Minjun Peng

ORCID: 0000-0001-5867-1972
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About
Contact & Profiles
Research Areas
  • Nuclear Engineering Thermal-Hydraulics
  • Nuclear reactor physics and engineering
  • Fault Detection and Control Systems
  • Nuclear Materials and Properties
  • Risk and Safety Analysis
  • Heat Transfer and Boiling Studies
  • Heat transfer and supercritical fluids
  • Advanced Data Processing Techniques
  • Fluid Dynamics and Mixing
  • Mineral Processing and Grinding
  • Graphite, nuclear technology, radiation studies
  • Probabilistic and Robust Engineering Design
  • Heat Transfer and Optimization
  • Machine Fault Diagnosis Techniques
  • Oil and Gas Production Techniques
  • Combustion and Detonation Processes
  • Radiation Shielding Materials Analysis
  • Nuclear and radioactivity studies
  • Spectroscopy and Chemometric Analyses
  • Model Reduction and Neural Networks
  • Radiation Therapy and Dosimetry
  • Refrigeration and Air Conditioning Technologies
  • Occupational Health and Safety Research
  • Advanced Sensor and Control Systems
  • Anomaly Detection Techniques and Applications

Harbin Engineering University
2016-2025

Harbin University
2010-2025

Zhejiang University of Technology
2024

China Academy of Safety Sciences and Technology
2024

Science and Technology Department of Sichuan Province
2024

Key Laboratory of Nuclear Radiation and Nuclear Energy Technology
2022

Ministry of Industry and Information Technology
2022

Wuhan Science and Technology Bureau
2016-2020

Nanjing University of Science and Technology
2013-2014

Harbin University of Science and Technology
2010

One of the most challenging safety precautions for workers in dynamic, radioactive environments is avoiding radiation sources and sustaining low exposure. This paper presents a sampling-based algorithm, DL-RRT*, minimum dose walk-path re-planning environments, expedient occupational nuclear facilities to avoid unnecessary The method combines principle random tree star (RRT*) D* Lite, uses expansion strength grid search strategy from Lite quickly find high-quality initial path accelerate...

10.1016/j.net.2018.11.018 article EN cc-by-nc-nd Nuclear Engineering and Technology 2018-11-30

An improved principal component analysis (PCA) method is applied for sensor fault detection and isolation (FDI) in a nuclear power plant (NPP) this paper. Data pre-processing false alarm reducing methods are combined with general PCA to improve the model performance practice. In data pre-processing, singular points random fluctuations original eliminated various techniques respectively. detecting, statistics-based proposed reduce alarms of T2 Q statistics. Finally, effects evaluated...

10.1016/j.net.2018.08.020 article EN cc-by-nc-nd Nuclear Engineering and Technology 2018-09-04

In order to ensure safe operation, the risks associated with Nuclear Power Plants (NPP) needs be precisely assessed. For that very reason, Prognostics and Health Management (PHM) is so crucial as it determines best time for each equipment maintenance. At present, bottleneck of predictive maintenance prediction equipment's remaining useful life (RUL). With development artificial intelligent techniques, deep learning algorithms are becoming more popular RUL prediction. Upon this, this paper...

10.3389/fenrg.2020.584463 article EN cc-by Frontiers in Energy Research 2020-11-06
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