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Proposal of point-wise power reconstruction for IRT-4M fuel assemblies in coupled Monte-Carlo calculations
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102
Safety Analysis Reports of First-Of-A-Kind Nuclear Reactors in Brazil: Proposal of Content for Deterministic Safety Analysis
Published 2025-02-01“… The main documents of Licensing processes for nuclear reactors in Brazil are the Preliminary Safety Analysis Report (PSAR), in the construction phase, and the Final Safety Analysis Report (FSAR), in the operation phase (initial and permanent), as defined by the National Nuclear Energy Commission (CNEN). …”
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103
Techno-economic-assessment of the methanol synthesis from captured CO2 and modular nuclear power-based electrolysis
Published 2025-11-01“…The purpose of this work is to perform an eco-techno-economic assessment of the methanol production fueled by nuclear-power-driven electrolysis and captured CO2. …”
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Research on Correction Method for Uranium Interference in Passive Neutron Coincidence Counting Method for Pu Measurement in MOX Fuel
Published 2024-06-01“…In the production process of MOX fuel, the mass of uranium and plutonium must be accurately measured for nuclear material accounting requirements. …”
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IMITATING NEUTRON IRRADIATION DAMAGE USING A COMBINATION OF ION BEAMS
Published 2018-05-01“…The long-term goal of the authors is to create an ion irradiation methodology, which could be employed in the development process of innovative nuclear fuel materials. This methodology will be based on combining of a set of ion beams in such a way that the final distribution of irradiation-induced defects in the material structure is similar to the one which would have been introduced by neutrons in a nuclear reactor. …”
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Study on frictional behavior of SiCf/SiC composite clad tube clamping condition under nuclear irradiation
Published 2023-12-01“…Abstract Silicon carbide fiber reinforced silicon carbide matrix (SiCf/SiC) composite is the key cladding material of nuclear fuel, which determines the safety and reliability of nuclear fuel storage and transportation. …”
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109
High-Temperature Tensile Properties and Serrated Flow Behavior of FeCrAl Alloy for Accident-Tolerant Fuel Cladding
Published 2024-12-01“…The development of FeCrAl alloys has commenced for use as nuclear fuel cladding material, intended to serve as an enhanced accident-tolerant alternative to Zr-based alloys. …”
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AI-Powered Convolutional Neural Network Surrogate Modeling for High-Speed Finite Element Analysis in the NPPs Fuel Performance Framework
Published 2025-05-01“…Convolutional Neural Networks (CNNs) are proposed for use in the nuclear power plant domain as surrogate models to enhance the computational efficiency of finite element analyses in simulating nuclear fuel behavior under varying conditions. …”
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112
Rapid and greener vortex-assisted deep eutectic solvent-based dispersive liquid-liquid microextraction for spectroscopic determination of Hg in fuels
Published 2025-03-01“…Three distinct deep eutectic solvents (choline chloride + ethylene glycol, choline chloride + levulinic acid, and betaine + levulinic acid) were synthesized and characterized using Fourier Transform infra-red spectroscopy (FT-IR), Thermogravimetric analysis (TGA), and 13C nuclear magnetic resonance (NMR) for the preconcentration of Hg in fuel oils prior to quantification using inductively coupled plasma-optical emission spectroscopy (ICP-OES). …”
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113
Design and Experimental Investigation of Fluoride Volatility Fluidized Bed Reactor
Published 2025-06-01“…China’s nuclear energy development is implemented through a three-step strategy of pressurized water reactor-fast reactor-fusion reactor, accompanied by closed nuclear fuel cycle technology. …”
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Introduction of a New B3Y-Fetal Potential in the Semimicroscopic Analysis of the 15N + 27Al Nuclear System
Published 2025-03-01“… The experimental data analysis of the low-energy elastic scattering process in the 15N+27Al nuclear system used a new microscopic approach. …”
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115
Sustainable conversion of waste biomass using hydrothermal carbonization method
Published 2015-06-01Get full text
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116
Study on prediction model of nitrogen oxide concentration in reprocessing plant based on random forest
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117
Minor actinides transmutation in pressurized water reactors. 2. Using uranium and thorium fuel to burn minor actinides in a system with several VVER reactors
Published 2024-12-01“…In the previously published first part of the study by Kazansky and Karpovich 2022, the fuel cycle for VVER reactors was investigated: minor actinides obtained during reactor operation were extracted from spent nuclear fuel and added to fresh fuel for the same reactor. …”
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Validation of Water Radiolysis Models Against Experimental Data in Support of the Prediction of the Radiation-Induced Corrosion of Copper-Coated Used Fuel Containers
Published 2025-04-01“…Copper has been proposed as a container material for the disposal of used nuclear fuel in a number of countries worldwide. The container materials will be subject to various corrosion processes in a deep geological repository, including radiation-induced corrosion (RIC) resulting from the γ-irradiation of the near-field environment. …”
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120
Mitochondria power the nucleus under pressure
Published 2025-09-01“…This proximity provides a localized surge of ATP within the nucleus, fueling energy-intensive nuclear processes, notably maintaining an open chromatin state and facilitating efficient DNA damage repair. …”
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