPCT, considering source code, configuration files and firmware files. Finally, we provide a case study of application the developed safety assessment framework and software FMEA/FIT practices during practical assessment of FPGA-based NPP I&C system.

Quantifying Minimum-Time-To-Intrusion Based on Dynamic Software Safety Assessment

2000 ◽  
Author(s):  
Jeffery M. Voas ◽  
Gary McGraw ◽  
Anup Ghosh ◽  
Frank Charron ◽  
Michael Schatz
Keyword(s):  
Safety Assessment ◽  
Minimum Time ◽  
Software Safety ◽  
Dynamic Software

Composition of Safety and Cyber Security Analysis Techniques and Tools for NPP I&C System Assessment

2020 ◽  
pp. 204-220
Author(s):  
Ievgen Babeshko ◽  
Kostiantyn Leontiiev
Keyword(s):  
Cyber Security ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Security Analysis ◽  
Assessment Method ◽  
Assessment Methods ◽  
Assessment Process ◽  
Safety Level ◽  
Methods And Techniques ◽  
And Control

Safety assessment of nuclear power plant instrumentation and control systems (NPP I&Cs) is a complicated and resource-consuming process that is required to be done so as to ensure the required safety level and comply to normative regulations. A lot of work has been performed in the field of application of different assessment methods and techniques, modifying them, and using their combinations so as to provide a unified approach in comprehensive safety assessment. Performed research has shown that there are still challenges to overcome, including rationale and choice of the safety assessment method, verification of assessment results, choosing and applying techniques that support safety assessment process, especially in the nuclear field. This chapter presents a developed framework that aggregates the most appropriate safety assessment methods typically used for NPP I&Cs.

Safety Assessment Process Optimization for Integrated Modular Avionics

2019 ◽  
Vol 34 (11) ◽  
pp. 58-67 ◽  
Author(s):  
Yunsheng Wang ◽  
Hang Lei ◽  
Richard Hackett ◽  
Martin Beeby
Keyword(s):  
Process Optimization ◽  
Safety Assessment ◽  
Assessment Process ◽  
Integrated Modular Avionics

scholarly journals The Safety Assessment Process—Setting the Scene: An FDA Perspective

ILAR Journal ◽  
2002 ◽  
Vol 43 (Suppl_1) ◽  
pp. S5-S10 ◽  
Author(s):  
Leonard M. Schechtman
Keyword(s):  
Safety Assessment ◽  
Assessment Process

Deterministic Risk Methodology for Road Tunnels

2008 ◽  
Author(s):  
Peter Vidmar ◽  
Stojan Petelin
Keyword(s):  
Safety Assessment ◽  
Calculated Data ◽  
Assessment Process ◽  
Strong Impact ◽  
Road Tunnel ◽  
Risk Matrix ◽  
Tunnel Length ◽  
Fire Dynamics ◽  
Road Tunnels ◽  
Ventilation Conditions

The definition of the deterministic approach in safety analyses arises from the need to understand the conditions that emerge during a fire accident in a road tunnel. The key factor of the tunnel operations during the fire is the ventilation, which during the initial phases of the fire have a strong impact on the evacuation of people and later on the access of the intervention units in the tunnel. The paper presents the use of the CFD model in the tunnel safety assessment process. The set-up of the initial and boundary conditions and the requirement for grid density found from validation tests of an FDS (Fire Dynamics Simulator) is used to prepare three kinds of fire scenarios, 20MW, 50MW and 100MW, with different ventilation conditions; natural, semi transverse, transverse and longitudinal ventilation. The observed variables, soot density and temperature, are presented in minutes time steps through the entire tunnel length. Comparing the obtained data in a table allows the analyses of the ventilation conditions for different heat releases from fires. The second step is to add additional criteria of human behaviour inside the tunnel (evacuation) and human resistance to the elevated gas concentrations and temperature. What comes out is a fully deterministic risk matrix that is based on the calculated data where the risk is ranged on five levels, from the lowest to a very dangerous level. The deterministic risk matrix represents the alternative to a probabilistic safety assessment methodology, wherein the fire risk is represented in detail and the CFD (Computational Fluid Dynamics) model results are physically correct.

Tools for the Standardised Software Safety Assessment. (The SOSAT Project)

1988 ◽  
Vol 21 (18) ◽  
pp. 1-6 ◽  
Author(s):  
G. Dahll ◽  
U. Mainka ◽  
J. Märtz
Keyword(s):  
Safety Assessment ◽  
Software Safety
Sign in / Sign up

Export Citation Format

Share Document