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Publications (999)
Evaporation of liquids from porous media plays a significant role in both natural and industrial applications. Evaporation is influenced by various factors, including porous structure, wettability, and thermal gradients, making it difficult to understand the underlying mechanisms and therefore manipulate the evaporation process. In the present stud...
Flow-induced vibrations pose significant risks to the long-term operation of the helical coil steam generator (HCSG). Developing effective mitigating measures heavily relies on clearly understanding the internal turbulent flow. This study investigates helium flow within a 30-degree central region of heat transfer assemblies in the HCSG of the high-...
This paper focuses on the passive residual heat removal system of a typical large advanced pressurized water reactor, analyzing its design, performance, and reliability during station blackout conditions combined with the failure of the auxiliary feedwater steam-driven pumps. The study employs modeling of passive safety systems and utilizes respons...
Flow channel contractions and expansions often lead to flow separation and accelerated fouling deposition, particularly around the tube support plate (TSP) in steam generators. This study employed large eddy simulation (LES) coupled with the discrete phase model (DPM) to analyze deposition mechanisms at various locations within these flow configura...
Blockage accidents are critical scenarios in the design and safety analysis of lead-bismuth cooled fast reactor (LFR) core. Traditional analysis of blockage accidents in LFR focuses on localized, fine-scale computational fluid dynamics (CFD) simulations of single or three assemblies, but the analysis of the whole core scale impact caused by blockag...
Physics-Informed Neural Network (PINN) integrates Deep Neural Networks (DNN) with physical principles to solve complex physical systems. While its computational accuracy and speed have yet to surpass traditional methods. To enhance the performance of PINN in solving complex nonlinear differential equations within the domain of thermal–hydraulic in...
The new generation of reactor technology, Fluoride-Salt-cooled high-Temperature Advanced Reactor (FuSTAR), is primarily intended for use in remote, underground, and arid areas. The design of the heat transport system and Passive Residual Heat Removal System (PRHRS) for FuSTAR has been completed, but verification is still pending. This study utilize...
The helical coil once-through steam generator (HCOTSG) has a complex internal structure, and nonlinear oscillatory forces acting on the fluid under motion conditions affect its flow and heat transfer characteristics. Studying the thermal-hydraulic properties under these conditions is crucial for the design, operation, and maintenance of steam gener...
The buoyancy-aided sodium flow in a vertical channel is investigated using direct numerical simulation (DNS) to study turbulent flow and heat transfer at six different Richardson numbers (Ri = 0, Ri = 0.025, Ri = 0.25, Ri = 2.5, Ri = 7.5, and Ri = 15) with a fixed friction Reynolds number (Reτ = 180). The results reveal that the velocity profile sh...
To evaluate the impact of temperature fluctuations caused by jet mixing in the upper plenum of a lead-bismuth eutectic (LBE) reactor on the fatigue damage of internal structural components, this paper conducts a study on the stress distribution of the operation head and the central column based on a fluid-solid coupling calculation method. On this...
When the molten core-concrete interaction (MCCI) occurs in a reactor, the high-temperature melt may melt through the concrete bottom plate and form a molten pool. At the same time, due to the heat generated by decay heat and chemical reactions, the concrete will decompose and produce a large amount of water vapor and carbon dioxide and other gases....
The nozzle plays a significant role in the nuclear power plant’s safety and the reactor’s integrity. The structure of the nozzle directly affects the atomization performance, consequently impacting the pressure and temperature variations within the regulator. This study focuses on the single inlet pressure-swirl nozzle structure, employing the resp...
MYRRHA is the Gen IV liquid metal cooled fast reactor, which is a pool-type reactor system developed and designed by the Belgian Nuclear Research Center SCK·CEN. Regarding the safety assessment of the installation, the major challenge is to analyze the complex coolant flow field characteristics in the large open regions of the reactor vessel. In th...
As a high-efficiency heat transfer element, heat pipe can be well adapted to the application scenarios of high heat flow density and high safety requirements in the field of nuclear engineering. This paper carries out experiments on a high-temperature sodium heat pipe, and obtains its operating characteristics in the straight pipe state and the ben...
As a representative of Generation IV nuclear energy systems, sodium-cooled fast reactors (SFR) may cause the liquid sodium flowing through the core to boil after a Core Disruptive Accident (CDA), which then forms a high-energy vapor cavity expansion to push the liquid sodium above, causing an impact failure to the main vessel structure in a very sh...
High-temperature heat pipe is an ideal technical solution for microreactors applied for space missions, planet surface, and the small electricity markets on the ground. However, the internal fluid flow state and the effects of key parameters such as permeability, porosity, and capillary force of wick structure on the distribution of working fluid i...
The thermal-hydraulic system code is an important support of the design, safety and operation of nuclear reactor. With the rapid development of numerical methods and software engineering, the modernization of thermal-hydraulic system code development becomes more and more important. Based on the open source finite volume solution platform OpenFOAM,...
The critical heat flux is the heat flux when the heat transfer on the surface of the nuclear fuel element deteriorates. Once CHF occurs, the fuel element temperature will rise sharply, resulting in a serious nuclear accident. Motion conditions impact the nuclear reactor in a number of ways, including the micro-level CHF mechanism as well as the flo...
High-temperature heat pipe is a passive and efficient heat transfer element, which is generally filled with a certain mass of alkali metal as the heat transfer medium, and utilizes vapor-liquid phase change to efficiently transfer heat from the evaporation section to the condensation section of the heat pipe. In the normal operation of high-tempera...
Heat pipe is the most critical heat transfer element in the silent heat pipe reactor, which utilizes the phase change of the work material to carry out heat transfer work through gravity, centripetal force and capillary force, and works stably under high temperature conditions with high heat transfer efficiency. Large-diameter high-temperature heat...
CFD simulations of multiphase behavior are essential in the safety analysis of nuclear reactors. As a particle method, the MPS method inherently possesses the capability of capturing interfaces or free surfaces. The PArticle method for Nuclear reactor thermal hyDraulic Analysis (PANDA) is a software platform based on particle methods, aiming to pro...
Helical cruciform fuel, due to its unique geometric shape, affects heat transfer, thereby improving the power level and safety margin of existing pressurized water reactors. This article establishes a unidirectional neutron thermal coupling calculation method for the complex geometric cross-section of helical cruciform fuel to study its flow and he...
The LBE- or Lead-cooled fast reactor (LFR) is an important candidate reactor for the Generation-IV nuclear energy systems, where the Molten Fuel-Coolant Interaction (MFCI) process differs from that occurred in light water reactors and sodium cooled fast reactors due to the coolant property differences. In the lack of experimental and numerical stud...
Subchannel codes play an important role in the thermal-hydraulic analysis of reactor cores. Based on the open-source CFD software OpenFOAM, the research team developed CorTAF, a finite volume method-based thermal-hydraulic analysis code for the core subchannel level. All the CorTAF codes are done on OpenFOAM, which has the function of calculating d...
Steam generator (SG) stands as a pivotal element within the primary circuit pressure boundary of nuclear power plants, functioning as a critical safety barrier against potential radioactive leaks. Throughout its operational lifecycle, the introduction of foreign objects (FOs) with diverse shapes into the secondary side of the SG may occur due to va...
This study focuses on energy transfer within the implosion target of a Laser Inertial Confinement Fusion Reactor (LICFR). The study involves an analysis of heat transfer and tritium production within the Tritium Breeding Blanket (TBM) and the energy cycle of the secondary loop.
The research is based on an operating condition of 200MW. Super critica...
With the increasing emphasis on the refinement of reactor thermal hydraulic calculations, research on multi-scale coupled models of nuclear reactor thermal hydraulic has also developed. This article utilizes the self-developed lead bismuth system analysis program SACLER, combined with the mature commercial CFD software FLUENT, to develop a coupled...
Liquid lead and lead-bismuth eutectic (LBE) are favored as primary side coolants for lead-cooled fast reactors due to their high heat carrying capacity, density, and boiling point. However, these liquids exhibit strong oxidation effects, leading to the formation of solid lead oxide particles. Additionally, they exert significant corrosion effects o...
In order to overcome the shortcomings of Computational Fluid Dynamics (CFD), which needs to consume a lot of computational resources and time to obtain the flow field information. In this paper, a non-intrusive reduced-order model was developed based on the POD an BP neural network. Then the established ROM was applied in the temperature filed rapi...
The Lead-bismuth cooled Fast Reactors (LFR) utilizes wrapped hexagonal fuel assemblies arranged in a honeycomb pattern. The inter-wrapper flow (IWF) between adjacent assemblies has a significant influence on the core thermal-hydraulics. In this paper, the LFR core assembly analysis model, inter-wrapper flow and heat transfer model, and multi-scale...
In this paper, the bubble migration characteristics of LFR after SGTR accidents are investigated based on the DPM. Firstly, the geometric and mesh models of the primary coolant system of the LFR are established, and the drag coefficient model of bubbles in the DPM is validated based on the bubble terminal velocities. Secondly, steady-state simulati...
Because of the unique design of Lead-cooled Fast Reactor (LFR), the steam generator tubes containing high-pressure water is placed directly in the high temperature lead pool, therefore once a steam generator water tube ruptures during operation, the high-pressure subcooled feed water would interact directly with hot lead, giving rise to Steam Gener...
In sodium-cooled fast reactor, once-through steam generator (OTSG) is an important heat transfer component, and it is also one of components that is prone to failure. The safe and stable operation of this equipment is crucial to the safety of sodium-cooled fast reactors. The steam generator has a sizable number of heat exchange tubes. Variations of...
The lead-bismuth cooled fast reactor core adopts box-type design, and the fuel rod bundle is fixed by wrapping wires. The complex geometric structure of the fuel assemblies significantly affects the flow and heat transfer status of the liquid metal coolant. Building upon the open-source CFD platform, OpenFOAM, this work established conservation equ...
The lead-cooled fast reactor (LFR) adopts the liquid lead-bismuth eutectic (LBE) as the primary coolant. Since LBE has the low Prandtl number property, that will cause the pattern between thermal transport and momentum transport to be mismatched and the failure of the Reynolds analogy theory. In this study, a new one-equation model of eddy diffusiv...
Atomization and sprays are widely used in industry and agriculture. An appropriate atomization simulation method is essential in analyzing the liquid film-breaking process and atomization performance, especially in large-scale atomization field calculations. This study innovatively proposes a portioned method that combines existing fundamental atom...
