scholarly journals An Adaptive Control Concept of Reactor Power Distribution

1970 ◽  
Vol 7 (6) ◽  
pp. 321-322 ◽  
Author(s):  
Tsutomu HOSHINO
Energies ◽  
2021 ◽  
Vol 14 (12) ◽  
pp. 3389
Author(s):  
Marcin Kamiński ◽  
Krzysztof Szabat

This paper presents issues related to the adaptive control of the drive system with an elastic clutch connecting the main motor and the load machine. Firstly, the problems and the main algorithms often implemented for the mentioned object are analyzed. Then, the control concept based on the RNN (recurrent neural network) for the drive system with the flexible coupling is thoroughly described. For this purpose, an adaptive model inspired by the Elman model is selected, which is related to internal feedback in the neural network. The indicated feature improves the processing of dynamic signals. During the design process, for the selection of constant coefficients of the controller, the PSO (particle swarm optimizer) is applied. Moreover, in order to obtain better dynamic properties and improve work in real conditions, one model based on the ADALINE (adaptive linear neuron) is introduced into the structure. Details of the algorithm used for the weights’ adaptation are presented (including stability analysis) to perform the shaft torque signal filtering. The effectiveness of the proposed approach is examined through simulation and experimental studies.


1979 ◽  
Vol 47 (6) ◽  
pp. 979-983
Author(s):  
I. Ya. Emel'yanov ◽  
L. N. Podlazov ◽  
A. N. Aleksakov ◽  
V. M. Panin

Author(s):  
Changhui Wang ◽  
Hongchun Wu ◽  
Liangzhi Cao

A method of on-line monitoring for commercial PWRs using eigenfunctions has been proposed in prevenient works. In this method, the eigenfunctions combine with the detector readings are used to reconstruct the real reactor power distribution. But it is very difficult to choose the eigenfunctions because the condition of the reactor is much complex. Therefore, some improvements on this method are studied in this paper. A number of representational conditions according to the reactor fuel management are picked up to create a data library of different eigenfunctions. On the monitoring process, the computer will judge that which represen6tational conditions most close to the real reactor condition and choose the eigenfunctions which will be used to reconstruct the reactor core power distribution combine with the detector readings. A reactor of Qinshan Nuclear Power Corporation is studied here as an example. The detector readings are from the simulator. The numerical result shows that this method can reconstruct the reactor power distribution with high speed (about 0.03 seconds for each step) and high accuracy (the relative errors are lower than 3% mostly).


Energies ◽  
2020 ◽  
Vol 13 (20) ◽  
pp. 5410
Author(s):  
Muhammad Hashim ◽  
Liangzhi Cao ◽  
Shengcheng Zhou ◽  
Rubing Ma ◽  
Yiqiong Shao ◽  
...  

In this study, a conceptual design was developed for a lead-bismuth-cooled small modular fast reactor SPARK-NC with natural circulation and load following capabilities. The nominal rated power was set to 10 MWe, and the power can be manipulated from 5 MWe to 10 MWe during the whole core lifetime. The core of the SPARK-NC can be operated for eight effective full power years (EFPYs) without refueling. The core neutronics and thermal-hydraulics design calculations were performed using the SARAX code and the natural circulation capability of the SPARK-NC was investigated by employing the energy conservation equation, pressure drop equation and quasi-static reactivity balance equation. In order to flatten the radial power distribution, three radial zones were constructed by employing different fuel enrichments and fuel pin diameters. To provide an adequate shutdown margin, two independent systems, i.e., a control system and a scram system, were introduced in the core. The control assemblies were further classified into two types: primary control assemblies used for reactivity control and power flattening and secondary control assemblies (with relatively smaller reactivity worth) used for power regulation. The load following capability of SPARK-NC was assessed using the quasi-static reactivity balance method. By comparing three possible approaches for adjusting the reactor power output, it was shown that the method of adjusting the coolant inlet temperature was viable, practically easy to implement and favored for the load following operation.


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