http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
Model Reference Robust Adaptive Control of Control Element Drive Mechanism in a Nuclear Power Plant
Bae-Jeong Park,Phuong-Tung Pham,Keum-ShikHong 제어·로봇·시스템학회 2020 International Journal of Control, Automation, and Vol.18 No.7
In the nuclear power plant, the control element drive mechanism (CEDM: A type of solenoid actuators) is used to insert nuclear fuel rods into the core to regulate the neutron absorption within the reactor. The control environment is full of uncertainty and disturbance, and the CEDM is supposed to cope with the varying conditions in the reactor. In this paper, a model reference adaptive control (MRAC) of CEDM is investigated. The existing MRAC scheme that assumes the known system order is first extended to the system with unknown high-frequency gain and output disturbance, and then the extended version is applied to the control problem of CEDM. A simplified relationship between the input voltage and the magnetic force of the CEDM is established based on Kirchhoff’s voltage law and the magnetic co-energy theory. The system order of the plant is identified by the prediction error method using experimental input/output data: A 3rd order linear model with three poles and two zeros turns out to be the best model for control. Based on this model, a 3rd order reference model is selected, and an adaptive control law with σ-modified adaptation laws is designed under output disturbance. The performance of the proposed control law is compared with a well-tuned PI controller and the conventional MRAC. The superiority of the proposed method is also demonstrated in an abnormal condition. Simulation and experiment results are provided.
박진석(Park Jinseok),이명구(Lee Myounggoo),조연호(Cho Yeonho),김현민(Kim Hyunmin) 대한기계학회 2018 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.6 No.1
내장형 제어봉 구동장치는 원자로의 반응도를 제어하는 전기기기로 기존의 외장형 제어봉 구동장치에 비해 제어봉인출 사고를 근본적으로 배제할 수 있다는 장점이 있다. 내장형 제어봉 구동장치는 고온, 고압, 고방사능 및 침수조건에서 작동되어야 하므로 환경조건에 대한 평가가 필요하다. 특히, 온도조건의 경우 전기기기의 성능에 미치는 영향이 클 수 있으므로 매우 중요하다. 본 논문은 내장형 제어봉 구동장치 열해석 모델을 개발하고 내열성능을 평가하는 과정을 소개한다. The IV-CEDM (in-vessel control element drive mechanism) is an electro-mechanical device to control reactivity of the nuclear reactor. Comparing to the conventional ex-vessel CEDM, the IV-CEDM provides a significant benefit of fundamentally eliminating the rod ejection accident. The IV-CEDM must be evaluated for its environmental conditions since it operates in high temperature, high pressure, high radiation and submerged condition. Especially, evaluation for the high temperature condition is very important because electro-mechanical devices could be affected a lot by temperature elevation. This paper introduces development of a thermal analysis model of the IV-CEDM and its evaluation for high temperature environment.
Bae, H.Y.,Kim, Y.J.,Kim, J.H.,Lee, S.H.,Lee, K.S.,Park, C.Y. Applied Science Publishers ; Elsevier Science Ltd 2014 The International journal of pressure vessels and Vol.114 No.-
This paper investigates effects of variables related to 3-D finite element welding residual stress analyses of penetration nozzles on residual stresses. Five variables are considered; (i) number of elements in the circumferential direction, (ii) number of beads in the circumferential direction, (iii) kinematic boundary conditions, (iv) circumferential modelling angle in 3-D finite element models and (v) detailed weld shape. Based on sensitivity analysis results, guidelines for 3-D finite element welding residual stress analyses of penetration nozzles are provided.
백민호(Min-Ho Baek),홍훈빈(Hoon-Bin Hong),박희준(Hee-June Park) 대한전기학회 2016 전기학회논문지 Vol.65 No.11
Control Rod Position Indicator in nuclear reactor vessel has developed for small reactor in Korea. Because of severe environment in reactor vessel, target of this study is to develop the suitable position indicator. In this study, solenoid type position indicator made of Mineral Insulated Cable(MI Cable) was introduced to adapt in severe environment. And inductance of the solenoid was used to indicate the rod position for high precision. But problem of this concept is that a linear slope of inductance is changed by temperature effect. To resolve this problem, two sensing coils were introduced for temperature compensation. A role of the sensing coil is to make reference linear equation about certain temperature. To confirm this concept, also, inductance of solenoid and sensing coils were measured at room and high temperature (~300℃). The results of measurement show that the position error of sensing coil between room and high temperature was about 2%. But it was identified that this error was resulted from insufficient test environment (temperature error between solenoid and sensing coils was about 2% at high temperature condition). Therefore, solenoid type position indicator shows that it is very suitable in reactor vessel as a high precision rod position indicator.
3차원 유한요소모델을 이용한 원전 제어봉구동장치 노즐 용접부 잔류응력 평가
박영철(Young-Chul Park),정재욱(Jae-Uk Jeong),김영진(Young-Jin Kim),장윤석(Yoon-Suk Chang),김성우(Sung-Woo Kim),김홍표(Hong-Pyo Kim) 대한기계학회 2011 대한기계학회 춘추학술대회 Vol.2011 No.10
The cracking due to PWSCC(Primary Water Stress Corrosion Cracking) has been observed at dissimilar metal welds of nuclear power plants. While the root cause was known as the interaction among sensitive thermal characteristics of alloy-type material, service condition and weld residual stress, the residual stress was considered as the most influential variable on PWSCC. In this context, several researches have been carried out world-widely, for which numerical schemes were employed especially to estimate residual stress distributions. Most of the previous analyses were performed by using 2-D axisymmetric models to reduce computational burden, however, which led to restriction to assess asymmetric parts such as CRDM(Control Rod Drive Mechanism) nozzle. Therefore, in the present study, complex 3-D finite element models were developed by changing angles between the CRDM nozzle and reactor pressure vessel head. Accordingly, parametric analyses were conducted to examine realistic stress distributions at critical locations with different geometric discontinuity. Key findings from the analyses were presented and discussed, which can be figured out the dimensional effects of residual stress on dissimilar metal welds.
권형도(Hyeong Do Kweon),남덕우(Deok Woo Nam),서정수(Jung Soo Suh) 한국소음진동공학회 2016 한국소음진동공학회 학술대회논문집 Vol.2016 No.4
Natural frequencies of the extension shaft assembly (ESA) of the control element drive mechanism (CEDM) for the advanced power reactor plus (APR+) have been determined by analyzing data obtained from a test and performing a numerical modal analysis. Axial acceleration time history signals of the ESA were obtained from an operational sequence of the CEDM, which produces impact force the same as that of impact tests onto the ESA. FFT analysis for the signals resulted in four natural frequencies. A modal analysis was performed to confirm the reliability of the results from the data analysis. Four natural frequencies for axial mode also resulted from the modal analysis. Maximum difference between two results is within 9%, therefore, the natural frequencies of the ESA from the data analysis are reliable.