• 제목/요약/키워드: safety experiment

검색결과 2,242건 처리시간 0.03초

교차로 인지와 방향지시등 조작 지점에 관한 검토 (Position of Intersection Recognition and Tum Signal Operation Approaching at Target Intersection)

  • 전용욱
    • 한국안전학회지
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    • 제24권3호
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    • pp.65-70
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    • 2009
  • In-vehicle route guidance information(RGI) systems have been developed with the advancement of the information and communication technologies. However, the RGI is provided by a pre-determined option, drivers occasionally pass the target intersection owing to non- or late- recognizing it. The purpose of this experiment is to examine the position of driver's tum signal operation and intersection recognition approaching at the target intersection which is difficult to identify as a preliminary research on developing the additional RGI connecting with the tum signal control. The field experiment was conducted to measure distances of the turn signal operation and intersection recognition from the target intersection according to driving lanes and landmarks at adjacent intersection. And, glance behavior to the car navigation display was evaluated by using an eye camera. The results indicate that drivers operate the turn signal after confirming a landmark in the case of the intersection with it. However, most case of driving, drivers operate the tum signal at 40 to 50m before coming to the target. To provide the additional RGI, when drivers do not operate the tum signal approaching at the target intersection based on the results, is expected to improve the traffic safety and the comfort for drivers.

배관 용접부 표면결함 검출 및 비교 (Detection and Comparison of Surface Defects in Pipe Welds)

  • 정윤수;고가진;안태형;김재열
    • 한국기계가공학회지
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    • 제19권1호
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    • pp.43-48
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    • 2020
  • At present, 24 nuclear power plants are in operation nationwide as the main power source responsible for about 27% of Korea's electricity, and five nuclear power plants are currently under construction. Issues of nuclear safety and reliability have always existed, but after the Fukushima accident, ensuring reliability has become an even more important issue for safety. Compared to other kinds of accidents, the initial response after a nuclear accident is more important than any other accident. Prior to accidents, it is important to be able to predict and judge the accident in advance for the sake of prevention. In this research, non-destructive inspection methods for existing pipe welds include radiographic, ultrasonic, magnetic particle practice, and liquid penetration testing. For this experiment, carbon steel pipes like that of the material used in nuclear pipes were adopted, and specimen welded to the flange (Flange) were manufactured. After testing, the weld specimen were not damaged through the infrared thermography (IRT) experiment. This study attempted to improve the safety of carbon steel pipes through a comparative analysis of finite element analysis.

An Investigation of Downcomer Boiling Effects During Reflood Phase Using TRAC-M Code

  • Chon Woo Chong;Lee Jae Hoon;Lee Sang Jong
    • Journal of Mechanical Science and Technology
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    • 제19권5호
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    • pp.1182-1193
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    • 2005
  • The capability of TRAC-M code to predict downcomer boiling effect during reflood phase in postulated PWR LOCA is evaluated using the results of downcomer effective water head and Cylindrical Core Test Facility (CCTF) experiments, which were performed at JAERI. With a full height downcomer simulator, effective water head experiment was carried out to investigate the applicability of the TRAC-M best estimate LOCA code to evaluate the effective water head with superheated wall temperature in downcomer. In order to clarify the effect of the initial superheat of the downcomer wall on the system and the core cooling behaviors during the reflood phase, two sets of analysis were also performed with a CCTF. Results show that TRAC­M code tends to under-predict downcomer effective water head and core differential pressure. However, the code results show a good agreement with the experimental results in downcomer temperature, heat flux and pressure. Finally, both experiment and calculation showed that the downcomer water head with the superheated downcomer wall is lower than that of the saturated wall temperature.

작업장 바닥 소재와 상태에 따른 지게차 미끄럼 거리 측정 (Slip Distance of Forklift Depending upon floor Materials and Conditions of Worksite)

  • 기도형;신동훈
    • 한국안전학회지
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    • 제20권1호
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    • pp.133-136
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    • 2005
  • The accidents attributed to the forklift have increased as the number of the forklift increases. It is significant that most of the accidents were fatal. This study investigated slip distance of forklift depending upon the floor materials and their conditions in industrial site. For doing this, an experiment was conducted, in which the floor materials and their conditions were adopted as independent variables and the slip distance as dependent variable. Six floor materials included asphalt concrete, two color hardener mortar, epoxy paint and deluxe tile. Two types of floor conditions, wet and dry, were used in the experiment. The results showed that the slip distance was shorter on the asphalt and concrete floors than on other floors, and that the distance on the wet floor was six times longer than that on the dry condition. Based on this result, it is recommended that as in the advanced countries, the regulation or standard on the floor conditions such as friction coefficient be established for reducing forklift relevant accidents.

밀폐 박스거더형 무도장 내후성강 교량의 부식취약부에 대한 방식대책 연구(II) (The anti-corrosion study on the corrosion-sensitive areas of unpainted weathering steel bridges with closed box girder(II))

  • 송창영;이의호;이제현;박현출;최재석;노영태
    • Corrosion Science and Technology
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    • 제12권4호
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    • pp.191-197
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    • 2013
  • This study is the second stage of developing the corrosion control technical manual about unpainted weathering steel bridge with closed box girder structures. This paper contains selection of corrosive sealant to apply into crevice of upper flange, injecting test of sealant at mock-up equipment with various condition, evaluation of experiment result. Through the experiment of injection of sealants into crevice of mock-up equipment, it is proved that the tar sealant injecting corrosion control method is useful to protect corrosion at box girder upper flange corroded by remaning rain water with calcium chloride.

RESEARCH ACTIVITIES ON A SUPERCRITICAL PRESSURE WATER REACTOR IN KOREA

  • Bae, Yoon-Yeong;Jang, Jin-Sung;Kim, Hwan-Yeol;Yoon, Han-Young;Kang, Han-Ok;Bae, Kang-Mok
    • Nuclear Engineering and Technology
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    • 제39권4호
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    • pp.273-286
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    • 2007
  • This paper presents the research activities performed to date for the development of a supercritical pressure water-cooled reactor (SCWR) in Korea. The research areas include a conceptual design of an SCWR with an internal flow recirculation, a reactor core conceptual design, a heat transfer test with supercritical $CO_2$, an adaptation of an existing safety analysis code to the supercritical pressure condition, and an evaluation of candidate materials through a corrosion study. Methods to reduce the cladding temperature are introduced from two different perspectives, namely, thermal-hydraulics and core neutronics. Briefly described are the results of an experiment on the heat transfer at a supercritical pressure, an experiment that is essential for the analysis of the subchannels of fuel assemblies and the analysis of a system safety. An existing system code has been adapted to SCWR conditions, and the process of a first-hand validation is presented. Finally, the corrosion test results of the candidate materials for an SCWR are introduced.

Evaluation of effectiveness of fault-tolerant techniques in a digital instrumentation and control system with a fault injection experiment

  • Kim, Man Cheol;Seo, Jeongil;Jung, Wondea;Choi, Jong Gyun;Kang, Hyun Gook;Lee, Seung Jun
    • Nuclear Engineering and Technology
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    • 제51권3호
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    • pp.692-701
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    • 2019
  • Recently, instrumentation and control (I&C) systems in nuclear power plants have undergone digitalization. Owing to the unique characteristics of digital I&C systems, the reliability analysis of digital systems has become an important element of probabilistic safety assessment (PSA). In a reliability analysis of digital systems, fault-tolerant techniques and their effectiveness must be considered. A fault injection experiment was performed on a safety-critical digital I&C system developed for nuclear power plants to evaluate the effectiveness of fault-tolerant techniques implemented in the target system. A software-implemented fault injection in which faults were injected into the memory area was used based on the assumption that all faults in the target system will be reflected in the faults in the memory. To reduce the number of required fault injection experiments, the memory assigned to the target software was analyzed. In addition, to observe the effect of the fault detection coverage of fault-tolerant techniques, a PSA model was developed. The analysis of the experimental result also can be used to identify weak points of fault-tolerant techniques for capability improvement of fault-tolerant techniques

밀폐도 및 밀집도의 영향에 따른 가스폭발 실험 연구 (Experimental Study on Gas Explosion According to the Effect of Confinement and Congestion Levels)

  • 방부형
    • 한국가스학회지
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    • 제27권4호
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    • pp.56-61
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    • 2023
  • 플랜트는 사회기반시설로써 중요한 보호시설이고, 여기서 발생 가능한 가스 누출 및 폭발과 같은 사고에 대한 안전성 확보는 설계 시 반드시 고려해야 한다. 하지만 플랜트에서의 폭발압력에 대한 연구는 경제성 등의 이유로 거의 없으며, 이에 대한 데이터가 부족한 실정이다. 본 연구에서는 플랜트에서 발생할 수 있는 폭발 시나리오를 고려한 실험 설계안을 제시하고 폭발 실험을 통해 폭압을 확인하였다. 가연성 물질로 수소-메테인 혼합 가스가 이용되었으며, 밀폐도와 밀집도가 폭압에 주는 영향에 대해 연구하였다. 밀폐도에 따라 압력파의 중첩이 폭압에 주는 영향과 밀집도에 따른 난류 영향을 구분하여 논의한다. 본 연구에서의 결과는 다양한 안전설계 시 입력자료로 활용될 수 있다.

내진설계용 편심방식 가지배관 고정장치의 좌굴 실험 (Buckling Experiment of Eccentric Seismic Bracing Devices for Branch Lines)

  • 오창수;김지훈;공하성
    • 대한안전경영과학회지
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    • 제26권1호
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    • pp.9-14
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    • 2024
  • Restraints of Branch Lines are used as earthquake-resistant support devices for fire-fighting pipes along with sway brace devices. The central types are aligned and fixed in a straight line with center of the pipe, but the eccentric types are fixed to on side of the pipe, so a bending moment occurs. In this study, three specimens each of central type and eccentric type were installed at an angle of 45° from the vertical and a monotonic compression load of 1340N was applied. All central type samples satisfied 17.8mm of the allowable displacement, but all eccentric type samples failed to meet the target load and buckled. Therefore, when considering the performance of eccentric type restraints, both compressive load and bending moment must be considered. Even through material mechanics calculations, the yield stress of eccentric type - 3/8 inch all threaded steel bolt - exceeds 320Mpa of the allowable stress. A experiment standards need to be established for eccentric type restraints.

안테나를 이용한 몰드변압기 절연결함 측정기법 연구 (Measurement and Analysis of Insulation Detects of Cast-resin Transformers using Antenna)

  • 최명일;김재진;한가람;전정채;이현옥
    • 전기학회논문지
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    • 제65권11호
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    • pp.1937-1942
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    • 2016
  • Unlike oil immersed transformers, cast-resin transformers have the solid insulator 'epoxy resin' in sealed structure. Therefore, they reveal a lot of limitations in checking aging conditions and predicting an accident. This study analyzed the characteristics of Cast-resin transformers by the measurement distance and measurement sensitivity with a corona defect sample, using antenna sensor. Therefore, the experiment has proven that the antenna sensor-based measurement method proposed in this study is able to detect the insulation defect location of the cast-resin transformer, unlike conventional measurement methods. It is expected that the result of this study will be used to develop a new type of measuring method in order to measure insulation defects and to use in safety inspection of domestic cast-resin transformers.