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ISSN: 2468-6050

Electrochemical behavior and corrosion rate prediction study of alloy 690

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Study on iterative algorithm of full plate cross-flow and counter-flow printed circuit heat exchanger for fluoride-salt-cooled high-temperature advanced reactor

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Prediction of heat transfer coefficients for steam condensation in the presence of air based on ANN method

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Numerical investigation on transverse flow of helical cruciform fuel rod assembly in a lead-bismuth cooled fast reactor

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The evaporation of nanoscale sodium liquid film on the non-ideal nanostructure surface: A molecular dynamics study

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Experimental investigation of nano-particle deposited wick Structure's heat transfer characteristics

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Development of an edge-cloud collaboration framework for fission battery management system

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Numerical study of gas-injection induced pool sloshing behavior using MPS method

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

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

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

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Influence analysis of alloy elements on irradiation embrittlement of RPV steel based on deep neural network

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Characteristic analysis of natural circulation residual heat removal in small reactor

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Preliminary study on FROBA-SCO2 with transient models and its application for Reactivity Initiated Accident and loss of flow accident

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Working properties of GEM-TPC at low pressure

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Analysis of radiation shielding effectiveness of hydride and borohydride metals for nuclear industry

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