Advanced nuclear power engine: A brief overview of gas core reactor for space exploration
June 2023
Space travel requires propulsion with high specific impulse. Gas core reactors using plasma nuclear fuel operate at high temperature (104-105K) and theoretically produce higher specific impulses (2500-7000s)...
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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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Steady-state thermal fluids analysis for the HTR-PM equilibrium core
2021
The high temperature gas-cooled reactor-pebble bed module (HTR-PM), designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, is a demonstration project of nuclear...
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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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Analysis of explosion incidents in nuclear fuel reprocessing facilities and recommendations for their prevention
June 2024
Human society endeavors to harness nuclear energy for peaceful utilization, intertwining it with global strategies to address pressing issues such as energy demand, environmental preservation, and energy...
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Phenomena identification Ranking Table (PIRT) study for suppression containment of small modular reactor using new methodology
June 2023
The Phenomena Identification and Ranking Table (PIRT) is a significant method for analyzing the safety of nuclear reactors. It helps researchers identify important phenomena within the reactor, enabling...
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Conceptual design of a novel megawatt portable nuclear power system by supercritical carbon dioxide brayton cycle coupled with heat pipe cooled reactor
December 2023
In order to meet realistic requirements for flexible and reliable power supply in special scenarios such as remote areas and deep ocean exploration, a novel megawatt portable nuclear power system called...
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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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Advanced manufacturing technologies for enhancing security in nuclear and radiological materials transport
September 2023
Advanced manufacturing technologies have transformed various industries, including nuclear security areas such as nuclear and radiological transport. This review manuscript describes the intersection...
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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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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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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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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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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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Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code
2021
In this research, a conceptual approach is presented to obtain the neutron flux at a reactor core. A simple spherical reactor core was analyzed by a mathematical model defined by Delphi programming...
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Experimental study on flow characteristics of rectangular narrow channel
2020
Plate fuel elements is gradually used in advanced reactor structure design because of its advantages of high fuel consumption and high safety. The flow channel of the plate fuel element is a typical...
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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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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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Advancements in the research of high-temperature gas-cooled reactor fuel via additive manufacturing techniques
March 2024
Recent advances in high-temperature gas-cooled reactor fuel research have captured the global spotlight, as modern operating contexts demand innovative responses to unprecedented challenges. This article...
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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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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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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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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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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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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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