• 제목/요약/키워드: power shutdown

검색결과 301건 처리시간 0.023초

Evaluation of Transient Natural Circulation Behavior during Accident in Low Power /Shutdown Condition of YGN Units 3/4

  • Bang, Young-Seok;Kim, Kap;Seul, Kwang-Won;Kim, Hho-Jung
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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    • pp.458-463
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    • 1997
  • A transient natural circulation behavior during a LOCA at hot-standby operation is evaluated for YGN Units 3/4. The plant initial condition is determined within the EOP limitation as suitable to hot-standby mode and the transient scenario is prepared as relevant to evaluation of transient natural circulation. A 0.4% cold leg break with loss of off-site power is calculated with RELAP5/MOD3.2, whose predictability has been verified for SBLOCA natural circulation test, S-NC-8B. Through one hour transient analysis, it is found that the plant has its own decay heat removal capability by natural circulation following a LOCA, at hot-standby mode. Additional calculation is performed to investigate an effect of HPSI flow on natural circulation.

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축정렬 불량시 베어링 특성 변화에 따른 발전소 증기 터빈의 동특성 연구 (Study of Dynamic Characteristics of Angular Misalignment of High-pressure Turbine in 1000MW Nuclear Power Plant)

  • 손석만;이준신;유기완;이선기;김태룡
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2000년도 춘계학술대회논문집
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    • pp.664-669
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    • 2000
  • Angular misalignment is one of the important causes for shaft vibration of turbine-generator in 1000MW nuclear power plant. It may cause the plant unexpected shutdown and subsequent accident. The change of dynamic characteristics in journal bearing and rotor due to angular misalignment in high pressure turbine is analyzed. The stiffness/damping coefficients of journal bearing increase as angular misalignment. Subsequently the natural frequency of HP turbine is changed. It was found that the natural frequency may locate near 2 times operating frequency in case of severe misalignment.

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순간 전압 변동에 의한 수용가측 영향 분석 (Analysis of Customers' Effect by Momentary Voltage Variation)

  • 한경남;김일동;윤상윤;임성정;김재철;김언석
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 1997년도 추계학술대회 논문집 학회본부
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    • pp.164-166
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    • 1997
  • This paper analyze customers' effect caused by momentary voltage variation. Momentary voltage variation is due to a serious results like shutdown of sensitive loads such as electronic equipment, computer, and magnetic contactor. However, conventional reliability ignored the effect of momentary voltage variation. In this paper we analyze the present state of momentary voltage variation in customers.

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안드로이드 기반 스마트TV 셋톱박스의 효과적 파일 시스템 복구 방법에 관한 연구 (Reserach for Filesystem Recovery in Android based SMART TV Settop)

  • 김병준;한경식;손승일
    • 한국정보통신학회:학술대회논문집
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    • 한국정보통신학회 2012년도 추계학술대회
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    • pp.773-775
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    • 2012
  • 모바일 시스템에 비해 안드로이드 기반 스마트TV 셋톱박스의 경우 직접 전원 연결을 통한 시스템 전원을 공급받기 때문에 갑작스러운 전원차단으로 인한 메모리기반 파일시스템의 손상이 발생하게 된다. 이를 개선하기 위해 init의 중복 실행을 통해 스마트TV OS 프레임워크가 시작되기 전에 해당 파일 시스템의 손상 유무를 판단하여 시스템 체크를 수행하는 방법에 대해 연구한다.

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Performance Analysis for the Modified Excitation System of Synchronous Machine Connected to HVDC System

  • Kim, Chan-Ki
    • KIEE International Transaction on Electrical Machinery and Energy Conversion Systems
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    • 제2B권3호
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    • pp.109-114
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    • 2002
  • This paper analysis the transient performance of the modified excitation system using 4-quadrant chopper for a synchronous machine connected to HVDC system. Conventionally, capacitors are used to supply reactive power requirement at a strong converter bus. And the installation of a synchronous machine is essential in an isolated weak network to re-start after a shutdown of HVDC and to increase the system strength. However, a conventional static excitation system has some problems which are harmonic instability and the system stress due to overvoltage. To reduce these problems, the new excitation system, which has 4-quadrant chopper, is proposed. As the proposed system provides the capability to allow reverse current and isolate between AC network and excitation power, problems of overvoltage and harmonic instability can be solved. The investigation is performed and confirmed by the time domain digital simulation using PSCAD/EMTDC program.

감육배관의 건전성평가 및 정비 관련 기술기준 고찰 (Review on the Integrity Evaluation and Maintenance of Wall-Thinned Pipe)

  • 이성호;이요섭;김홍덕;이경수;황경모
    • 한국압력기기공학회 논문집
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    • 제11권2호
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    • pp.51-60
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    • 2015
  • Local wall thinning and integrity degradation caused by several mechanisms, such as flow accelerated corrosion, cavitation, flashing and/or liquid droplet impingement, is a main concern in secondary steam cycle piping system of nuclear power plants in terms of safety and operability. Thinned pipe management program (TPMP) has being developed and optimized to reduce the possibility of unplanned shutdown and/or power reduction due to pipe failure caused by wall thinning. In this paper, newest technologies, standards and regulations related to the integrity assessment, repair and replacement of thinned pipe component are reviewed. And technical improvement items in TPMP to secure the reliability and effectiveness are also presented.

A STUDY ON AN ASSESSMENT METHOD FOR IMPROVING TECHNICAL SPECIFICATIONS USING SYSTEM DYNAMICS

  • KANG KYUNG MIN;JAE MOOSUNG
    • Nuclear Engineering and Technology
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    • 제37권1호
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    • pp.109-117
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    • 2005
  • Limiting conditions for operations (LCOs) are evaluated dynamically using the tool of system dynamics. The LCOs de-fine the allowed outage times (AOTs) and the actions to be taken if the repair cannot be completed within the AOT. System dynamics has been developed to analyze the dynamic reliability of a complicated system. System dynamics using Vensim software have been applied to LCOs assessment for an example system, the auxiliary feed water system of a reference nuclear power plant. Analysis results of both full power operation and shutdown operation have been compared for a measure of core damage frequency. The framework developed in this study has been shown to be very flexible in that it can be applied to assess LCOs quantitatively under any operational context of the TS in FSAR.

Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model

  • Korbu, Tamara;Kuzmin, Andrei;Rudak, Eduard;Kravchenko, Maksim
    • Nuclear Engineering and Technology
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    • 제53권6호
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    • pp.1731-1735
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    • 2021
  • The operation of the nuclear reactor requires accurate and fast methods and techniques for analysing its kinetics. These techniques become even more important when the MOX-fuel is used due to the lower value of delayed neutron fraction 𝛽 for 239Pu. Based on a Birth-and-Death process review, the mathematical model of thermal reactor core has been proposed different from existing ones. The analytical method for thermal point-reactor parameters evaluation is described within this work. The proposed method is applied for analysis of the unsteady transient processes taking place in a thermal reactor at its start-up or shutdown power change, as well as during small accidental power variation from the rated value. Theoretical determination of MASURCA reactor core reactivity through the analysis of experimental data on neutron time spectra was made.

Performance measurement of safety-critical systems based on ordinary differential equations and Petri nets: A case study of nuclear power plant

  • Nand Kumar Jyotish;Lalit Kumar Singh;Chiranjeev Kumar
    • Nuclear Engineering and Technology
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    • 제55권3호
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    • pp.861-869
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    • 2023
  • This article proposes a novel approach to measure the performance of Safety-Critical Systems (SCS). Such systems contain multiple processing nodes that communicate with each other is modeled by a Petri nets (PN). The paper uses the PN for the performance evaluation of SCS. A set of ordinary differential equations (ODEs) is derived from the Petri net model that represent the state of the system, and the solutions can be used to measure the system's performance. The proposed method can avoid the state space explosion problem and also introduces new metrics of performance, along with their measurement: deadlock, liveness, stability, boundedness, and steady state. The proposed technique is applied to Shutdown System (SDS) of Nuclear Power Plant (NPP). We obtained 99.887% accuracy of performance measurement, which proves the effectiveness of our approach.

Establishment of the Procedure to Prevent Boron Precipitation During Post-LOCA Long Term Cooling for WH 3-Loop NPPs

  • Cho, H.R.;Lee, S.K.;Ban, C.H.;Hwang, S.T.;Chang, B.H.
    • Nuclear Engineering and Technology
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    • 제30권1호
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    • pp.47-57
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    • 1998
  • Boric acid concentrations of the refueling water storage tank and the accumulators for Westinghouse 3-loop type plants are increased to meet the post loss of coolant accident shutdown requirement for the extended fuel cycles from 12 months to 18 months. To maintain long term cooling capability following a LOCA, the switchover time is examined using BORON code to prevent the boron precipitation in the reactor core with the increased boron concentrations. The analysis results show that hot leg recirculation switchover times are shortened to 7.5 hours from 24 hours after the initiation of LOCA for Kori 3&4 and 8 hours from 18 hours for Ulchin 1&2, respectively. The How path in the mode J for Kori 3&4 is recommended to realign to the simultaneous recirculation of both hot and cold legs from the cold leg recirculation, as done by Ulchin 1&2.

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