Chenghui Wan , Wenhui Liu , Jiahe Bai , Jianfu Zhang , Hanbo Gao , Zhewen Xiao
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引用次数: 0
Abstract
In this research, a quick and accurate prediction model has been developed for the key parameters of pressurized water reactors (PWRs) by applying the residual module neural network and single-channel convolutional neural network. The improved Gen-II PWRs, including CNP1000 and CPR1000, constitute the principal operating units in China and have accumulated a great many measurement values for critical boron concentration (CBC) and power distributions. To improve the prediction accuracy of these key parameters, this study utilizes approximately 19,971 sets of measurement values for CBC and 618 sets of data for 3-D power distribution. These datasets are combined with core state parameters provided by the PWR-core analysis code LOCUST/SPARK, which include factors such as fuel-assembly loading, assembly-averaged burnup, and poison-isotope distribution, among others, to train the intelligent models. As a result the intelligent model linking simulated core state parameters to measured key parameters has been established, making it possible to accurately and rapidly predict the measured CBC and power distribution. The verification tests indicate that the predicted CBCs have an average error of about 3.32 ppm with a 95 % confidence interval of [-6.0 ppm, 7.5 ppm], taking only 1.8 ms for each prediction. The predicted axial-power distributions and axial offset (AO) have an average relative error of about 0.46 % and 0.069 %, with 95 % confidence intervals of [-1.4 %, 1.4 %] and [-0.124 %, 0.071 %], respectively, and require only 8.3 ms for each prediction. Additionally, the predicted radial core power distributions have an average error of about 0.31 % with a 95 % confidence interval of [-0.92 %, 0.92 %] and require only 3.2 ms for each prediction. These results demonstrate that the intelligent models established in this research are capable of predicting key parameters with high accuracy and efficiency, which provides a novel technical approach for further enhancing the operational economy and safety of PWR nuclear power plants.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.