A Quantitative Safety Assessment Methodology for Safety-Critical Programmable Electronic Systems Using Fault Injection

Safety integrity level (SIL)-based functional safety assessment is widely required in designing safety functions and checking their validity of electrical/electronic/programmable electronic (E/E/PE) safety-related systems after being issued IEC 61508 in 2010. For the hardware of E/E/PE safety-related systems, quantitative functional safety assessment based on target failure measures is needed for deciding or allocating the level of SIL. On the other hand, IEC 61508 does not provide any quantitative safety assessment method for allocating SIL for the software of E/E/PE safety-related systems because the software failure is treated as a systematic failure in IEC 61508. We discuss the needfulness of quantitative safety assessment for software of E/E/PE safety-related systems and propose mathematical fundamentals for conducting quantitative SIL-based safety assessment for the software of E/E/PE safety-related systems by applying the notion of software reliability modeling and assessment technologies. We show numerical examples for explaining how to use our approaches.

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Physics-of-failure assessment methodology for power electronic systems

Microelectronics Reliability ◽

10.1016/j.microrel.2014.07.123 ◽

2014 ◽

Vol 54 (9-10) ◽

pp. 1680-1685 ◽

Cited By ~ 4

Author(s):

D. Squiller ◽

H. Greve ◽

E. Mengotti ◽

F.P. McCluskey

Keyword(s):

Electronic Systems ◽

Power Electronic ◽

Assessment Methodology ◽

Physics Of Failure ◽

Failure Assessment

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An Integrated Safety Assessment System for Near-Surface Disposal of Low- and Intermediate-Level Radioactive Waste in Korea

9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3 ◽

10.1115/icem2003-4616 ◽

2003 ◽

Author(s):

JooWan Park ◽

Chang-Lak Kim ◽

Jin Beak Park ◽

Eun Yong Lee ◽

Youn Myoung Lee ◽

...

Keyword(s):

Radioactive Waste ◽

Safety Assessment ◽

Assessment System ◽

Intermediate Level ◽

Radioactive Waste Disposal ◽

System Level ◽

Assessment Methodology ◽

Regulatory Requirements ◽

Near Surface ◽

Intermediate Level Radioactive Waste

An integrated safety assessment system to be used for evaluation of near-surface disposal concept has been developed within the framework of safety assessment methodology taken for low- and intermediate-level radioactive waste disposal in Korea. It is to provide an evaluation of the safety of the disposal system in a clear, comprehensive and well-documented manner, and to integrate the results into a defensible package showing reasonable assurance of compliance with regulatory requirements for licensing application. This system is made up of two key components, a system-level safety assessment code and an input database/quality assurance module for safety assessment, which both are interfaced with each other.

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Hybrid Probabilistic and Possibilistic Safety Assessment: Methodology and Application

Volume 3: Hazardous Waste; Engineered/Geological Barriers in Disposal Systems; L/ILW; Radioactive Waste From Research/Industries; Spent Fuel/HLW Disposal; Public Involvement; Remediation of Uranium Mining/Milling; LL/ILW; Clearance/Exemption Levels; Mgmt. of Fissile Material; HLW; Dismantling; Reversible/Irreversible Disposal; Waste Avoidance/Minimization; Decontamination; Liquid Waste; Radioactive Waste Processing; Transport of Spent Fuel/HLW; Solid HLW Confinement; QA/QC ◽

10.1115/icem2001-1248 ◽

2001 ◽

Author(s):

Kazuyuki Kato ◽

Osamu Amano ◽

Takao Ikeda ◽

Hideji Yoshida ◽

Hiroyasu Takase

Keyword(s):

Safety Assessment ◽

System Development ◽

Probability Density Functions ◽

Density Functions ◽

Data Sets ◽

Assessment Methodology ◽

Membership Functions ◽

Fuzzy Membership Functions ◽

High Level ◽

Support Decision Making

Abstract This paper presents a unified methodology to handle variability and ignorance by using probabilistic and possibilistic techniques respectively. The methodology has been applied to the safety assessment of geological disposal of high level radioactive waste. Ignorances associated with scenarios, models and parameters were defined in terms of fuzzy membership functions derived through a series of interviews to the experts, while variability was formulated by means of probability density functions (pdfs) based on available data sets. The exercise demonstrated the applicability of the new methodology and, in particular, its advantage in quantifying ignorances based on expert opinion and in providing information on the dependence of assessment results on the level of conservatism. In addition, it was shown that sensitivity analysis can identify key parameters contributing to uncertainties associated with results of the overall assessment. The information mentioned above can be utilized to support decision making and to guide the process of disposal system development and optimization of protection against potential exposure.

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