A5075367402- Risk and Safety Analysis
- Nuclear reactor physics and engineering
- Reliability and Maintenance Optimization
- Nuclear Engineering Thermal-Hydraulics
- Software Reliability and Analysis Research
- Nuclear Materials and Properties
- Fault Detection and Control Systems
- Probabilistic and Robust Engineering Design
- Nuclear and radioactivity studies
- Advanced Multi-Objective Optimization Algorithms
- CCD and CMOS Imaging Sensors
- Fusion materials and technologies
- Radiation Detection and Scintillator Technologies
- Power System Reliability and Maintenance
- Particle Detector Development and Performance
- Radioactive contamination and transfer
- Graphite, nuclear technology, radiation studies
- Metaheuristic Optimization Algorithms Research
- Marine and Coastal Research
- Software Testing and Debugging Techniques
- Real-time simulation and control systems
- Maritime Navigation and Safety
- Engineering Diagnostics and Reliability
- Smart Grid Security and Resilience
- Vehicle Routing Optimization Methods
Chinese Academy of Sciences
2018-2024
Hefei Institutes of Physical Science
2018-2024
Key Laboratory of Nuclear Radiation and Nuclear Energy Technology
2022-2023
Shanghai Jiao Tong University
2014-2016
Significance Despite great efforts to pursue a safe nuclear energy system during the first era, which was dominated by developed countries, severe accidents still occurred. Today, development has entered an unexpected second is driven developing countries. This may give rise risk. Nuclear power plants are complex sociotechnical systems, and their safety never been fully defined. We argue that social aspects, rather than just technical measures, must be involved ensure safety. In this paper,...
Deep learning–based nuclear intelligent fault detection and diagnosis (FDD) methods have been widely developed achieved very competitive results with the progress of artificial intelligence technology. However, pretrained model for tasks is hard in achieving good performance when reactor operation conditions are updated. On other hand, retraining a new data set will waste computing resources. This article proposes an FDD method cross-condition cross-facility based on optimized transferable...
AbstractCold-standby systems are often featured with small failure probability and widely used as critical safety in current engineering fields. The existing analysis methods for cold standby have the problems low-computional efficiency either events or components mixed distribution types. To solve these problems, we propose a self-stratifying subset simulation (4S) method based on MCMC performance function of cold-standby system. Numerical case studies performed to demonstrate reasonability...
Many practical systems are often involved in sequence-dependent failure behaviors. The efficiency of analyzing these dynamic is limited by addressing sequential events (SFEs). survival signature method has the potential to address this issue. However, cannot be applied directly due existence SFEs. In article, adapted signature-based methods developed for rapid analysis modeled fault trees with priority- <sc xmlns:mml="http://www.w3.org/1998/Math/MathML"...
Dynamic fault trees are important tools for modeling systems with sequence failure behaviors. The Markov chain state space method is the only analytical approach a repairable dynamic tree (DFT). However, this suffers from explosion, and not suitable analyzing large scale DFT. Furthermore, requires components’ time-to-failure to follow exponential distributions, which limits its application. In study, motivated efficiently analyze DFT, Monte Carlo simulation based on coupling of minimal cut...
Probabilistic Safety Assessment (PSA) is an important method to evaluate the safety concerns of Nuclear Power Plants (NPPs) from probability perspective. The Reliability, Availability, Maintainability, Inspectability (RAMI) approach was promoted by International Thermonuclear Experimental Reactor (ITER) organization system reliability and availability, reduce technical risks acceptable level perspective for fusion devices. Both PSA RAMI adopt probabilistic failure issues nuclear systems. In...
In complex nuclear energy redundancy systems, there are many failure events that do not follow specific time distribution. For these atypical time-distribution events, traditional dynamic fault tree (DFT) methods cannot be applied directly, which has posed great challenges to reliability modeling and evaluating. this contribution, we summarize in systems propose new evaluating based on DFT. To demonstrate the reasonability of proposed methods, two case studies about make-up water pumps...
Latin Hypercube Design (LHD) is widely used in computer simulation to solve large-scale, complex, nonlinear problems. The high-dimensional LHD (HLHD) problem one of the crucial issues and has been a large concern long run. This paper proposes an improved Hybrid Particle Swarm Optimization (IHPSO) algorithm find near-optimal HLHD by increasing particle evolution speed strengthening local search. In proposed algorithm, firstly, diversity population ensured through comprehensive learning....
Fusion reactors are expected to be more safe and environmentally friendly in the development of nuclear energy systems. It is vital fully understand overall radiation risk level fusion comparison with existing The objective this paper propose a assessment methodology for reactor accidents, which capable quantifying comparable other advanced In paper, specific accident characteristics comprehensively analyzed ITER fission reactors. postulated initiating events as well possible environmental...
Dynamic fault trees (DFTs) are powerful tools to model industrial systems having dynamic failure mechanisms, such as sequence- and function-dependent behaviors. Yet for large complex DFTs, their quantitative analyses still of great challenges. Up now, many researchers have presented several approaches deal with this problem, among which, the sum disjoint products (SDP) methods, binary decision tree, sequential diagram (SBDD), improved SBDD, proven be an efficient way. In SDP negating a...
Testing and maintenance activities of safety equipment have drawn much attention in Nuclear Power Plant (NPP) to risk cost control. The testing are often implemented compliance with the technical specification requirements. Technical maintenance-related parameters, that is, allowed outage time (AOT), period duration, so forth, NPP associated controlling level operating which need be minimized. above problems can formulated by a constrained multiobjective optimization model, is widely used...
Reasonable and feasible reliability index allocation is significant for improving safety reducing costs fusion reactors. Although the allocated when designing some key systems, not implemented from overall layer to system component layers In this contribution, reactors are divided into different by applying Analytic Hierarchy Process (AHP); these include layer, failure mode etc. Combining Probabilistic Safety Assessment (PSA) model AHP, layer. Firstly, a new method based on PSA AHP proposed....
“How safe is enough?” a key and fundamental question for any risky engineering safety goals has been extensively studied in many fields, such as chemical industry, nuclear etc. Fusion reactors are advanced which expected to be more attractive terms of environmental impact, remarkable progress made toward the realization fusion energy this regard. However, not guaranteed automatically: accidents could happen with possible future reactor, potentially resulting releases radioactive materials....
Loss of power supply from the diesel generator system (DGS) after loss offsite (LOOP) will pose great threat to safety GEN-II pressurized water reactors (PWR). Therefore, it is very desirable evaluate DGS’s reliability. The traditional analyzing tools are limited static approaches neglecting dynamic sequence failure behaviors, such as reliability block diagram (RBD), fault tree (SFT). Static modeling techniques not capable capturing sequence-dependent behaviors typically existing in NPP...
No-public evacuation is an expectation for fusion power plants (FPPs) from the public and governments. In this technical note, a preliminary consequence assessment of ITER wet bypass–like accident (the with most severe in ITER) helium-cooled deuterium-tritium tokamak FPP performed compared that ITER. Ideal gas–based methodology proposed to evaluate released materials accidents, which verified by typical cases FPPs. The verification indicates that, best estimated codes, method much simpler...
As one of the innovative researches in nuclear field, Advanced Modular Nuclear Systems (AMNS) has been wild concerned and paid more attention to maintenance safety problems. The rapid development sensors Internet Things (IoT) technology provides a new opportunity for safeguard operation AMNS. This paper proposes an Intelligent Prognostic Health Management (PHM) based Auxiliary Decision framework. designed framework acquires data uses emerging deep learning techniques monitor AMNS operations...