A5068736738- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Nuclear Physics and Applications
- Nuclear and radioactivity studies
- Fusion materials and technologies
- Cyclone Separators and Fluid Dynamics
- Nuclear Engineering Thermal-Hydraulics
- Molten salt chemistry and electrochemical processes
- Image Processing and 3D Reconstruction
- Radioactive element chemistry and processing
- Heat Transfer and Boiling Studies
- Advanced Sensor and Control Systems
- Particle Dynamics in Fluid Flows
- Advanced Computational Techniques and Applications
- Fluid Dynamics and Mixing
- Spacecraft and Cryogenic Technologies
- Robotic Mechanisms and Dynamics
- Wind and Air Flow Studies
- Advanced Numerical Analysis Techniques
- Power Systems and Renewable Energy
- Geochemistry and Elemental Analysis
- Metallurgical Processes and Thermodynamics
- Advanced Algorithms and Applications
- Advanced Mathematical Modeling in Engineering
Shanghai Institute of Applied Physics
2016-2025
Chinese Academy of Sciences
2016-2025
University of Chinese Academy of Sciences
2015-2024
Zaozhuang University
2023
Hebei University
2010
University of Electronic Science and Technology of China
2009
Using low enrichment uranium as driver fuel under once-through mode in molten salt reactor (MSR) attracts more and attention because of its availability, no new technology, nuclear nonproliferation. It is regarded a wise research development road to shorten deployment time MSRs prepare techniques experiences for thorium-uranium breeding the future. However, this management still faced with some different technical routes, such selection carrier salts, uranium, or without thorium, recycle...
As a type of fourth-generation advanced nuclear reactor, Molten Salt Reactors (MSRs) utilize liquid molten salt as fuel. The circulation this fuel leads to widespread distribution radioactive gases within the MSRs, which can affect their safe operation. In paper, fission 87 Kr and 135m Xe are research subjects. Computational Fluid Dynamics (CFD) - FLUENT is employed analyze leak migration behavior these reactor containment under various leakage scenarios. studies show that: (1) gas flow...
In molten salt reactors (MSRs), a small amount of inert gas could be entrained from the free liquid surface to primary loop, which may have obvious impacts on heat transfer performance exchanger, reactivity core, and migration insoluble fission products. It is necessary understand how bubbles flow into reactor what kinds size distribution should they be. Meanwhile, exchanger an important complicated place before enters in exhibit complex behavior, such as coalescence, breakup, or retention....
Graphite is an excellent moderator widely used in fission nuclear reactors. However, the component dimensions and physical properties of graphite will be apparently affected by neutron radiation during reactor operation. In molten salt reactors (MSRs), dimensional change not only cause structural integrity issue, but also have obvious impacts on neutronic thermal-hydraulic behaviors due to volume fraction (VF) fuel active core. Considering these effects synthetically, we developed a...
Dimensional change of the graphite assemblies due to irradiation is a key factor in limiting service lifespan reactor core small modular molten salt reactors. The assembly structure, determining fast neutron flux distribution and temperature distribution, has notable impact on its dimensional hence lifespan. In this article, we put forward an innovative solid hexagonal prism (HPA) surrounded by fuel prolong compare it with traditional round channel (RCA) flowing through central channel....
The SM-MSR (small modular molten salt reactor) has a good prospect for development with regards to combining the superiority of reactor and modularization technologies, showing advantages safety, reliability, low economic cost flexibility site selection. However, because its internal structural parts are not easily replaced, outer shielding structure is limited, lifespan vessel in-reactor design needs be addressed. In order find an optimal model both high fuel efficiency strong radiation...