• Title/Summary/Keyword: Safety Injection System

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A Study on Thermal Stratification Phenomenon due to In-Leakage in the Safety Injection Piping of Nuclear Power Plant (원전 안전주입 배관에서의 In-Leakage 에 의한 열성층 현상에 관한 연구)

  • Kim, K.C.;Park, M.H.;Youm, H.K.;Kim, T.Y.;Lee, S.K.
    • Proceedings of the KSME Conference
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    • 2003.04a
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    • pp.1633-1638
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    • 2003
  • In case that in-leakage through the valve disk occurs, a numerical study is performed to estimate on thermal stratification phenomenon in the Safety Injection piping connected with the Reactor Coolant System piping of Nuclear Power Plant. As the leakage flow rate increases, the temperature difference between top and bottom of horizontal piping has the inflection point. In the connection point of valve and piping, the maximum temperature difference between top and bottom was 185K and occurred in the condition of 10 times of standard leakage flow rate. In the connection point of elbow and horizontal piping, the maximum temperature difference was 145K and occurred in the condition of 15 times of standard leakage flow rate. In the vertical piping of Safety Injection piping, the near of connection point between elbow and vertical piping showed the outstanding thermal stratification phenomenon in comparison with another region because of turbulent penetration from Reactor Coolant System piping. In order to prevent damage of piping due to the thermal stratification when in-leakage through the valve disk occurs, the connection points between valve and piping, and the connection points between elbow and piping need to be inspected continually.

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Integral effect test for steam line break with coupling reactor coolant system and containment using ATLAS-CUBE facility

  • Bae, Byoung-Uhn;Lee, Jae Bong;Park, Yu-Sun;Kim, Jongrok;Kang, Kyoung-Ho
    • Nuclear Engineering and Technology
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    • v.53 no.8
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    • pp.2477-2487
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    • 2021
  • To improve safety analysis technology for a nuclear reactor containment considering an interaction between a reactor coolant system (RCS) and containment, this study aims at an experimental investigation on the integrated simulation of the RCS and containment, with an integral effect test facility, ATLAS-CUBE. For a realistic simulation of a pressure and temperature (P/T) transient, the containment simulation vessel was designed to preserve a volumetric scale equivalently to the RCS volume scale of ATLAS. Three test cases for a steam line break (SLB) transient were conducted with variation of the initial condition of the passive heat sink or the steam flow direction. The test results indicated a stratified behavior of the steam-gas mixture in the containment following a high-temperature steam injection in prior to the spray injection. The test case with a reduced heat transfer on the passive heat sink showed a faster increase of the P/T inside the containment. The effect of the steam flow direction was also investigated with respect to a multi-dimensional distribution of the local heat transfer on the passive heat sink. The integral effect test data obtained in this study will contribute to validating the evaluation methodology for mass and energy (M/E) and P/T transient of the containment.

An Efficient Analysis Model for Process Quality Information in Manufacturing Process of Automobile Safety Belt Parts (자동차 안전벨트 부품 제조공정에서의 효율적 공정품질정보 분석 모형)

  • Kong, Myung Dal
    • Journal of the Korean Institute of Plant Engineering
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    • v.23 no.4
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    • pp.29-38
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    • 2018
  • Through process quality information, the time required for process quality analysis has been drastically shortened, the process defect rate has been reduced, and the manufacturing lead time has been shortened and the on-time delivery rate has been improved. Therefore, The purpose of this study is to develop a quality information analysis system model that effectively shortens the time required for process quality analysis in automobile safety belt parts manufacturing process. As a result of experiments on communication operation between manufacturing execution system (MES) quality server, injection machine control computer, injection machine programmable logic controller (PLC) and terminal, in analyzing quality information, the conventional handwriting input method took an average of 20 minutes, but the new multi-network method took about 2 minutes on average. In addition, the process defect rate was reduced by 13% and the manufacturing lead time was shortened from 28 hours to 20 hours. The delivery compliance rate improved from 96 to 99%.

Harmonic Reduction of Electric Propulsion System by Current Injection (전류주입에 의한 전기추진시스템의 고조파 저감)

  • Kim, Jong-Su;Han, Won-Hui;Seo, Dong-Hoan
    • Journal of the Korean Society of Marine Environment & Safety
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    • v.18 no.4
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    • pp.360-364
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    • 2012
  • AC to DC converter that consists of relatively simple diode rectifier devices has been widely used in the field of the electric propulsion system. Also, since this rectifier includes large harmonics in the input current, a variety of researches have been developed to reduce the harmonics. The proposed method of this paper is to reduce the harmonics included in the input current of rectifiers and propulsion motor by injecting the output current of diode rectifier into the input of them. In addition, the proposed method ensures electrical safety through the respective isolation of the injection current, the source, and the loads using the Wye-Delta insulating transformer applied in current injection device that is installed in the input circuit of rectifiers and propulsion motor. The proposed method is simulated by applying to the electric propulsion ship that is currently operating. We confirm the validity of the proposed method compared with conventional power conversion system.

ANALYSIS OF THE ISP-50 DIRECT VESSEL INJECTION SBLOCA IN THE ATLAS FACILITY WITH THE RELAP5/MOD3.3 CODE

  • Sharabi, Medhat;Freixa, Jordi
    • Nuclear Engineering and Technology
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    • v.44 no.7
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    • pp.709-718
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    • 2012
  • The pressurized water reactor APR1400 adopts DVI (Direct Vessel Injection) for the emergency cooling water in the upper downcomer annulus. The International Standard Problem number 50 (ISP-50) was launched with the aim to investigate thermal hydraulic phenomena during a 50% DVI line break scenario with best estimate codes making use of the experimental data available from the ATLAS facility located at KAERI. The present work describes the calculation results obtained for the ISP-50 using the RELAP5/MOD3.3 system code. The work aims at validation and assessment of the code to reproduce the observed phenomena and investigate about its limitations to predict complicated mixing phenomena between the subcooled emergency cooling water and the two-phase flow in the downcomer. The obtained results show that the overall trends of the main test variables are well reproduced by the calculations. In particular, the pressure in the primary system show excellent agreement with the experiment. The loop seal clearance phenomenon was observed in the calculation and it was found to have an important influence on the transient progression. Moreover, the collapsed water levels in the core are accurately reproduced in the simulations. However, the drop in the downcomer level before the activation of the DVI from safety injection tanks was underestimated due to multi-dimensional phenomena in the downcomer that are not properly captured by one-dimensional simulations.

Design Concept of Hybrid SIT (복합안전주입탱크(Hybrid SIT) 설계개념)

  • Kwon, Tae-Soon;Euh, Dong-Jin;Kim, Ki-Hwan
    • The KSFM Journal of Fluid Machinery
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    • v.17 no.6
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    • pp.104-108
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    • 2014
  • The recent Fukushima nuclear power plant accidents shows that the core make up at high RCS pressure condition is very important to prevent core melting. The core make up flow at high pressure condition should be driven by gravity force or passive forces because the AC-powered safety features are not available during a Station Black Out (SBO) accident. The reactor Coolant System (RCS) mass inventory is continuously decreased by releasing steam through the pressurizer safety valves after reactor trip during a SBO accident. The core will be melted down within 2~3 hours without core make up action by active or passive mode. In the new design concept of a Hybrid Safety Injection Tank (Hybrid SIT) both for low and high RCS pressure conditions, the low pressure nitrogen gas serves as a charging pressure for a LBLOCA injection mode, while the PZR high pressure steam provides an equalizing pressure for a high pressure injection mode such as a SBO accident. After the pressure equalizing process by battery driven initiation valve at a high pressure SBO condition, the Hybrid SIT injection water will be passively injected into the reactor downcomer by gravity head. The SBO simulation by MARS code show that the core makeup injection flow through the Hybrid SIT continued up to the SIT empty condition, and the core heatup is delayed as much.

A Reliability Analysis of HHSIS of KNU 5,6,7 and 8 Following the Removal of s-signal from Charging/safety Injection Pump Mini-flow Line Valves (충전/안전주입 펌프 순환배관의 안전주입신호 제거에 따른 원자력 5,6,7,8 호기의 고압안전주입계통의 신뢰도 분석)

  • Chung, Dae-Wook;Chung, Chang-Hyun;Kang, Chang-Soon
    • Nuclear Engineering and Technology
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    • v.20 no.1
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    • pp.47-53
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    • 1988
  • The objective of this study is to evaluate the reliability of the High Head Safety Injection System (HHIS) of KNU 5, 6, 7 and 8 following the removal of safety injection signal (s-signal) from the mini-flow bypass line valves of charging/safety injection pumps. The unavailability of HHSIS and the rupture probability of a charging/safety injection pump have been computed for two different cases; with s-signal on and removed. The results show that when the s-signal is removed from the mini-flow bypass line valves, the unavailability of HHSIS slightly increases while the rupture probability of a charging/safety injection pump is significantly reduced. Hence, based upon the results of this study we conclude that it is more reasonable to remove the s-signal from the mini-flow bypass line valves of KNU 5, 6, 7 and 8 in the normal plant operation. And to improve the availability of HHSIS, the modification of operational procedures and the emphasis on operator training are recommended.

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Analysis of Safety Assessment of Railway Signalling by Safety Case Documents (Safety Case 문서를 기반한 열차제어시스템 안전성 평가방법 분석)

  • Hwang, Jong-Gyu;Jo, Hyun-Jeong;Yoon, Yong-Ki;Kim, Yong-Gyu
    • Proceedings of the KSR Conference
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    • 2007.05a
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    • pp.1016-1022
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    • 2007
  • It is demanded to produce the safety evidence documents in other to approval safety characteristic of railway signaling system which stands is included, it is demanding from IEC 62425 standards. Also it is express clearly that safety assessment if signaling system has to be verification of these safety evidence documents. This Safety Case has the results of safety activity through system life-cycle, such as hazard lists, hazard identification and analysis, risk assessment and countermeasure, verification and test results. Consequently, first of all, the analysis and verification of these Safety Case documents has to be accomplished to approval and acceptance of signaling system safety. And also if the safety assessor was want, it is able to be experimental test auditory which is, arbitrary faults injection test, to above described documents verification. In this paper, the contents and architecture of Safety Case are presented as first steps of safety assessment technology establishment for railway signaling system.

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Analysis of Risk Control Options for Blockage Treatment (Subsea X-mas Tree에서의 Blockage 처리 실패에 대한 위험도 저감 방안 분석)

  • Yoo, Won-Woo;Park, Min-Sun;Yang, Young-Soon
    • Journal of Ocean Engineering and Technology
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    • v.27 no.2
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    • pp.47-52
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    • 2013
  • A subsea chemical injection system treats blockage problems in a subsea production system. It is important to treat problems quickly, because production delays cause fatal profit losses in a subsea production system. Therefore, the subsea industry requires a relatively higher reliability level for a production system compared to other industries. In this study, a subsea chemical injection system (linked to a control system) to inject chemicals into a subsea X-mas tree was analyzed. By using FSA (Formal Safety Assessment), the risk factors were defined and a quantitative risk analysis utilizing FTA (Fault Tree Analysis) and ETA (Event Tree Analysis) was performed. As a result, the effectiveness of a risk reduction option was evaluated.