http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
김창회(Kim Chang Hwoi),이상정(Lee Sang Jeong) 대한전자공학회 1992 대한전자공학회 학술대회 Vol.1992 No.10
In this paper, an adaptive generalized predictive control(GPC) algorithm which minimizes a N-stage cost function is proposed. The resulting controller is based on GPC algorithm and can be used in unknown plant parameters as the parameters of one step ahead predictor are estimated by recursive least squares method. The estimated parameters are extended to G, P, and F matrix which contain the parameters of N step ahead predictors. And the minimization of cost function assuming no constraints on future controls results in the projected control increment vector. Hence this adaptive GPC algorithm can be used for either unknown system or varing system parameters, and it is also shown through simulations that the algorithm is robust to the variation of system parameters. This adaptive GPC scheme is shown to have the same stability properties as the deterministic GPC, and requires small amount of calculation compared to other adaptive algorithms which minimize N-stage cost function. Especially, in case that the maximum output horizon is 1, the proposed algorithm can be applicable to direct adaptive GPC.
디지털 원자로 보호 시스템을 위한 정형 소프트웨어 요구사항 명세
유준범(Junbeom Yoo),차성덕(Sungdeok Cha),김창회(Chang Hwoi Kim),오윤주(Younju Oh) 한국정보과학회 2004 정보과학회논문지 : 소프트웨어 및 응용 Vol.31 No.6
원자력 발전소의 디지털 제어 시스템에 적용되는 소프트웨어는 안전성이 중요시되는 safety-critical 소프트웨어로, 충분한 수준의 안전성을 보장하기 위해서 여러 기법들이 적용되고 있다. 특히, 정형명세 기법은 개발의 초기 단계에서 소프트웨어 요구 사항들을 명확하고 완전하게 명세하도록 유도함으로써 안전성을 크게 향상시킬 수 있는 기법으로 인정 받고 있다. 본 논문에서는 원자력 발전소 디지털 제어 시스템 소프트웨어의 요구 사항 명세에 적합하도록 개발된 정형명세 기법인 NuSCR을 논의한다. 또한, 개발된 NuSCR의 적용성을 검토하기 위해, 현재 KNICS 사업단에서 개발중인 발전소보호계통 소프트웨어의 요구사항을 정형 명세한 경험을 소개하고 있다. 또한, 원자력 도매인에 특화된 정형명세 기법인 NuSCR의 우수성도 실례를 들어 설명하고 있다. The software of the nuclear power plant digital control system is a safety-critical system where many techniques must be applied to it in order to preserve safety in the whole system. Formal specifications especially allow the system to be clearly and completely specified in the early requirements specification phase therefore making it a trusted method for increasing safety. In this paper, we discuss the NuSCR, which is a qualified formal specification method for specifying nuclear power plant digital control system software requirements. To investigate the application of NuSCR, we introduce the experience of using NuSCR in formally specifying the plant protection system’s software requirements, which is presently being developed at KNICS. Case study that shows that the formal specification approach NuSCR is very much qualified and specialized for the nuclear domain is also shown.
데이터 기반 경험적 모델의 원전 계측기 고장검출 민감도 평가
허섭(Seop Hur),김재환(Jae-Hwan Kim),김정택(Jung-Taek Kim),오인석(In-Sock Oh),박재창(Jae-Chang Park),김창회(Chang-Hwoi Kim) 대한전기학회 2016 전기학회논문지 Vol.65 No.5
When an accident occurs in the nuclear power plant, the faulted information might mislead to the high possibility of aggravating the accident. At the Fukushima accident, the operators misunderstood that there was no core exposure despite in the processing of core damage, because the instrument information of the reactor water level was provided to the operators optimistically other than the actual situation. Thus, this misunderstanding actually caused to much confusions on the rapid countermeasure on the accident, and then resulted in multiplying the accident propagation. It is necessary to be equipped with the function that informs operators the status of instrument integrity in real time. If plant operators verify that the instruments are working properly during accident conditions, they are able to make a decision more safely. In this study, we have performed various tests for the fault detection sensitivity of an data-driven empirical model to review the usability of the model in the accident conditions. The test was performed by using simulation data from the compact nuclear simulator that is numerically simulated to PWR type nuclear power plant. As a result of the test, the proposed model has shown good performance for detecting the specified instrument faults during normal plant conditions. Although the instrument fault detection sensitivity during plant accident conditions is lower than that during normal condition, the data-drive empirical model can be detected an instrument fault during early stage of plant accidents.