• Journal of the Korean Society of Safety
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• v.5 no.2
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• pp.50-57
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• 1990

A new technique for the measurement of surface roughness based on the intensity fluctuations of laser light backscattered from a moving surface has been introduced. This paper reports a method of measuring surface roughness using coherent optics and interferometry. Included are both the theory of the technique and experimental verification. The range of surface roughness which can be accurately measured by this method is also reported.

• Journal of Korean Society of Industrial and Systems Engineering
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• v.19 no.38
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• pp.61-68
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• 1996

Quality Assurance Principles must be effectively implemented in developments and in use of safety critical software in nuclear industry. Brief definitions related to computer software and quality assurance were defined and several methods for evaluating software quality were proposed herewith. Independent verification and validation was suggested to assure the quality of safety critical software.

• Proceedings of the Safety Management and Science Conference
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• 2008.11a
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• pp.161-165
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• 2008

This paper introduces three continuous sampling plans by attribute. Revised KS standards for acceptance samplings such as KSA ISO 2859-3, 4 : 2001 and 21247 : 2007 are presented. These plans are based on skip-lot, DQL(Declared Quality Level) and VL (Verification Level).

• Journal of the Korean Society of Safety
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• v.17 no.2
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• pp.92-99
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• 2002

Safety-related motor operated valve(MOV) safety significance for Ulchin Unit 3 was categorized. The safety evaluation of MOV of domestic nuclear power plants affects the generic data used for the quantification of MOV common cause failure(CCF) events in Ulchin Units 3&4 PSA. Therefore, in this paper, MGL(multiple greek letter)parameter ${\beta}$, used for the evaluation of MOV CCF probabilities in Ulchin Units 3&4 probabilistic safety assessment(PSA), was re-estimated and the MOV safety significance was categorized. The re-estimation results of MGL parameter show that the value of(is decreased by 30% compared with the current value used in Ulchin Unit 3&4 PSA. The categorization results of MOV safety significance using the changed value of MGL parameter(show that the number of HSSCs(high safety significant components) is decreased by 54.5% compared with those using the current value of it used in Ulchin Units 3&4 PSA.

• Proceedings of the Earthquake Engineering Society of Korea Conference
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• 2000.04a
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• pp.3-16
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• 2000

The ultimate safety-goal of nuclear power plants should be targeted at preventing release of nuclear radiation compared to general structures, Accordingly the phases of siting design construction and operation of NPPs are severely regulated by codes of aseismic design so as to assure safety of NPPs. To accomplish this goal strict quality assurace and seismic qualification tests should be conducted for all phases of NPP construction. In addition seismic monitoring systems should be installed and always in operation to provide proper post-earhquake procedures. Besides periodic safety review should be performed during operation along with the seismic margin assessment. In this paper general procedures to secure seismic safety of NPPs are systematically reviewed and additional considerations for improvement are suggested.

• Proceedings of the Safety Management and Science Conference
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• 2012.11a
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• pp.473-485
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• 2012

최근 현대사회는 자동차, 철도 및 항공 등 대형 복합 시스템의 체계 속에서 지내고 있으며, 고장 및 사고로 인한 시스템의 안전 설계에 대한 고려와 안전에 대한 인식이 증가하고 있다. 따라서 기존의 시스템공학 프로세스에서 다루는 시스템 설계에 대한 단계별 안전 활동의 강화의 필요성 역시 강조되고 있다. 그 중에서도 시스템 설계의 최종 활동에 해당하는 검증 단계 활동이 제대로 수행되어야만 초기에 의도한 시스템 설계의 안전도 향상을 바라볼 수 있을 것이다. 본 논문에서는 안전 활동을 고려한 시스템공학 프로세스의 검증 단계의 개선사항 도출과 모델링을 통해 안전중시 시스템인 철도 차량 운전실 시스템을 대상으로 적용 및 조정 구축에 대한 내용을 기술하고 있다. 본 연구의 결과를 토대로 향후 품질 향상 및 비용 절감과 데이터의 관리 및 추적기능을 개선함으로써 안전사고 발생 가능성을 줄일 수 있을 것으로 기대된다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.233-238
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• 1997

본 논문에서는 Safety-critical 소프트웨어를 위한 V'||'&'||'V 지침서(guideline) 개발 방법론을 제시한다. 즉, 기존의 산업계 표준인 IEEE Std-1012, IEEE Std-1059에서 논의되고 있는 개념을 근간으로 "독립성(independence)", "소프트웨어 안전성 분석(software safety analysis)", "COTS 평가(evaluation) 기준", "다른 보증(assurance) 조직들간의 관련성(relationship)" 등의 필수 안전 항목들을 추가하여 원전 안전성 시스템(NPP safety system)을 위한 V'||'&'||'V 지침서 개발 방법론을 제시하였다 제시된 방법론에는 V'||'&'||'V 지침서의 범위(scope), 승인기준(acceptance criteria) 부분인 지침서 프레임(guideline framework), V'||'&'||'V activities 및 methods 부분인 타스크(task) entrance 및 exit 기준(criteria), 리뷰 및 감사(review and audit), 테스팅 그리고 V'||'&'||'V material의 QA 레코드(records) 및 형상관리, 소프트웨어 검증 및 확인 계획서(Software Verification and Validation Plan : SVVP) 생성 등의 내용을 기술하고, Safety-critical 소프트웨어 V'||'&'||'V 방법론도 함께 제시하였다.

• Journal of Electrical Engineering and Technology
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• v.2 no.3
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• pp.386-390
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• 2007

At recent times, an essential issue in the replacement of the old analogue I&C to computer-based digital systems in nuclear power plants becomes the quantitative software reliability assessment. Software reliability models have been successfully applied to many industrial applications, but have the unfortunate drawback of requiring data from which one can formulate a model. Software that is developed for safety critical applications is frequently unable to produce such data for at least two reasons. First, the software is frequently one-of-a-kind, and second, it rarely fails. Safety critical software is normally expected to pass every unit test producing precious little failure data. The basic premise of the rare events approach is that well-tested software does not fail under normal routine and input signals, which means that failures must be triggered by unusual input data and computer states. The failure data found under the reasonable testing cases and testing time for these conditions should be considered for the quantitative reliability assessment. We presented the quantitative reliability assessment methodology of safety critical software for rare failure cases in this paper.

• The Transactions of the Korean Institute of Electrical Engineers P
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• v.65 no.4
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• pp.242-249
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• 2016

The railway system is being converted to the computer system from the existing mechanical device, and the dependency on software is being increased rapidly. Though the size and degree of complexity of software for railway system are slower than the development speed of hardware, it is expected that the size will be grown bigger gradually and the degree of complexity will be increased also. Accordingly, the validation of reliability and safety of embedded software for railway system was started to become influential as the important issue. Accordingly, various software test and validation activities are highly recommended in the international standards related railway software. In this paper, we presented a software coding analysis tool using symbolic execution for railway system, and presented its result of implementation.

• Proceedings of the Korean Society for Technology of Plasticity Conference
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• 2002.05a
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• pp.98-102
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• 2002

As the nuclear power plant has been operated continuously and increased gradually, transportation and storage of spent fuel are seriously considered nowadays. The transportation cask which contains radioactive material needs to be inspected about structural safety. About safety verification, description of IAEA Safety Standards states that cask must withstand hypothetical accident conditions. In this paper, 9m free drop impact analysis was performed for transportation cask and impact limiter by using the finite element methods. Furthermore, we obtained the dynamic behavior of wood to as compared with safety test results, and verified the safety of transportation cask.