Pengcheng Zhao

ORCID: 0000-0002-0041-8170
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About
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Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear Engineering Thermal-Hydraulics
  • Nuclear Materials and Properties
  • Heat transfer and supercritical fluids
  • Nuclear Physics and Applications
  • Graphite, nuclear technology, radiation studies
  • Electrochemical Analysis and Applications
  • Model Reduction and Neural Networks
  • Heat Transfer and Boiling Studies
  • Advanced biosensing and bioanalysis techniques
  • Power Transformer Diagnostics and Insulation
  • Cinema and Media Studies
  • Groundwater flow and contamination studies
  • Nuclear and radioactivity studies
  • Advanced Chemical Sensor Technologies
  • Power Systems Fault Detection
  • Image Enhancement Techniques
  • Electrocatalysts for Energy Conversion
  • Non-Destructive Testing Techniques
  • Engineering Diagnostics and Reliability
  • Advanced Sensor and Control Systems
  • Machine Fault Diagnosis Techniques
  • Fuel Cells and Related Materials
  • Probabilistic and Robust Engineering Design
  • MXene and MAX Phase Materials

University of South China
2018-2024

Xiangtan University
2024

Chongqing University
2024

South China University of Technology
2023

University of Science and Technology of China
2021

Hunan Institute of Technology
2020

China General Nuclear Power Corporation (China)
2020

After an emergency shutdown of a lead-bismuth fast reactor, thermal stratification occurs in the upper Plenum, which negatively impacts integrity reactor structure and residual heat removal capacity natural circulation flow. The research on reactors has mainly been conducted using experimental method, system program, computational fluid dynamics (CFD). However, equipment required for method is expensive, accuracy program unpredictable, resources time CFD approach are extensive. To overcome...

10.1016/j.net.2023.05.002 article EN cc-by-nc-nd Nuclear Engineering and Technology 2023-05-03

Accurately predicting the thermal hydraulic parameters of a transient reactor core under different working conditions is first step toward safety. Mass flow rate and temperature are important hydraulics, which have often been modeled as time series prediction problems. This study aims to achieve accurate continuous instantaneous conditions, well test feasibility newly constructed gated recurrent unit (GRU) model based on soft attention mechanism for parameter predictions. Herein, China...

10.1016/j.net.2024.01.045 article EN cc-by-nc-nd Nuclear Engineering and Technology 2024-03-06

Inter-Turn Short Circuit (ITSC) faults do not necessarily produce high temperatures but exhibit distinct heat distribution and characteristics. This paper proposes a novel fault diagnosis identification scheme utilizing an improved You Look Only Once Vision 8 (YOLOv8) algorithm, enhanced with infrared image slicing-aided hyper-inference (SAHI) technique, to automatically detect ITSC trajectories in dry-type transformers. The acquisition system gathers data on captures images varying contrast...

10.3390/en17184559 article EN cc-by Energies 2024-09-12

Small Modular Reactors (SMRs) are attracting wide attention due to their outstanding performance, extensive studies have been carried out for lead-based fast reactors (LFRs) that cooled with Lead or Lead-bismuth (LBE), and small modular natural circulation LFR is one of the promising candidates SMRs LFRs development. One challenges design master thermal-hydraulic performance in reactor primary circuit, while characteristics a coupled problem core thermal power, loop layout operating state...

10.1016/j.net.2020.05.023 article EN cc-by-nc-nd Nuclear Engineering and Technology 2020-05-30

Targeting at simulating the application of thorium-uranium (TU) fuel in CANDU-6 reactor, this paper analyzes process using code DRAGON/DONJON where discrete TU pins are applied reactor under time-average equilibrium refueling. The results show that coolant void reactivity assembly analyzed is lower than 37-element bundle cell with natural uranium and mixed pins; max channel/bundle power core meets limits - less 6700kW/860 kW; conversion ratio higher uranium; exit burnup increases to 13400...

10.1016/j.net.2018.10.022 article EN cc-by-nc-nd Nuclear Engineering and Technology 2018-10-25

SNCLFR-100 is a small modular natural circulation lead-cooled fast reactor, developed by University of Science and Technology China, aiming at taking full advantage the good economics inherent safety reactors to develop miniaturized, lightweight multi-purpose special nuclear reactor technology. still in conceptual design stage, order fully evaluate features provide reference for optimization next three typical transients are selected based on analysis initiating events using code Analysis...

10.3389/fenrg.2021.678939 article EN cc-by Frontiers in Energy Research 2021-06-08

In this study, the dynamic characteristics of accelerator-driven subcritical reactor (ADSR) under beam transients with high heterogeneity neutron flux in time-space are investigated. Multi-mode core few-group constants generated by three kinds fluxes: steady state ADSR, λ-eigenvalue fundamental wave, and α-eigenvalue wave. The proposed overcome limitation single constant two-step method that cannot consider variation density energy spectrum time space. Compared to existing different...

10.3389/fenrg.2020.603084 article EN cc-by Frontiers in Energy Research 2021-01-13

The multi-physics coupled methodologies that have been widely used to analyze the complex process occurring in nuclear reactors also R&D of numerical reactors. advancement field computer technology has helped development these methodologies. Herein, we report integration ADPRES code and RELAP5 into SALOME-ICoCo framework form a coupling platform. platform exploits supervisor architecture, serial mode, mesh one-to-one correspondence explicit methods during analysis, uncertainty analysis tool...

10.1016/j.net.2023.02.010 article EN cc-by-nc-nd Nuclear Engineering and Technology 2023-02-08

To meet the numerous application demands of lead-bismuth reactors, different design optimization tasks need to be conducted on these reactors based existing reactor core solutions. However, is a challenging task because it complex, multi-dimensional, and nonlinear constrained problem. resolve issues improve efficiency optimization, new method, called KSM-OLHS-SEUMRE Kriging surrogate model (KSM), orthogonal Latin hypercube sampling (OLHS), space exploration unimodal region elimination...

10.3389/fenrg.2022.849229 article EN cc-by Frontiers in Energy Research 2022-03-21

In this study, a cladding surface temperature prediction method based on an adaptive RBF neural network was proposed. This can significantly improve the accuracy and efficiency of thermal safety evaluation lead–bismuth fast reactor. First, sub-channel analysis program SUBCHANFLOW, core model small reactor SPALLER-100 established. Second, calculated 2000 groups power distribution coolant flow data were used as training samples. The trained to predict fuel elements in Finally, by comparison,...

10.3389/fenrg.2022.852146 article EN cc-by Frontiers in Energy Research 2022-04-12

Automatic image colorization is inherently an ill-posed problem with uncertainty, which requires accurate semantic understanding of scenes to estimate reasonable colors for grayscale images. Although recent interaction-based methods have achieved impressive performance, it still a very difficult task infer realistic and automatic colorization. To reduce the difficulty scenes, this paper tries utilize corresponding audio, naturally contains extra information about same scene. Specifically,...

10.48550/arxiv.2401.13270 preprint EN other-oa arXiv (Cornell University) 2024-01-01

High-order harmonic techniques can be used to recreate neutron flux distributions in reactor cores using the diffusion equation. However, traditional source iteration and correction have sluggish convergence rates protracted calculation periods. The correctness of implicitly restarted Arnoldi method (IRAM) resolving eigenvalue problems one-dimensional two-dimensional equations was confirmed by computing benchmark SLAB_1D_1G steady-state TWIGL IRAM. By integrating Galerkin projection with...

10.1016/j.net.2024.02.055 article EN cc-by-nc-nd Nuclear Engineering and Technology 2024-03-01

During fault diagnosis of rolling bearings rotating machinery in nuclear power plant, there are different data processing methods for original vibration signals, and have diagnostic accuracy under the same model. [Purpose] When performance model is limited, order to improve model, it necessary study method. [Methods] Therefore, signal processed into five ways: time-domain diagram(TD), time grayscale diagram(TGS), fast Fourier transform frequency-domain diagram(FFT), short-time time-frequency...

10.1117/12.2680129 article EN 2023-05-31
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