http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
Zare, Nafiseh,Jahanfarnia, Gholamreza,Khorshidi, Abdollah,Soltani, Jamshid Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.9
In this study, a fractional order proportional integral derivative (FOPID) controller is designed to create the reference power trajectory and to conquer the uncertainties and external disturbances. A fractional nonlinear model was utilized to describe the nuclear reactor dynamic behaviour considering thermal-hydraulic effects. The controller parameters were tuned using optimization method in Matlab/Simulink. The FOPID controller was simulated using Matlab/Simulink and the controller performance was evaluated for Hard variation of the reference power and compared with that of integer order a proportional integral derivative (IOPID) controller by two models of fractional neutron point kinetic (FNPK) and classical neutron point kinetic (CNPK). Also, the FOPID controller robustness was appraised against the external disturbance and uncertainties. Simulation results showed that the FOPID controller has the faster response of the control attempt signal and the smaller tracking error with respect to the IOPID in tracking the reference power trajectory. In addition, the results demonstrated the ability of FOPID controller in disturbance rejection and exhibited the good robustness of controller against uncertainty.
Ghafour Ahmad Khanbeigi,Gholamreza Jahanfarnia,Naser Mansour Sharifloo,Mohamad Kazem Sheikh-el-Eslami,Kaveh Karimi 대한전기학회 2020 Journal of Electrical Engineering & Technology Vol.15 No.5
In this paper a close solution is presented to determine the trade-off between cost and safety to cope with station blackout (SBO) in Pressurized Water Reactors (PWRs). To compute the profi t of each generation unit, a Supply Function Equilibrium (SFE) model swhich considers carbon tax is used in a uniform electricity market. A hierarchical heuristic method is applied for decision making on safety improvement of Nuclear Power Plants (NPPs). In this method the break-even point is used as a criterion to make a decision on comparing cost of safety improvement and profi t of NPP in a deregulated electricity market. This method is applied in a case of adding an Emergency Water Supply (EWS) and an Emergency Diesel Generator (EDG) to a NPP where impacts of its investment cost and its profi t are investigated. The achieved results show that the break-even point of investment cost and net profi t of the NPP by adding the EDG is one month later than NPP with addition of EWS.
Mehdi Dehjourian,Reza Sayareh,Mohammad Rahgoshay,Gholamreza Jahanfarnia,Amir Saied Shirani 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.5
Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments. The management of hydrogen safety and prevention of overpressurization could be implemented through a hydrogen reduction system and spray system. During the course of the hypothetical large break loss-of-coolant accident in a nuclear power plant, hydrogen is generated by a reaction between steamand the fuel-cladding inside the reactor pressure vessel and also core concrete interaction after ejection of melt into the cavity. The MELCOR 1.8.6 was used to assess core degradation and containment behavior during the large break loss-of-coolant accident without the actuation of the safety injection system except for accumulators in Beznau nuclear power plant. Also, hydrogen distribution in containment and performance of hydrogen reduction system were investigated.