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      KCI등재

      원전 안전-필수 소프트웨어의 품질향상을 위한 최적화된 확인 및 검증 방안 = An Optimized V&V Methodology to Improve Quality for Safety-Critical Software of Nuclear Power Plant

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      https://www.riss.kr/link?id=A105571461

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      다국어 초록 (Multilingual 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.
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      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 s...

      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.

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      참고문헌 (Reference)

      1 Dyer M, "The Cleanroom Approach to Quality Software Development" John Wiley & Sons 1992

      2 S. Koo, "Software Design Specification and Analysis Technique(SDSAT) for the Development of Safety-Critical Systems Based on a Programmable Logic Controller(PLC)" 91 (91): 648-664, 2006

      3 N. G. Leveson, "Safeware – System Safety and Computers" Addison-Wesley 1995

      4 Storey N, "Safety-Critical Computer Systems" Addison-Wesley 1996

      5 HYUNCHUL HAN, "NuSEE: AN INTEGRATED ENVIRONMENT OF SOFTWARESPECIFICATION AND V&V FOR PLC BASED SAFETYCRITICALSYSTEMS" 한국원자력학회 38 (38): 256-276, 2006

      6 IEEE, "IEEE Standard 1012 for software verification and validation, an American National Standard"

      7 S. Koo, "An Effective Technique for the Software Requirements Analysis of NPP Safety-Critical Systems, Based on Software Inspection, Requirement Traceability, and Formal Specification" 89 (89): 248-260, 2005

      1 Dyer M, "The Cleanroom Approach to Quality Software Development" John Wiley & Sons 1992

      2 S. Koo, "Software Design Specification and Analysis Technique(SDSAT) for the Development of Safety-Critical Systems Based on a Programmable Logic Controller(PLC)" 91 (91): 648-664, 2006

      3 N. G. Leveson, "Safeware – System Safety and Computers" Addison-Wesley 1995

      4 Storey N, "Safety-Critical Computer Systems" Addison-Wesley 1996

      5 HYUNCHUL HAN, "NuSEE: AN INTEGRATED ENVIRONMENT OF SOFTWARESPECIFICATION AND V&V FOR PLC BASED SAFETYCRITICALSYSTEMS" 한국원자력학회 38 (38): 256-276, 2006

      6 IEEE, "IEEE Standard 1012 for software verification and validation, an American National Standard"

      7 S. Koo, "An Effective Technique for the Software Requirements Analysis of NPP Safety-Critical Systems, Based on Software Inspection, Requirement Traceability, and Formal Specification" 89 (89): 248-260, 2005

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2026 평가예정 재인증평가 신청대상 (재인증)
      2020-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2017-01-01 평가 등재학술지 유지 (계속평가) KCI등재
      2013-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2010-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2007-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      2006-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2005-06-22 학술지명변경 외국어명 : 미등록 -> JOURNAL OF THE KOREA SOCIETY FOR SIMULATION KCI등재후보
      2004-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
      2004-01-01 평가 등재후보 탈락 (등재후보1차)
      2002-01-01 평가 등재후보 1차 FAIL (등재후보1차) KCI등재후보
      2000-07-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.3 0.3 0.32
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.28 0.25 0.541 0.11
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