Most Cited Articles

Open access

ISSN: 2468-6050

Investigation of kaolin - Granite composite bricks for gamma radiation shielding

Electrochemical behavior and corrosion rate prediction study of alloy 690

Heat-transfer characteristics of screw tube in one-side high heat load condition for fusion reactor divertor application

Best estimate plus uncertainty analysis of the China advanced large-scale PWR during LBLOCA scenarios

Experimental study on flow characteristics of rectangular narrow channel

Experimental and numerical investigation of two phase ejector performance with the water injected into the induced flow

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

Studies on post-dryout heat transfer in R-134a vertical flow

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

Assessment of radiological safety and emergency response of VVER-1200 type reactor

Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core

Numerical investigation of the thermal-hydraulic characteristics of AP1000 steam generator U-tubes

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

Calculation of flow heat transfer characteristics of liquid gallium

Study on the thermal and geometrical parameters of helical coil once-through steam generator system

Influence of zinc injection on deposition of corrosion products on inner wall of heat transfer tube

Study on startup characteristics of prototype once-through steam generator for China fast reactor

IVR design and review of advanced NPPs in China: Issues and perspectives

Experimental study on aerosol behavior in water pool scrubbing under severe accident conditions

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

Tomographic imaging of two-phase flow

Development and evaluation of fuel performance analysis code FuSPAC

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