• Nuclear Engineering and Technology
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• 제36권5호
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• pp.420-429
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• 2004

The local power density should be estimated accurately to prevent fuel rod melting. The local power density at the hottest part of a hot fuel rod, which is described by the power peaking factor, is more important information than the local power density at any other position in a reactor core. Therefore, in this work, the power peaking factor, which is defined as the highest local power density to the average power density in a reactor core, is estimated by fuzzy neural networks using numerous measured signals of the reactor coolant system. The fuzzy neural networks are trained using a training data set and are verified with another test data set. They are then applied to the first fuel cycle of Yonggwang nuclear power plant unit 3. The estimation accuracy of the power peaking factor is 0.45% based on the relative $2_{\sigma}$ error by using the fuzzy neural networks without the in-core neutron flux sensors signals input. A value of 0.23% is obtained with the in-core neutron flux sensors signals, which is sufficiently accurate for use in local power density monitoring.

• Nuclear Engineering and Technology
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• 제50권1호
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• pp.97-106
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• 2018

Improved load-following capability is one of the most important technical tasks of a pressurized water reactor. Controlling the nuclear reactor core during load-following operation leads to some difficulties. These difficulties mainly arise from nuclear reactor core limitations in local power peaking: the core is subjected to sharp and large variation of local power density during transients. Axial offset (AO) is the parameter usually used to represent the core power peaking. One of the important local power peaking components in nuclear reactors is axial power peaking, which continuously changes. The main challenge of nuclear reactor control during load-following operation is to maintain the AO within acceptable limits, at a certain reference target value. This article proposes a new robust approach to AO control of pressurized water reactors during load-following operation. This method uses robust feedback-linearization control based on the multipoint kinetics reactor model (neutronic and thermal-hydraulic). In this model, the reactor core is divided into four nodes along the reactor axis. Simulation results show that this method improves the reactor load-following capability in the presence of parameter uncertainty and disturbances and can use optimum control rod groups to maneuver with variable overlapping.

• Nuclear Engineering and Technology
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• 제41권9호
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• pp.1181-1190
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• 2009

Knowing more about the Local Power Density (LPD) at the hottest part of a nuclear reactor core can provide more important information than knowledge of the LPD at any other position. The LPD at the hottest part needs to be estimated accurately in order to prevent the fuel rod from melting in a nuclear reactor. Support Vector Machines (SVMs) have successfully been applied in classification and regression problems. Therefore, in this paper, the power peaking factor, which is defined as the highest LPD to the average power density in a reactor core, was estimated by SVMs which use numerous measured signals of the reactor coolant system. The SVM models were developed by using a training data set and validated by an independent test data set. The SVM models' uncertainty was analyzed by using 100 sampled training data sets and verification data sets. The prediction intervals were very small, which means that the predicted values were very accurate. The predicted values were then applied to the first fuel cycle of the Yonggwang Nuclear Power Plant Unit 3. The root mean squared error was approximately 0.15%, which is accurate enough for use in LPD monitoring and for core protection that uses LPD estimation.

• Nuclear Engineering and Technology
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• 제50권7호
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• pp.1017-1023
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• 2018

The measurement and calculation of neutronic parameters in nuclear research reactors has an important influence on control and safety of the nuclear reactor. The power peaking factors, reactivity coefficients and kinetic parameters are the most important neutronic parameter for determining the state of the reactor. The position of the control shim safety rods in the core configuration affects these parameters. The main purpose of this work is to use the MTR_PC package to evaluate the effect of the partially insertion of the control rod on the neutronic parameters at the operating core of the Tehran Research Reactor. The simulation results show that by increasing the insertion of control rods (bank) in the core, the absolute values of power peaking factor, reactivity coefficients and effective delayed neutron fraction increased and only prompt neutron life time decreased. In addition, the results show that the changes of moderator temperature coefficients value versus the control rods positions are very significant. The average value of moderator temperature coefficients increase about 98% in the range of 0-70% insertion of control rods.

• Transactions on Electrical and Electronic Materials
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• 제15권6호
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• pp.309-314
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• 2014

This work proposes an integrated high frequency divider with an inductive peaking technique implemented in a current mode logic (CML) frequency divider. The proposed divider is composed with a master-slave flip-flop, and the master-slave flip-flop acts as a latch and read circuits which have the differential pair and cross-coupled n-MOSFETs. The cascode bias is applied in an inductive peaking circuit as a current source and the cascode bias is used for its high current driving capability and stable frequency response. The proposed divider is designed with $0.18-{\mu}m$ CMOS process, and the simulation used to evaluate the divider is performed with phase-locked loop (PLL) circuit as a feedback circuit. A divide-by-two operation is properly performed at a high frequency of 20 GHz. In the output frequency spectrum of the PLL, a peak frequency of 2 GHz is obtained witha divide-by-eight circuit at an input frequency of 250 MHz. The reference spur is obtained at -64 dBc and the power consumption is 13 mW.

• 한국정보통신학회논문지
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• 제9권2호
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• pp.262-267
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• 2005

본 논문에서는 여러 가지 효율 개선 방법 중에서 Doherty Amplifier에 관해 논하였다. 간단한 회로를 이용하여 하나의 PEP 180w급 LDMOS를 사용하여 효율성과 선형성 개선에 관한 성능분석을 하였다 제작된 Doherty Amp의 성능을 검증하기 위해 Balanced Class AB Amplifier와 성능을 비교하였다. 실험결과 peaking Amp의 $V_gs.P$가 1.53V일 때 효율이 최대 11.6$\%$ 이상 증가되었으며 매뉴얼로 gate bias 조절을 통하여 선형성 개선의 최적 bias point를 찾은 후 WCDMA 4fA에서는 $V_gs.P$가 3.68V일 때 IMSR (InterModulation to Signal Ratio)이 최대 3.34dB가 증가됨을 보였다. 특히 1.53V로 peaking amp의 bias point를 맞추게 되면 출력 전력 434Bm에서 -324Bc 이하의 IMSR과 탁월한 효율 증가를 얻을 수 있었다.

• 전기전자학회논문지
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• 제7권1호
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• pp.72-79
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• 2003

일반적으로 p-i-n Photodiode 수신기의 광신호처리 전단증폭기의 설계에서 공통소스 입력단을 사용하는 트랜스임피던스(Transimpedance)구조로 설계한다. 본 논문에서는 공통게이트 입력단을 사용하는 전류모드 광전단증폭기를 설계하였다. 이러한 광전단증폭기로 사용되는 전류모드 공통게이트 트랜스임피던스 증폭기의 특징은 높은 이득과 높은 대역폭을 동시에 얻을 수 있다는 것이다. 본 논문에서는 광전단 증폭기 설계에서 잡음 최적화를 이용하여 설계과정을 자동화 시킴으로써 보다 단순하게 트랜스임피던스 증폭기를 설계하는 기법을 제시하였다. 그리고 커패시턴스 피킹(Capacitive Peaking) 기술을 사용하여 대역폭을 더욱 증가시킬 수 있다. 제안하는 기법을 사용하여 설계된 전류모드 광전단 증폭기에 캐패시턴스 피킹을 적용하여 0.35um CMOS 공정을 사용할 경우 대역폭이 1.57GHz이고, 트랜스임피던스 이득이 2.34k, 입력 잡음전류가 470nA이고 입력 잡음 전류의 주파수밀도(spectral density)가 6.13pA/ 인 저 잡음의 고속 전류모드 트랜스임피던스 광전단증폭기를 설계 하였다. 시뮬레이션 결과 제안된 광전단증폭기의 전력소비는 3.3V 공급전압에서16.84mW이었다.

• 한국전자파학회:학술대회논문집
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• 한국전자파학회 2005년도 종합학술발표회 논문집 Vol.15 No.1
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• pp.81-86
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• 2005

In this paper, we present an efficiency extension of Doherty power amplifier using LDMOS FET devices with different peak output powers and an unequal power divider. The amplifier is designed by using a MRF21045 with P1 dB of 45 W as the main amplifier biased for Class-AB operation and a MRF21090 with P1 dB of 90 W as the peaking amplifier biased for Class-C operation. The input power is divided into a 1:1.5 power ratio between the main and peaking amplifier. The simulated results of the proposed Doherty amplifier shows an efficiency improvement of approximately 19 % in comparison to the class-AB amplifier at an output power of 42.5 dBm. The fabricated Doherty amplifier obtained a PAE of 33.68 % at 9 dB backed off from P1 dB of 51.5 dBm.

• 한국전자파학회논문지
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• 제16권9호
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• pp.957-963
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• 2005

본 논문에서는 TSMC 0.25 ${\mu}m$ CMOS RF-Mixed mode 공정 기술을 이용하여 초고속 광통신 시스템의 수신부에 사용되는 광대역 transimpedance amplifier를 설계하였다. 특히 광대역을 구성하기 위해 cascode와 common-source 구조에 active inductor shunt peaking을 이용하여 설계 및 제작하였으며, 측정 결과 gain 변화 없이 -3 dB 대역폭 특성이 cascode는 0.8 GHz에서 $81\%$ 증가한 1.45 GHz, common-source는 0.61 GHz에서 $48\%$ 증가한 0.9 GHz 결과가 나왔으며, 전체 파워 소비는 바이어스 2.5 V를 기준으로 37 mW와 45 mW이며, transimpedance gain은 61 dB$\Omega$과 61.4 dB$\Omega$을 얻을 수 있었다. 그리고 input noise current density도 상용 TIA와 거의 비슷한 $5 pA/\sqrt{Hz}$와 $4.5 pA/\sqrt{Hz}$를 가지며, out put Return loss는 전 대역에서 -10 dB 이하의 정합 특성을 보였다. 그리고 전체 chip 사이즈는 $1150{\times}940{\mu}m^2$이다.

• Nuclear Engineering and Technology
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• 제46권4호
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• pp.513-520
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• 2014

In this paper, three types of operational and industrial absorbers used at research reactors, including Ag-In-Cd alloy, $B_4C$, and Hf are selected for sensitivity analyses. Their integral effects on the main neutronic core parameters important to safety issues are investigated. These parameters are core excess reactivity, shutdown margin, total reactivity worth of control rods, thermal neutron flux, power density distribution, and Power Peaking Factor (PPF). The IAEA 10 MW benchmark core is selected as the case study to verify calculations. A two-dimensional, three-group diffusion model is selected for core calculations. The well-known WIMS-D4 and CITATION reactor codes are used to carry out these calculations. It is found that the largest shutdown margin is gained using the $B_4C$; also the lowest PPF is gained using the Ag-In-Cd alloy. The maximum point power densities belong to the inside fuel regions surrounding the central flux trap (irradiation position), surrounded by control fuel elements, and the peripheral fuel elements beside the graphite reflectors. The greatest and least fluctuation of the point power densities are gained by using $B_4C$ and Ag-In-Cd alloy, respectively.