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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Optimization study of lead-based reactor heat exchangers based on Dakota coupling CFD
June 2024
The lead-bismuth fast reactor is one of the fourth-generation reactor types.The microchannel heat exchangers are used as intermediate heat exchangers, which significantly influence the efficiency of...
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Research on reactor power prediction of nuclear power plant based on multivariate optimization GRU model
June 2024
In the operation of nuclear power plants, the accurate prediction of power change trends is crucial for ensuring safety and stability. In this work, a ML-GRU-RS method, based on model-agnostic meta-learning...
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Method of out-of-pile high-temperature tests of low-melting materials in conditions of modeling a severe nuclear reactor accident
June 2024
This article is devoted to the technique for conducting experiments to study the nature of the interaction of low-melting metals with corium in the conditions of simulating a severe nuclear reactor...
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Investigate of electrochemical properties of Nd(II) and Nd(III) in eutectic LiCl–KCl molten salt
June 2024
Pyroprocessing is one of the promising methods to reprocess the spent nuclear fuel. Neodymium (Nd) constitutes about one third of rare earth in fission products, however, the electrochemical properties...
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Investigation of sodium fire aerosol diffusiophoresis deposition in concrete gaps during the processes within nuclear power plants
June 2024
Sodium fire accidents are among the high-risk incidents that nuclear power plants with sodium-cooled fast reactors pay close attention to. Sodium fire reactions can generate a considerable amount of...
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Experimental study of aerosol diffusiophoresis deposition in steel containment under external cooling measures
June 2024
The steel containment of an advanced passive Pressurized Water Reactor adopted a passive containment cooling system to transfer residual heat to the environment through the steel containment, where...
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Study on post-accident aerosol retention behavior in microchannels of steel containment in passive nuclear power plants
June 2024
During an accident at a nuclear power plant, even if the containment is not severely damaged or fails, radioactive aerosols can still leak into the environment through microchannels that potentially...
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Research on the configuration scheme and system parameter optimization of pumps in the component cooling system and sea water system for HPR1000
June 2024
The Component Cooling System (CCS) and the Sea Water System (SWS) of HPR1000 are heat removal systems related to the safety of nuclear power plants. In both CCS and SWS, the configuration of pumps is...
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The formation and stripping mechanism of oxide film on stainless steel surfaces
June 2024
Typically, equipment in nuclear facilities operating in nitric acid media are made of stainless steel. Retired equipment exhibits relatively high levels of radioactivity, and chemical cleaning is a...
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Ensuring safety in the Air transport of radioactive materials: Regulations, methodologies, and probabilistic safety assessment
June 2024
The paper is focused on comprehensive study on air transportation of radioactive materials, covering regulations and requirements, hazard identification and proposed a methodology to apply the Probabilistic...
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A comparative neutronic analysis of U–Th fuels as potential alternatives to traditional UO2 fuel for enhanced performance and safety in the ACP-100 SMR
June 2024
This study examines U–Th-based alternative fuel options for the ACP-100 reactor core through a neutronic lens. Neutronic simulations were performed utilizing the Monte Carlo SERPENT code for 540 EFPDs....
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