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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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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Numerical study on PWR fuel rod cladding ballooning and burst behavior with the thermo-mechanical coupling finite element method
March 2025
The ballooning behavior of fuel rod cladding is an important issue of nuclear reactor, which may initiate a severe nuclear reactor accident. Based on COMSOL multi-physical module, this research established...
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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,...
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Debris filtering efficiency assessment of the fuel assembly bottom nozzle
March 2025
The debris-induced fretting wear is a key factor to cause the fuel failure in pressurized water reactor (PWR). Assessing the debris filtering efficiency of bottom nozzle is an important way to analyze...
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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....
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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...
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Review of spatial scale dispersion models (ATDMs) to simulate environmental dispersion and deposition of radionuclides and the overview of GIS coupling with dispersion models
December 2024
Estimation of the radiological consequences including the calculation of radiation doses to the exposed population requires numerical evaluation of atmospheric radioactive releases from nuclear facilities...
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Study of a multi-factor coupling removal model for gas-borne source terms under jet flow conditions
December 2024
After a pipe rupture in the reactor steam generator, high-temperature and high-pressure radioactive materials from the primary circuit enter the secondary side of the steam generator via a jet flow....
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24-Month long cycle fuel management research based on accident tolerant fuel
December 2024
As the installed nuclear power plants steadily increase in China, the demand for 24-month long cycle fuel management is gradually increasing as well. 18-month refueling strategy is mainly applied in...
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An open-source Thermo-hydraulic Uniphase Advection and Convection Solver for Salt Flows (TUAS)
December 2024
Due to a lack of open-source GUI simulators and corresponding system level simulation libraries for Gen IV Reactors such as the Fluoride Salt Cooled High Temperature Reactor (FHR), a systems level library...
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Experimental study of Portland cement concrete performance at moderately-elevated temperature
September 2024
Concrete, as the most commonly-used construction materials, is used for thousands of structures, including buildings in nuclear power plants. Some concrete structures in nuclear power plants are subjected...
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Characterization of oxygen transport in a lead-bismuth natural circulation loop
September 2024
To investigate the oxygen mass transfer characteristics of a lead-bismuth natural circulation loop, numerical simulations of flow, heat transfer, and oxygen mass transfer processes were conducted using...
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Condensation film flowing dynamics on inclined downward facing plate: Experimental and modeling study
September 2024
In-containment refueling water storage tanks have been equipped as an important coolant source for passive cooling systems in the third-generation reactors. Condensate film collection from the containment...
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Thermal analysis of irradiated secondary neutron source assembly with wet transportation
September 2024
The irradiated secondary neutron source assembly can be used to start-up reactors. After irradiated, secondary neutron source assembly will produce neutron and γ. So, when used to start-up reactors,...
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Study on the characteristics of aerosol diffusiophoresis deposition on the outer surface of a vertical circular tube
September 2024
The deposition behavior of aerosols due to diffusiophoresis directly influences the migration and deposition of radioactive materials following an accident. This is critical in analyzing source term...
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