• Title/Summary/Keyword: Safety Integrity

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Design and Verification of the Hardware Architecture for the Active Seat Belt Control System Compliant to ISO 26262 (ISO 26262에 부합한 능동형 안전벨트 제어 시스템의 하드웨어 아키텍처 설계 및 검증)

  • Lee, Jun Hyok;Koag, Hyun Chul;Lee, Kyung-Jung;Ahn, Hyun-Sik
    • The Transactions of The Korean Institute of Electrical Engineers
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    • v.65 no.12
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    • pp.2030-2036
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    • 2016
  • This paper presents a hardware development procedure of the ASB(Active Seat Belt) control system to comply with ISO 26262. The ASIL(Automotive Safety Integrity Level) of an ASB system is determined through the HARA(Hazard Analysis and Risk Assessment) and the safety mechanism is applied to meet the reqired ASIL. The hardware architecture of the controller consists of a microcontroller, H-bridge circuits, passive components, and current sensors which are used for the input comparison. The required ASIL for the control systems is shown to be satisfied with the safety mechanism by calculation of the SPFM(Single Point Fault Metric) and the LFM(Latent Fault Metric) for the design circuits.

Design of EMI reduction of Electric Vehicle Wireless Power Transfer Wireless Charging Control Module with Power Integrity and Signal Integrity (전원무결성과 신호무결성을 갖는 전기차 무선전력전송 무선충전컨트롤모듈 EMI 저감 설계)

  • Hong, Seungmo
    • The Journal of Korea Institute of Information, Electronics, and Communication Technology
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    • v.14 no.6
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    • pp.452-460
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    • 2021
  • As the global electric vehicle (EV) market expands, eco-friendly EV that complement performance and safety problems continue to be released and the market is growing. However, in the case of EVs, the inconvenience of charging, safety problems such as electric shock, and electromagnetic interference (EMI) problems caused by the interlocking of various electronic components are problems that must be solved in EVs. The use of wireless power transmission technology can solve the problem of safety by not dealing with high current and high voltage directly and solving the inconvenience of charging EVs. In this paper, in order to reduce EMI a wireless charging control module, which is a key electronic component of WPT of EV. EMI reduction was designed through simulation of problems such as resonance and impedance that may occur in the power supply and signal distortion between high-speed communication that may occur in the signal part. Therefore, through the EMI reduction design with power integrity and signal integrity, the WPT wireless charging control module for electric vehicles reduces 10 dBu V/m and 15 dBu V/m, respectively, in 800 MHz to 1 GHz bands and 1.5 GHz bnad.

Anomaly Detection Technique of Satellite on Network RTK (Network RTK 환경에서 위성에 의한 이상 검출 기법)

  • Shin, Mi Young;Cho, Deuk Jae;Yoo, Yun-Ja;Hong, Cheol-Ye;Park, Sang-Hyun
    • Journal of Navigation and Port Research
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    • v.37 no.1
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    • pp.41-48
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    • 2013
  • A positioning technique using the augmentation system has been researched to improve the accuracy. The network RTK is the precise positioning technique using carrier phase correction data from reference stations and is constantly being researched. The study for the system accuracy has been performed but system integrity research has not been done as much as system accuracy. In this paper, we presented the anomaly detection algorithm by satellite system and the diagnosis algorithm to a basic research in the integrity on network RTK. And the presented algorithms are verified on the DL-V3 dual-frequency receiver and the simulated error scenario using the GSS7700.

Design of Monitoring System for Network RTK (네트워크 RTK 환경에 적합한 감시 시스템 설계)

  • Shin, Mi-Young;Han, Young-Hoon;Ko, Jae-Young;Cho, Deuk-Jae
    • Journal of Navigation and Port Research
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    • v.39 no.6
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    • pp.479-484
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    • 2015
  • Network RTK is a precise positioning technique using carrier phase correction data from reference stations within the network, and is constantly being researched for improved performance. However, the study for the system accuracy has been performed but system integrity research has not been done as much as system accuracy, because network RTK has been mainly used on surveying for static or kinematic positioning. In this paper, adequate monitoring system for network RTK is designed as basis research for integrity monitoring on network RTK. To this, fault tree on network RTK is analyzed, and a countermeasure is prepared to detect and identify the each fault items. Based these algorithms, monitoring system to use on central processing facility is designed for network RTK service.

Evaluation of Degraded Materials by Automated Ball Indentation(ABI) Technique (압입법을 이용한 재료의 열화도 평가)

  • 김석민;석창성;이승석;권재도
    • Journal of the Korean Society of Safety
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    • v.15 no.1
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    • pp.28-35
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    • 2000
  • As huge energy transfer systems like a nuclear power plant, steam power plant and petrochemical plant are operated for a long time, mechanical properties are changed by degradation. The life time of the systems can be affected by the mechanical properties. So determination of the integrity of the metallic structure is required either to en4sure that failure will not occur during the service life of the components or to evaluate the lifetime extension of the structure. An automated ball indentation(ABI) method was developed as a non-destructive technique for evaluating the integrity of such metallic components. In this paper, we would like to present the aging evaluation technique by the ABI method. The five classes of the thermally aged CF8M specimens were prepared using an artificially accelerated aging method. After holding 100, 300, 900, 1800 and 3600 hours at 43$0^{\circ}C$, the specimens were cooled down using water to room temperature respectively. The tensile test, hardness test, charpy impact test, ABI test were performed. The results of the fracture test were compared with those of ABI test and the new evaluation technique of the integrity of metallic structures was developed.

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A Study on HIGH TEMPERATURE FRACTURE TOUGHNESS of Pressure Vessel Steel SA516 at High Temperature. (압력용기용강의 고온파괴인성에 관한 연구)

  • 박경동;김정호
    • Proceedings of the KWS Conference
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    • 2001.05a
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    • pp.228-231
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    • 2001
  • Elastic-plastic fracture toughness $J_{1c}$ can be used as an effective design criterion in elastic plastic fracture mechanics. Most of these systems are operated at high temperature and $J_{1c}$ values are affected by temperature. therefore, the $J_{1c}$ valuse at high temperature must be determined for use of integrity evaluation and designing of such systems. Elastic-plastic fracture toughness $J_{1c}$ tests were performed on SA516 carbon steel plate and test results were analyzed according to ASTM E 813-8, ASTM 1813-89. Safety and integrity are required for reactor pressure vessels vecause pthey are operated in high temperature. there are single specimen method, which used as evaluation of safety and integrity for reactor pressure vessels. In this study, elastic-plastic fracture toughness$(J_{1c})$ and $J-\Delta{a}$ of SA 516/70 steel used as reactor pressure vessel steel are measured and evaluated at room Temperature, $150^{\circ}C$, $250^{\circ}C$ and $370^{\circ}C$ according to unloading compliance method.

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Evaluation on High Temperature Fracture toughness of Pressure Vessel SA516/70 Steel (압력용기용 SA516/70강의 고온파괴인성평가)

  • 박경동;김정호;윤한기;박원조
    • Journal of Ocean Engineering and Technology
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    • v.15 no.2
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    • pp.99-104
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    • 2001
  • Elastic-plastic fracture toughness $J_{lc}$ can be used as an effective design criterion in elastic plastic fracture mechanics. Most of these systems are$J_{lc}$ $J_{lc}$ value at high temperature must be determined for use of integrity evaluation and designing of such systems. Elastic-plastic fracture toughness $J_{lc}$ tests were performed on SA516/70 carbon steel plate and test results were analyzed according to ASTM E 813-87, ASTM E 813-89 and ASTM E 1152-87.safety and integrity are required for reactor pressure vessels because, they are operated in high temperature. There are single specimen method, which used as evaluation of safety and integrity for reactor pressure vessels. In this study, elastic-plastic fracture toughness($J_{lc}$) and J-$\Delta$a of SA 516/70 steel used as reactor pressure vessel steel are measured and evaluated at room temperature, 150$^{\circ}C $, 250$^{\circ}C $ and 370$^{\circ}C $ according to unloading compliance method.

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Electrical fire simulation in control room of an AGN reactor

  • Jyung, Jae-Min;Chang, Yoon-Suk
    • Nuclear Engineering and Technology
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    • v.53 no.2
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    • pp.466-473
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    • 2021
  • Fire protection is one of important issues to ensure safety and reduce risks of nuclear power plants (NPPs). While robust programs to shut down commercial reactors in any fires have been successfully maintained, the concept and associated regulatory requirements are constantly changing or strengthening by lessons learned from operating experiences and information all over the world. As part of this context, it is necessary not only to establish specific fire hazard assessment methods reflecting the characteristics of research reactors and educational reactors but also to make decisions based on advancement encompassing numerical analyses and experiments. The objectives of this study are to address fire simulation in the control room of an educational reactor and to discuss integrity of digital console in charge of main operation as well as analysis results through comparison. Three electrical fire scenarios were postulated and twenty-four thermal analyses were carried out taking into account two turbulence models, two cable materials and two ventilation conditions. Twelve supplementary thermal analyses and six subsequent structural analyses were also conducted for further examination on the temperature and heat flux of cable and von Mises stress of digital console, respectively. As consequences, effects of each parameter were quantified in detail and future applicability was briefly discussed. On the whole, higher profiles were obtained when Deardorff turbulence model was employed or polyvinyl chloride material and larger ventilation condition were considered. All the maximum values considered in this study met the allowable criteria so that safety action seems available by sustained integrity of the cable linked to digital console within operators' reaction time of 300 s.

Integrity Evaluation for Stud Female Threads on Pressure Vessel according to ASME Code using FEM (유한요소해석에 의한 ASME Code 적용 압력용기 스터드 암나사산의 건전성 평가)

  • Kim, Moon-Young;Chung, Nam-Yong
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.27 no.6
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    • pp.930-937
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    • 2003
  • The extension of design life among power plants is increasingly becoming a world-wide trend. Kori #1 unit in Korea is operating two cycle. It has two man-ways for tube inspection in a steam generator which is one of the important components in a nuclear power plant. Especially, stud bolts fur man-way cover have damaged by disassembly and assembly several times and degradation for bolt materials for long term operation. It should be evaluated and compared by ASME Code criteria for integrity evaluation. Integrity evaluation criteria which has been made by the manufacturer is not applied on the stud bolts of nuclear pressure vessels directly because it is controlled by the yield stress of ASME Code. It can apply evaluation criteria through FEM analysis to damaged female threads and to evaluated safety fer helical-coil method which is used according to Code Case-N-496-1. From analysis results, we found .that it is the same results between stress intensity which got from FEM analysis on damaged female threads over 10% by manufacture integrity criteria and 2/3 yield strength criteria on ASME Code. It was also confirmed that the helical-coil repair method would be safe.