• Title/Summary/Keyword: forced shut-down system

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Convergence study to improve a game regulation for youth (청소년 게임 규제 정책 개선을 위한 융합적 연구)

  • Kim, Yu-Na;Lee, Hwan-Soo
    • Journal of Digital Convergence
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    • v.13 no.8
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    • pp.59-67
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    • 2015
  • As online game addiction of youth becomes a serious social problem, various regulations restricting their game play have been introduced. However, it is considered that forced shut-down, selective shut-down, and other regulations have no effect, and theoretical debates about the necessity of regulations also continue. Therefore, this study theoretically re-examines the necessity of youth game regulations by the discussion on domestic and international policy trends and existing research. In order to confirm empirical evidence of the effectiveness of regulations, this study compares and analyses the change of youth's game play time and patterns before and after the regulations. According to the results, the effect of the regulations is inadequate so this study proposes reasonable improvement ways of them through convergent approach including legal, political, and technological perspective.

Design and Application of Forced Cooling System in Steam Turbine (증기터빈 강제냉각 장치의 설계 및 적용)

  • 김효진;류승우;강용호
    • Journal of the Korean Society for Precision Engineering
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    • v.15 no.9
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    • pp.25-32
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    • 1998
  • The forced cooling system is designed to shorten the overhaul time of steam turbine, which is important in view of economic concern of utility companies, Forced cooling of the hot turbine is achieved by suction of air flow into the turbine after the turbine shuts down. The heat transfer process by suction of air flow can cause thermal stress due to the thermal gradients. In this paper, the analysis of heat transfer is performed to calculate the air flow rate. Based on the prediction of cyclic fatigue damage and the experience, the cooling equipment is designed for shortening the cooling time of steam turbine.

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A Study on the In-Pipe Surge Analysis for Cargo Unloading Piping System of LNG Carrier (LNG선의 화물 하역 배관망의 과도 응답 해석에 관한 연구)

  • Chun, Byung-Il;Woo, Jong-Sik
    • Journal of the Society of Naval Architects of Korea
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    • v.33 no.1
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    • pp.124-134
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    • 1996
  • In this paper the pressures and flowrate distributions in the loading/unloading piping system of LNG carrier have been investigated in the case of unsteady flow state as well as steady one. Under emergency situation the main cargo pumps are forced to fail, and the ESD(Emergency Shut Down) valves and Stop valves are closed within set-time. The surge pressures according to the variations of valve closing time have been computed to recognize the surge phenomenon due to sudden decrease of flowrate. By means of these analysis results, the most important factors on the in-pipe surge phenomenon of cargo loading/unloading piping system of LNG Carrier are the type of ESD and Stop valves, valve closing time, and the pipe arrangements.

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Analysis on Hypothetical Multiple Events of mSGTR and SBO at CANDU-6 Plants Using MARS-KS Code (중수로 원전 가상의 mSGTR과 SBO 다중 사건에 대한 MARS-KS 코드 분석)

  • Seon Oh YU;Kyung Won LEE;Kyung Lok BAEK;Manwoong KIM
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.17 no.1
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    • pp.18-27
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    • 2021
  • This study aims to develop an improved evaluation technology for assessing CANDU-6 safety. For this purpose, the multiple steam generator tube rupture (mSGTR) followed by an unmitigated station blackout (SBO) in a CANDU-6 plant was selected as a hypothetical event scenario and the analysis model to evaluate the plant responses was envisioned into the MARS-KS input model. The model includes logic models for controlling the pressure and inventory of the primary heat transport system (PHTS) decreasing due to the u-tubes' rupture, as well as the main features of PHTS with a simplified model for the horizontal fuel channels, the secondary heat transport system including the shell side of steam generators, feedwater and main steam line, and moderator system. A steady state condition was successfully achieved to confirm the stable convergence of the key parameters. Until the turbine trip, the fuel channels were adequately cooled by forced circulation of coolant and supply of main feedwater. However, due to the continuous reduction of PHTS pressure and inventory, the reactor and turbine were shut down and the thermal-hydraulic behaviors between intact and broken loops got asymmetric. Furthermore, as the conditions of low-flow coolant and high void fraction in the broken loop persisted, leading to degradation of decay heat removal, it was evaluated that the peak cladding temperature (PCT) exceeded the limit criteria for ensuring nuclear fuel integrity. This study is expected to provide the technical bases to the accident management strategy for transient conditions with multiple events.