Study on the direct measurement method for trace plutonium in samples from spent fuel reprocessing
September 2025
To directly, rapidly, and accurately measure trace plutonium in reprocessing samples, two α scintillation counters were developed for the direct measurement of liquids and solids after source preparation....
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Research on temperature composite control system for radioactive waste incineration equipment
September 2025
This paper presents a multi-mode control scheme for the temperature regulation of radioactive waste incineration equipment, integrating modern and fuzzy control theories. Separate controllers were designed...
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Study on the method of measuring the interface of radioactive liquid by air blowing
September 2025
Aiming at the interfacial measurement method of radioactive liquids, we propose and validate a program to realize the interfacial measurement of radioactive liquids by using the air blowing method....
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Research on container for high-level radioactive waste vitrification product
September 2025
Product containers for high-level radioactive waste liquid vitrified glass are critical components for ensuring continuous and stable operation of vitrification plants. Given the substantial demand...
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Vibration response simulation of centrifuge excited by liquid medium based on SPH-FEM
September 2025
A coupled Smoothed Particle Hydrodynamics-Finite Element Method (SPH-FEM) framework is implemented to study flow-induced vibration problems of a decanter centrifuge drum under operational conditions....
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Research on skin dose assessment methods after severe accidents in nuclear power plants
September 2025
In the event of a severe accident at the nuclear power plant, the radioactive plume can cause external immersion exposure and deposition exposure to the skin. The predominant code utilized for estimating...
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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...
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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....
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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...
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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...
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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...
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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....
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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...
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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....
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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...
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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...
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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...
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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...
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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...
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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...
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Research on Fluid-Structure Interaction of Spent Fuel Storage and Transportation Basket
Available online 21 June 2025
The structural form of the spent fuel storage and transportation basket is different from that of the traditional rack, and the FSI parameters depend on the structural form. It is uncertain whether...
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Impact of Revised RG 1.183 on Source Terms and Radiological Consequences of Rod Ejection Accident for the HRP1000 reactor
Available online 19 June 2025
This paper compares and analyzes the impact of the revised RG 1.183 on the source term and radioactive consequences of the rod ejection accident. The revision of RG 1.183 has resulted in changes to...
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Numerical Simulation of Humidification Process by Spray Evaporation under Different Air Pressure and Temperature
Available online 6 June 2025
In special industrial fields, when dry compressed air enters process fluids containing radioactive substances, it often carries radioactive water vapor. To effectively solve this problem, it is necessary...
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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...
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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...
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