• 한국철도학회논문집
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• 제8권4호
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• pp.354-360
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• 2005

The railway track and the substructures constructed in the field test section of Kyongbu High Speed Line are the structures for HSL, for the first time designed and constructed by domestic technical group. It is very important to verify the local design criteria and specifications for these structures and also to assure the recordings for vibration or deflection produced on the essential parts of the structures. The study to verify the high-speed railway track performance and to ensure the run in safety on the track in curved section during the KTX run. Finally, the conclusion are drawn as follows. The measuring values of the deflection effort of the rail and displacement for verifying the track performance in the field test section of Kyoungbu HSL satisfy the criteria of the foreign countries (Japan and Germany). The measured value for the wheel load and the presumed value show the consistent tendency. The wheel loads of the exterior and interior of the rails at the speed superior to 300km/h are measured same. Finally, the comparison between the theoretical value presented during the verification of the derailment to evaluate the safety of the train run at the time of the detailed design of the track and the measured value in the field shows that the correct design of track structure was applied.

• 한국압력기기공학회 논문집
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• 제10권1호
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• pp.25-30
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• 2014

Korea Hydro & Nuclear Power Co.,LTD(KHNP) was strongly interested in promotion of employee's Safety Culture because it is needed to change the recognition of Safety Culture after the Fukushima accident and Kori-1 blackout event. So, KHNP developed the KHNP Safety Culture Definition, Principles and Attributes and shared them with all employees. By using them, Safety Culture Assessment for a site plant employees was carried out. Through the pilot Safety Culture Assessment in 2012, In 2013, it was expanded to 6 plants and various improvements had been obtained from that. KHNP has been developing a variety of training materials, Safety Culture posters, videos which was designed to give lessons about safety culture with a variety of event cases. And keep trying to form Safety Culture Circumstances In this study, statistic methods are used to verify the effectiveness of KHNP Safety Culture Principles and Safety Culture Assessment.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(2)
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• pp.602-607
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• 1995

This article presents safety review experience of microprocessor-based Interposing Logic System(ILS) of Engineering Safety Feature Actuation System(ESFAS). The ILS is the first application of computerized logic design to safety system in Korean nuclear power plants without verification of the system reliability by proven technology concept. As a result of evaluation for the ILS, Korea Institute of Nuclear Safety(KINS) concluded that the microprocessor-based ILS is not acceptable in some features detailed enough to defend against software common mode failures(CMF). Therefore, we required licensee to install hardwired interlock signal configuration and a Hardwired Backup Panel to control safety-related equipment. We believe that the microprocessor-based ILS with the hardwired backup panel and inter-connection of interlock signal by hardwired configuration will improve the plant safety.

• 대한설비공학회:학술대회논문집
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• 대한설비공학회 2009년도 하계학술발표대회 논문집
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• pp.745-750
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• 2009

In Korea, since the implementation of the GMO Law, the intrest of biosafety level 3(BL3) lab. is increasing. In this study, using CONTAM which is applying multizone modelling, the multizone simulation for design verification of BL3 lab. was performed. In BL3 lab., because required air change rate is greater than general estimated air-conditioning load and it is difficult to maintain room pressure difference efficiently, to maintain pressure difference between laboratory rooms is important through sealing condition of doors and proper airflow control of laboratory rooms. In this study, about BL3 lab.(M. tuberculosis research lab.), the multizone simulation for four kind of biohazard scenarios was performed in the case of unexpected spread of contaminants in the laboratory room, anteroom, corridor and inside of BSC. Multizone simulation results show that these approach methods are used as a tool for the design and verification of BL3 lab.

• 한국융합학회논문지
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• 제10권11호
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• pp.95-100
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• 2019

본 논문은 자율 주행차량의 운행과 더불어 기존 차량 사고 방지를 위한 차량 간 통신 기술, 자율주행 기술, 브레이크 자동 제어 기술, 인공지능 기술 등이 널리 개발되고 있다. 차량 사고 발생이 일어나더라도 사망이나 부상을 최소화하기 위한 각종 기술들의 안전성의 상용화에 있다. 본 논문의 경우 자율주행 차량시, 안전성 확보연구이다. 이는 일반적인 저전력 근거리 무선 통신용 칩 신호나 초소형 도로 AI 장착 등의 공간적 요소에 따라 판별한다. 반면 본 논문은 상기 전자 칩의 신호를 읽는 데에서 생체 전자 칩까지의 "감지영역 내 체류 시간인식, 민감도"까지 체크하여 승차한 안전의 신뢰성을 높인다. 실제 세계 각국의 신뢰성을 실증한 결과로서, 안전성면에서 탑승객 전원의 안전 자율 시스템을 유도한다. 무인 자율차량 탑승과 상용화는 가까운 미래에 도로위 IoT의 AI 시스템과 생체 칩(Verification emotion + Chip)으로의 연계성면에서 그 진보성의 실증결과, 세계 각국의 안전 기술신뢰성은 더욱 부각된다.

• 한국시뮬레이션학회논문지
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• 제24권4호
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• pp.1-9
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• 2015

원자력 분야에서 안전관련(safety-related) 소프트웨어의 활용이 점차 확대됨에 따라서, 그에 상응하는 소프트웨어 안전과 신뢰도 향상을 위한 방안 연구가 지난 10여년 전부터 활발히 진행되고 있다. 원전 계측제어시스템(MMIS)은 원자력 발전소의 두뇌와 신경망에 해당하는 기능을 수행하고 있고 첨단 디지털 장비들로 구성된다. 따라서 원전 계측제어시스템의 소프트웨어 오류는 원자력 발전소 운전에 지장을 초래할 수 있고, 오동작으로 인한 발전소 정지로 경제적 손실을 초래할 수 있다. 소프트웨어 확인 및 검증(verification and validation, V&V)은 소프트웨어 품질을 향상시킬 수 있는 소프트웨어 공학의 분야로 알려져 있고, 원자력 산업계에서는 소프트웨어 생명주기에 따른 철저한 V&V 활동을 이행하고 준수할 것을 법규로 규정하고 있다. V&V 활동은 소프트웨어 전 생명주기에 따라 분석과 시험 활동들의 조합으로 다른 품질관련 공학 업무를 보완하는 역할을 한다. 본 논문에서는 명세 평가, 요건 추적, 소스코드 리뷰, 및 소프트웨어 시험을 통한 최적화된 안전관련 소프트웨어 V&V 방법론에 기반한 소프트웨어 품질 향상 방안과 단계별로 적합한 도구를 활용하여 효율성을 확보할 수 있는 방안을 제시하고자 한다. 제안된 방법론은 실제 신한울 1,2호기 원자력발전소 MMIS 시스템에 적용되어 입증되었다.

• Journal of Radiation Protection and Research
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• 제44권3호
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• pp.118-126
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• 2019

Background: Government conducts environmental radioactivity surveillance for verification purpose around nuclear facilities based on the Nuclear Safety Law and issues a surveillance report every year. This study aims to evaluate the short and the long-term fluctuation of radionuclides detected above MDC and their origins using concentration ratios between these radionuclides. Materials and Methods: Sample media for verification surveillance are air, rainwater, groundwater, soil, and milk for terrestrial samples, and seawater, marine sediment, fish, and seaweed for marine samples. Gamma-emitting radionuclides including $^{137}Cs$, $^{90}Sr$, Pu, $^3H$, and $^{14}C$ are evaluated in these samples. Results and Discussion: According to the result of the environmental radioactivity verification surveillance in the vicinity of nuclear power facilities in 2017, the anthropogenic radionuclides were not detected in most of the environmental samples except for the detection of a trace level of $^{137}Cs$, $^{90}Sr$, Pu, and $^{131}I$ in some samples. Radioactivity concentration ratios between the anthropogenic radionuclides ($^{137}Cs/^{90}Sr$, $^{137}Cs/^{239+240}Pu$, $^{90}Sr/^{239+240}Pu$) were similar to those reported in the environmental samples, which were affected by the global fallout of the past nuclear weapon test, and Pu atomic ratios ($^{240}Pu/^{239}Pu$) in the terrestrial sample and marine sample showed significant differences due to the different input pathway and the Pu source. Radioactive iodine ($^{131}I$) was detected at the range of < $5.6-190mBq{\cdot}kg-fresh^{-1}$ in the gulfweed and sea trumpet collected from the area of Kori and Wolsong intake and discharge. A high level of $^3H$ was observed in the air (Sangbong: $0.688{\pm}0.841Bq{\cdot}m^{-3}$) and the precipitation (Meteorology Post: $199{\pm}126Bq{\cdot}L^{-1}$) samples of the Wolsong nuclear power plant (NPP). $^3H$ concentration in the precipitation and pine needle samples showed typical variation pattern with the distance and the wind direction from the stack due to the gaseous release of $^3H$ in Wolsong NPP. Conclusion: Except for the detection of a trace level of $^{137}Cs$, $^{90}Sr$, Pu, and $^{131}I$ in some samples, anthropogenic radionuclides were below MDC in most of the environmental samples. Overall, no unusual radionuclides and abnormal concentration were detected in the 2017's surveillance result for verification. This research will be available in the assessment of environment around nuclear facilities in the event of radioactive material release.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 2000년도 추계 학술발표회 논문집 Proceedings of EESK Conference-Fall 2000
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• pp.215-223
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• 2000

In this study, the effect of stiffness ratio between base frame and anchorgae is evaluated and the seismic verification of nuclear power plant equipment anchorage is performed for typical equipment. The stiffness ratio between base frame and anchorage is mainly controlled by the effective height of side wall plate. And, the change of that stiffness ratio cause the large shift or ovreturning axis of equipment base. This shift of overturning axis of equipment base is able to reduce the factor of safety about 10%. Therefore, the adequate method for evaluating of effective height of side wall is required as further study.

• 한국철도학회:학술대회논문집
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• 한국철도학회 2005년도 추계학술대회 논문집
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• pp.125-130
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• 2005

The railway shall be verified with the view point of dynamic performances before delivering to the Customer and the verification procedure shall be followed the Customer's demands or relevant international standard, UIC 518 (Testing and approval of railway vehicles from the point of view of their dynamic behavior-Safety-Track fatigue-Ride quality). In this paper, verification procedures in UIC 518 and the test results for domestic project are summarized.

• 한국철도학회:학술대회논문집
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• 한국철도학회 2004년도 추계학술대회 논문집
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• pp.192-199
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• 2004

In this paper the arthurs introduce the performance verification for Korea high-speed rail system developed at G7 project, how to draw basic provision requirements in the process of construction of national safety criteria certification system, and definition of basic requirements to make safety criteria at each subsystem and technology field in the future.