• Title/Summary/Keyword: Nuclear Steam Generator

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AN EVALUATION OF THE APERIODIC AND FLUCTUATING INSTABILITIES FOR THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN INTEGRAL REACTOR

  • Kang Han-Ok;Lee Yong-Ho;Yoon Ju-Hyeon
    • Nuclear Engineering and Technology
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    • v.38 no.4
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    • pp.343-352
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    • 2006

  • Convenient analytical tools for evaluation of the aperiodic and the fluctuating instabilities of the passive residual heat removal system (PRHRS) of an integral reactor are developed and results are discussed from the viewpoint of the system design. First, a static model for the aperiodic instability using the system hydraulic loss relation and the downcomer feedwater heating equations is developed. The calculated hydraulic relation between the pressure drop and the feedwater flow rate shows that several static states can exist with various numbers of water-mode feedwater module pipes. It is shown that the most probable state can exist by basic physical reasoning, that there is no flow rate through the steam-mode feedwater module pipes. Second, a dynamic model for the fluctuating instability due to steam generation retardation in the steam generator and the dynamic interaction of two compressible volumes, that is, the steam volume of the main steam pipe lines and the gas volume of the compensating tank is formulated and the D-decomposition method is applied after linearization of the governing equations. The results show that the PRHRS becomes stabilized with a smaller volume compensating tank, a larger volume steam space and higher hydraulic resistance of the path $a_{ct}$. Increasing the operating steam pressure has a stabilizing effect. The analytical model and the results obtained from this study will be utilized for PRHRS performance improvement.

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Fault Diagnosis for the Nuclear PWR Steam Generator Using Neural Network (신경회로망을 이용한 원전 PWR 증기발생기의 고장진단)

  • Lee, In-Soo;Yoo, Chul-Jong;Kim, Kyung-Youn
    • Journal of the Korean Institute of Intelligent Systems
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    • v.15 no.6
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    • pp.673-681
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    • 2005

  • As it is the most important to make sure security and reliability for nuclear Power Plant, it's considered the most crucial issues to develop a fault detective and diagnostic system in spite of multiple hardware redundancy in itself. To develop an algorithm for a fault diagnosis in the nuclear PWR steam generator, this paper proposes a method based on ART2(adaptive resonance theory 2) neural network that senses and classifies troubles occurred in the system. The fault diagnosis system consists of fault detective part to sense occurred troubles, parameter estimation part to identify changed system parameters and fault classification part to understand types of troubles occurred. The fault classification part Is composed of a fault classifier that uses ART2 neural network. The Performance of the proposed fault diagnosis a18orithm was corroborated by applying in the steam generator.

  • https://doi.org/10.5391/JKIIS.2005.15.6.673 인용 PDF KSCI

Optimal Sampling Period of the Digital Control System for the Nuclear Power Plant Steam Generator Water Level Control (증기발생기 수위 제어를 위한 디지탈 제어기의 적정 샘플링 주기)

  • Hur, Woo-Sung;Seong, Poong-Hyun
    • Nuclear Engineering and Technology
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    • v.27 no.1
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    • pp.8-17
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    • 1995

  • A great effort has been made to improve the nuclear plant control system by use of digital technologies, and a long term schedule for the control system upgrade has been prepared with an aim to implementation in the next generation nuclear plane. In case of digital control system, it is important to decide the sampling period for analysis and design of the system, because the performance and the stability of a digital control system depend on the value of the sampling period of the digital control system. There is, however, currently no systematic method used universally for determining the sampling period of the digital control system. Generally, a traditional way to select the sampling frequency is to use 20 to 30 times the bandwidth of the analog control system which has the same system configuration and parameters as the digital one. In this paper, a new method to select the sampling period is suggested which takes into account of the performance as well as the stability of the digital control system. By use of the frying's model of steam generator, the optimal sampling period of an assumptive digital control system for steam generator level control is estimated and is actually verified in the digital control simulation system for KORI-2 nuclear power plant steam generator level control. Consequently, we conclude the optimal sampling period of the digital control system for KORI-2 nuclear power plant steam generator level control is 1 second for all power ranges.

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