A hybrid approach to quantify software reliability in nuclear safety systems
Creators
- 1. Indira Gandhi Centre for Atomic Research, Kalpakkam 603102 (India)
- 2. Safety Research Institute, Atomic Energy Regulatory Board, Kalpakkam 603102 (India)
Description
Highlights: ► A novel method to quantify software reliability using software verification and mutation testing in nuclear safety systems. ► Contributing factors that influence software reliability estimate. ► Approach to help regulators verify the reliability of safety critical software system during software licensing process. -- Abstract: Technological advancements have led to the use of computer based systems in safety critical applications. As computer based systems are being introduced in nuclear power plants, effective and efficient methods are needed to ensure dependability and compliance to high reliability requirements of systems important to safety. Even after several years of research, quantification of software reliability remains controversial and unresolved issue. Also, existing approaches have assumptions and limitations, which are not acceptable for safety applications. This paper proposes a theoretical approach combining software verification and mutation testing to quantify the software reliability in nuclear safety systems. The theoretical results obtained suggest that the software reliability depends on three factors: the test adequacy, the amount of software verification carried out and the reusability of verified code in the software. The proposed approach may help regulators in licensing computer based safety systems in nuclear reactors.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2012.06.026Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2012.06.026;
- PII
- S0306-4549(12)00261-7;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 50
- Journal Page Range
- p. 133-140
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44100944
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- COMPLIANCE; COMPUTER CODES; COMPUTERS; MUTATIONS; NUCLEAR POWER PLANTS; RADIATION PROTECTION; REACTOR SAFETY; REACTORS; RELIABILITY; TESTING; VERIFICATION
- Descriptors DEC
- NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.