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An Optimized V&V Methodology to Improve Quality for Safety-Critical Software of Nuclear Power Plant
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 Title & Authors
An Optimized V&V Methodology to Improve Quality for Safety-Critical Software of Nuclear Power Plant
Koo, Seo-Ryong; Yoo, Yeong-Jae;
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 Abstract
As the use of software is more wider in the safety-critical nuclear fields, so study to improve safety and quality of the software has been actively carried out for more than the past decade. In the nuclear power plant, nuclear man-machine interface systems (MMIS) performs the function of the brain and neural networks of human and consists of fully digitalized equipments. Therefore, errors in the software for nuclear MMIS may occur an abnormal operation of nuclear power plant, can result in economic loss due to the consequential trip of the nuclear power plant. Verification and validation (V&V) is a software-engineering discipline that helps to build quality into software, and the nuclear industry has been defined by laws and regulations to implement and adhere to a through verification and validation activities along the software lifecycle. V&V is a collection of analysis and testing activities across the full lifecycle and complements the efforts of other quality-engineering functions. This study propose a methodology based on V&V activities and related tool-chain to improve quality for software in the nuclear power plant. The optimized methodology consists of a document evaluation, requirement traceability, source code review, and software testing. The proposed methodology has been applied and approved to the real MMIS project for Shin-Hanul units 1&2.
 Keywords
Safety-Critical Software;Verification & Validation;Quality;Traceability;Testing;
 Language
Korean
 Cited by
 References
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