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ISSN: 2468-6050

Study on prediction model of nitrogen oxide concentration in reprocessing plant based on random forest

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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Advanced nuclear power engine: A brief overview of gas core reactor for space exploration

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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Steady-state thermal fluids analysis for the HTR-PM equilibrium core

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

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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Thermal hydraulic study of NuScale iPWR passive containment cooling behaviour during loss-of-coolant accident

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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Validation and sensitivity analysis of the FLEXPART model using the Kincaid experiment data

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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Conceptual design of a novel megawatt portable nuclear power system by supercritical carbon dioxide brayton cycle coupled with heat pipe cooled reactor

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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Analysis of explosion incidents in nuclear fuel reprocessing facilities and recommendations for their prevention

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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A general two-group constants estimator for 17x17 PWR assembly configurations using artificial neural networks

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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Multi-objective optimization of 200 kW air centripetal turbine based on artificial neural networks

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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Review of spatial scale dispersion models (ATDMs) to simulate environmental dispersion and deposition of radionuclides and the overview of GIS coupling with dispersion models

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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Phenomena identification Ranking Table (PIRT) study for suppression containment of small modular reactor using new methodology

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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Research on fault diagnosis method for nuclear power plants rotating machinery based on MoCo Siamese neural network

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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Advanced manufacturing technologies for enhancing security in nuclear and radiological materials transport

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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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

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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Thermal mechanical response analysis of the first wall in laser initial confinement fusion reactors

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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Experimental study on flow characteristics of rectangular narrow channel

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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Ensuring safety in the Air transport of radioactive materials: Regulations, methodologies, and probabilistic safety assessment

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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Experimental progress of 209Bi(n,G)210gBi cross-section measurement based on polonium self-deposition technique

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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Characteristics of aerosol release from fuel cladding breakage in lead-bismuth reactors

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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A study on data analysis utilizing the K-edge absorption spectroscopy in mixed thorium and uranium solutions

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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Debris filtering efficiency assessment of the fuel assembly bottom nozzle

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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Numerical study on PWR fuel rod cladding ballooning and burst behavior with the thermo-mechanical coupling finite element method

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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Numerical study on the factors affecting natural ventilation cooling and structural optimization of glass curing body temporary storage

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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Thermomechanical and radiological investigations of storage casks for radioactive spent fuel assemblies

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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