Experimental studies of adaptive control system for nuclear steam generators증기 발생기의 적응 제어시스템에 대한 실험적 연구

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dc.contributor.advisorNo, Hee-Cheon-
dc.contributor.advisor노희천-
dc.contributor.authorCho, Byung-Hak-
dc.contributor.author조병학-
dc.date.accessioned2011-12-14T08:11:22Z-
dc.date.available2011-12-14T08:11:22Z-
dc.date.issued1986-
dc.identifier.urihttp://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=65467&flag=dissertation-
dc.identifier.urihttp://hdl.handle.net/10203/49133-
dc.description학위논문(석사) - 한국과학기술원 : 핵공학과, 1986.2, [ ix, 101 p. ]-
dc.description.abstractA new approach is proposed here for the level control of steam generators through a weighted one-step- ahead stochastic self-tuning algorithm. The complicated steam generator model is represented by four parameters; water level, feedwater, steam flow and stochastic disturbances. A set of time series difference equations are obtained by combining these parameters and the measurements of water level, feedwater flow, and steam flow. These parameters are determined by a recursive least squares algorithm which results from minimizing the sum of the squared error between output (steam generator water level) and one-step-ahead optimal prediction of output. This algorithm contains a forgetting factor which can be used to account for an exponential decay of past data in tracking a slow drift in the parameters. The recursive least squares with forgetting factor, $0.950 < \lambda < 0.995$, shows good performance when rapid changes occur in process. Control input is calculated by using the time series difference equation so that the one-step-ahead optimal prediction of output equals to desired output. However, excessive control effort may be called for to bring output to desired output. Therefore, the present weighted one-step-ahead controller is designed to achieve a compromise between the extent of bringing output to desired output and the amount of control effort. An additional integral action controller is adopted optionally to compensate for the steady-state offset which comes from non-zero mean disturbances or control input weighting. To measure water level, feedwater flow, and steam flow accurately, the conventional D/P cells are replaced by capacitance-type transducers. The transducers give excellent linearity, even in the very low $\triangle$P range. The experimental loop, which is a mock-up of the secondary loop of the nuclear power plant, is used to prove effectiveness of the present adaptive control algorithm. It can be concluded from experimental results that ...eng
dc.languageeng-
dc.publisher한국과학기술원-
dc.subject핵증기 발생기.-
dc.titleExperimental studies of adaptive control system for nuclear steam generators-
dc.title.alternative증기 발생기의 적응 제어시스템에 대한 실험적 연구-
dc.typeThesis(Master)-
dc.identifier.CNRN65467/325007-
dc.description.department한국과학기술원 : 핵공학과, -
dc.identifier.uid000841314-
dc.contributor.localauthorCho, Byung-Hak-
dc.contributor.localauthor조병학-
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NE-Theses_Master(석사논문)
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