• 제목/요약/키워드: safety technology development

검색결과 3,416건 처리시간 0.049초

개 연골세포의 손상에 의한 Tartrate Resistant Acid Phosphatase 활성의 변화 측정 (The Change of Tartrate Resistant Acid Phosphatase Activity in Capsaicin-Induced Canine Chondrocyte Death)

  • 설재원;이해범;김남수;김인식;강형섭;이영훈;강동원;박상열
    • 한국임상수의학회지
    • /
    • 제23권2호
    • /
    • pp.144-148
    • /
    • 2006
  • Apoptotic death of articular chondrocytes has been implicated in the pathogenesis of osteoarthritis. Tartrate resistant acid phosphatase (TRAP) has been used for several years as a marker enzyme of bone-resorbing osteoclasts. This study investigated the activity of TRAP in media of apoptotic cell death-induced canine chondrocyte. We exposed canine chondrocyte to capsaicin and the results showed that capsaicin induced cell death in a dose dependent manner. And we measured TRAP activity in media of chondrocyte death induced by capsaicin treatment and the results capsaicin significantly increased the activity of TRAP in media for dose dependent. We also investigated whether the combination treatment with capsaicin and TRAIL enhance apoptotic cell death in canine chondrocyte. We exposed canine chondrocyte to capsaicin for 24 hrs at the indicated dose, and then treated with recombinant TRAIL protein for 24 hrs. TRAIL alone did not induce cell death after 24 hours, but the combined treatment of both induced more cell death compared with capsaicin alone in a dose dependent manner. Also, the combination treatment with capsaicin and TRAIL increased the activity of TRAP in culture media. These results suggest that TRAP can flow out into extracellular after chondrocyte damage, and TRAP may be a successful biomarker for detection of joint disease such as osteoarthritis.

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

  • Yoo, Jaewoon;Chang, Jinwook;Lim, Jae-Yong;Cheon, Jin-Sik;Lee, Tae-Ho;Kim, Sung Kyun;Lee, Kwi Lim;Joo, Hyung-Kook
    • Nuclear Engineering and Technology
    • /
    • 제48권5호
    • /
    • pp.1059-1070
    • /
    • 2016
  • The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel. The PGSFR design has been focused on the robustness of safety systems by enhancing inherent safety characteristics of metal fuel and strengthening passive safety features using natural circulation and thermal expansion. The preliminary safety information document as a major outcome of the first design phase of PGSFR development was issued at the end of 2015. The project entered the second design phase at the beginning of 2016. This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper.

CONCEPTUAL DESIGN OF THE SODIUM-COOLED FAST REACTOR KALIMER-600

  • Hahn, Do-Hee;Kim, Yeong-Il;Lee, Chan-Bock;Kim, Seong-O;Lee, Jae-Han;Lee, Yong-Bum;Kim, Byung-Ho;Jeong, Hae-Yong
    • Nuclear Engineering and Technology
    • /
    • 제39권3호
    • /
    • pp.193-206
    • /
    • 2007
  • The Korea Atomic Energy Research Institute has developed an advanced fast reactor concept, KALIMER-600, which satisfies the Generation IV reactor design goals of sustainability, economics, safety, and proliferation resistance. The concept enables an efficient utilization of uranium resources and a reduction of the radioactive waste. The core design has been developed with a strong emphasis on proliferation resistance by adopting a single enrichment fuel without blanket assemblies. In addition, a passive residual heat removal system, shortened intermediate heat-transport system piping and seismic isolation have been realized in the reactor system design as enhancements to its safety and economics. The inherent safety characteristics of the KALIMER-600 design have been confirmed by a safety analysis of its bounding events. Research on important thermal-hydraulic phenomena and sensing technologies were performed to support the design study. The integrity of the reactor head against creep fatigue was confirmed using a CFD method, and a model for density-wave instability in a helical-coiled steam generator was developed. Gas entrainment on an agitating pool surface was investigated and an experimental correlation on a critical entrainment condition was obtained. An experimental study on sodium-water reactions was also performed to validate the developed SELPSTA code, which predicts the data accurately. An acoustic leak detection method utilizing a neural network and signal processing units were developed and applied successfully for the detection of a signal up to a noise level of -20 dB. Waveguide sensor visualization technology is being developed to inspect the reactor internals and fuel subassemblies. These research and developmental efforts contribute significantly to enhance the safety, economics, and efficiency of the KALIMER-600 design concept.

안전방출밸브 개발과 용량인증 사례 (Experience for Development and Capacity Certification of Safety Relief Valves)

  • 김칠성;노희선;김강태;김지헌;김종수
    • 한국유체기계학회 논문집
    • /
    • 제8권3호
    • /
    • pp.16-25
    • /
    • 2005
  • The purpose of this study is localization of safety relief valves for Nuclear Service. The safety relief valve is the important equipment used to protect the pressure vessel, the steam generator and the other pressure facility from overpressure by discharging the operating medium when the pressure of system is reaching the design pressure of the system. We developed design technology used FEM ' CFM about safety relief valve for Nuclear Service according to ASME (or KEPIC) Code and KHNP's Technical Specification. To prove validity of a design technology, actually, we manufactured and inspected and tested the sample products designed according to a developed technology. The capacity qualification test was achieved according to requirement of ASME(or KEPIC) Code by NBBI and the functional qualification test was achieved according to ASME QME-1 for operating condition in technical specification of KHNP by NLI. Therefore we have to achieve the development of safety relief valves for Nuclear Service with our own technologies.

GMO 안전성평가제도의 고찰 (Need for Reinforcement of Safety Assessment on Genetically Modified Organisms)

  • 김은진;최동근
    • 한국유기농업학회지
    • /
    • 제14권2호
    • /
    • pp.139-157
    • /
    • 2006
  • Biotechnology has reached the level of giving birth to new forms of life and with this is a growing controversy in the conflict between science and ethics. Especially, GMOs are closely linked to the food products we consume and thus, the majority of the public shows a very sensitive reaction to the safety of GMO food products. Many perspectives arose surrounding the issues of safety on the human body and the ecology. This outlines diverse structural mechanisms to be set up to ensure safety such as risk assessment, risk management etc. Despite the precautionary principle guaranteed in many ways, the problem arises whether and how this principle can be taken in the safety assessment. GMOs due to its uniqueness do not end with just the possession of the technology involved but must also be considered with the prerequisite that they could be cultured again. Therefore the reinforcement of safety assessment system is necessary. That is, the reinforcement of risk assessment including field tests, the consideration of socio-economic effects, the coordinated system of relevant authorities, the development of technology for safety assessment.

  • PDF

건설현장 근로자의 안전의식과 안전교육 활성화 방안 (A Study for Construction Workers' Safety Consciousness and Safety Education Activation Methods)

  • 정지연;유희종
    • 한국안전학회지
    • /
    • 제28권1호
    • /
    • pp.47-51
    • /
    • 2013
  • This research is the descriptive survey research targeting construction workers for searching a vitalization method on safety education by understanding the real condition of the sense of safety consciousness and the condition of safety education. The collected data of 147 workers are analyzed by using arithmetic mean, t-test, and ANOVA Analysis of Variance through SPSS PC program. This research investigated the real condition of safety consciousness, recognition on safety education, and the differences of safety consciousness depend on the general characteristic of subject. According to the result of the study, development of standardized safety consciousness assessment tool and institutionalization of safety education program is needed.

수소연료전지 자동차 안전성 평가기술 개발 (Development of Safety Assessment for Hydrogen Fuel Cell Vehicle)

  • 용기중;이광범
    • 한국수소및신에너지학회논문집
    • /
    • 제25권5호
    • /
    • pp.500-508
    • /
    • 2014
  • In the ongoing debates over the need to identify new sources of energy and to reduce the emissions of greenhouse gases. Hydrogen has emerged as one of the most promising alternatives due to its emissions from the vehicle being virtually zero. The governments have identified the development of regulations and standards as one of the key requirements for commercialization of HFCV. Regulations and standards will help overcome technological barriers to commercialization. The development of Global Technical Regulation (GTR) for HFCV occurred under the World Forum for Harmonization of Vehicle Regulations. Development of a technique for safety assessment of HFCV include four tasks, research for regulation system and policy, hydrogen safety, vehicle operation safety and protection against high-voltage. The objective is to establish a technique for safety assessment and amend safety standards for HFCV and consequently reflect research results to vehicle management policy. We devised safety standards and evaluation techniques with regard to high-pressure gas and high voltage of hydrogen fuel cell vehicle. KMVSS for HFCV was amended to June 10, 2014. including the results of the safety assessment technology for high-voltage and hydrogen characteristics.

건설업 사고 발생원인 파악을 위한 사고 분석 모델 개발 (Development of Accident Cause Analysis Model for Construction Site)

  • 임원준;기정훈;성주현;박종일
    • 한국안전학회지
    • /
    • 제34권1호
    • /
    • pp.45-52
    • /
    • 2019
  • Accident analysis models were developed to improve the construction site safety and case studies was conducted. In 2016, 86% of fatality accidents occurred due to simple unsafe acts. Structure related accidents are less frequent than the non structure related causes, but the number of casualties per accident is two times higher than non structure one. In the view of risk perception, efforts should be given to reduce accidents caused by low frequency - high consequence structure related causes. In case of structure related accident, structural safety inspection and management (including quality), ground condition management / inspection technology, and provision of risk information delivery system in case of non structure related accident were proposed as a solution. In analysis of relationship between safety related stakeholder, the main problem were the lack of knowledge of controller and player, loss of control due to duplicated controls, lack of communication system of risk information, and relative position error of controller and player.