Study on the evolution and collection characteristics of droplet impact on a collector under space conditions
September 2025
The Liquid Droplet Radiator (LDR) exhibits superior specific thermal radiation capacity, yet its performance is hindered by droplet splashing and subsequent loss during high-speed collisions with the...
Dynamic analysis of cold end accident conditions for a space gas-cooled reactor coupled with He–Xe brayton cycle system
September 2025
Space nuclear power systems are promising for deep space missions. As the critical component of the space nuclear power system, radiators' performance significantly impacts both the cycle efficiency...
Simulation study of steam flow behavior and piping mechanical response analysis in safety valve discharge pipes with fluid-structure interaction
September 2025
This study numerically simulates the steam flow behavior and piping mechanical response within the safety valve discharge piping of a nuclear power system. A one-way Fluid-Structure Interaction (FSI)...
Study on X-ray fluorescence measurement method for Fe content in secondary circuit sampling filter membranes of nuclear power plants
September 2025
The measurement of iron (Fe) content in second-loop sampling filter membranes is critical for evaluating corrosion product deposition in pressurized water reactor (PWR) nuclear power plants. Traditional...
Application of isomorphic remote manipulators with haptic feedback in the development of automatic analysis equipment for spent fuel reprocessing samples
September 2025
Acid concentration and plutonium valence state in samples are crucial analytical parameters for process control during spent fuel reprocessing. Due to the high radioactivity and strong corrosiveness...
Effects of feedback color and icon shape on touch interaction performance under unstable conditions of floating nuclear power platforms
September 2025
In floating nuclear power platforms (FNPPs), the main control interface will gradually transition from traditional physical control panels to highly integrated, intelligent touchscreens. Existing research...
A study on data analysis utilizing the K-edge absorption spectroscopy in mixed thorium and uranium solutions
June 2025
X-ray absorption spectroscopy stands as a non-destructive assay technique commonly employed in nuclear fuel reprocessing plants to analyze the concentration of elements such as uranium, plutonium,thorium.The...
Research on applicability of containment test data for HPR1000 based on phenomena scaling
June 2025
The volume of the nuclear power plant containment is huge, making it difficult to conduct equal-scale or large-scale thermal-hydraulic tests. Currently the test data mainly come from small-scale tests....
A general two-group constants estimator for 17x17 PWR assembly configurations using artificial neural networks
June 2025
In this study, a preliminary general two-group constants predictor using artificial neural networks (ANNs) for pressurized water reactor (PWR) based assembly designs is established. Users can input...
Characteristics of aerosol release from fuel cladding breakage in lead-bismuth reactors
June 2025
Lead-bismuth reactors are the most promising type among the fourth-generation reactors. When the reactor operates for a long time, the fuel cladding may develop small breaches due to high temperatures...
Research on fault diagnosis method for nuclear power plants rotating machinery based on MoCo Siamese neural network
June 2025
Rotating machinery is a kind of significant equipment that widely used in nuclear power plants (NPPs). The harsh operating environment and long-term continuous operation of the rotating machinery can...
Validation and sensitivity analysis of the FLEXPART model using the Kincaid experiment data
June 2025
FLEXPART, a Lagrangian particle dispersion model, is widely used in atmospheric dispersion and nuclear emergency response studies. However, a systematic sensitivity analysis of this model is still lacking....
Study on prediction model of nitrogen oxide concentration in reprocessing plant based on random forest
June 2025
During the spent fuel reprocessing process, nitrogen oxides (NOx) gases are generated. The treatment and emission control of NOx rely on measurements from instrumentation. In situations where operating...
Numerical simulation study on oxygen transport in the natural circulation process of liquid lead–bismuth eutectic
June 2025
The lead-cooled fast reactor uses liquid lead–bismuth eutectic (LBE) as the coolant. In accident conditions, a passive cooling system is used to remove the heat from the reactor core to avoid meltdown....
Multi-objective optimization of 200 kW air centripetal turbine based on artificial neural networks
June 2025
The air-Brayton cycle has the characteristics of safety and high efficiency, which can be used as an energy conversion system for mobile small reactors. The air turbine is one of the key components...
Thermal hydraulic study of NuScale iPWR passive containment cooling behaviour during loss-of-coolant accident
June 2025
Operation of the NuScale emergency core cooling system (ECCS) was studied, with an emphasis on the crucial role of the containment vessel (CNV). Design parameters such as vessel volume were varied to...
Thermal mechanical response analysis of the first wall in laser initial confinement fusion reactors
June 2025
This paper investigates the thermo-mechanical response characteristics of the first wall of a laser initial confinement fusion reactor under periodic transient heat flux loads. The first wall of the...
Numerical study on the factors affecting natural ventilation cooling and structural optimization of glass curing body temporary storage
June 2025
Glass curing technology is a mature and effective technical means to deal with high level liquid waste produced by spent fuel reprocessing. The dry storage technology of glass curing body is a developing...
Performance of sodium cooled traveling wave reactor core with axial fuel shuffling strategy
June 2025
A prototype sodium cooled traveling wave reactor core with axial fuel shuffling, consist of an ignition and breeding region, was designed in this paper. Neutronic and depletion calculation was performed...
Experimental progress of 209Bi(n,G)210gBi cross-section measurement based on polonium self-deposition technique
June 2025
Lead bismuth eutectic alloy (LBE:44.5 wt%Pb+55.5 wt%Bi) is an important coolant candidate for fourth-generation reactors due to its good physical and chemical properties. However, the risk of radioactive...
Preliminary study on the postulated siting accident source term of integrated small reactor
March 2025
In accordance with the characteristics of integrated small reactor, a study was conducted on the postulated siting accident source term scheme. The principles for selecting accident types were explored...
Analysis of natural circulation characteristics for pool-type fast reactor system
March 2025
In the inherent safety design of the pool-type fast reactor, when the normal heat transfer routine of the primary system is lost during accident conditions, the residual heat of the reactor core is...
The impact of natural removal on the release of nuclides into the containment after accident
March 2025
The natural removal coefficient directly affects the amounts of radioactive iodine and aerosols released into the containment after the accident. The radioactivity calculation models in LOCA were established,...
Thermomechanical and radiological investigations of storage casks for radioactive spent fuel assemblies
March 2025
In this research, the Monte Carlo particle transport method and COMSOL Multiphysics were utilized to simulate and analyze the TK-13 cask, which contains spent fuel assemblies of the WWER-1000 reactor....
Drop analysis and numerical simulation of spent fuel transfer basket
March 2025
The spent fuel transfer basket is responsible for the transfer and storage of the assemblies, and the fall condition of the basket needs to be considered to ensure the critical safety of the spent fuel...
