Pipe-Diameter Effects on Horizontal Gas-Liquid Flow Regimes and Pressure Drop: A Nuclear Thermal-Hydraulic Review
Available online 24 September 2026
This review systematically examines the influence of pipe diameter on horizontal gas-liquid two-phase flow, focusing on flow regimes, regime transitions, frictional pressure drop, and predictive modeling...
Development and Verification of an Integrated Semi-Implicit Pressure Coupling Framework for SACOS and VITARS
Available online 20 September 2026
An integrated semi-implicit pressure-coupling framework, VITARS-SC 2.0, was developed to combine the system-scale capabilities of VITARS with the subchannel resolution of SACOS. Unlike the previous...
Preliminary Assessment of Multiscale System–Subchannel Coupling for Reactor Thermal-Hydraulic Analysis
Available online 19 September 2026
System thermal-hydraulic codes efficiently predict reactor-circuit transients, but their simplified core models provide limited information on assembly-scale flow and temperature redistribution. VITARS-SC...
Study on the Testing Method for Lithium-7 Isotopic Abundance in Nuclear-Grade Lithium-Type Cation Exchange Resins
Available online 11 September 2026
To address the lack of standardized testing methods for lithium-7 (7Li) abundance in nuclear-grade lithium-type resins in China and provide a technical basis for judging compliance with the control...
Research progress on irradiation damage of Molybdenum-Rhenium alloys
June 2026
Renowned for their outstanding creep resistance and high-temperature performance, Molybdenum–Rhenium (Mo–Re) alloys are now prime candidates for structural applications in nuclear reactors and first-wall...
Development status of small modular fast reactors
June 2026
Small modular reactors (SMRs) offer significant prospects for widespread application due to their compact size, modularity, low cost and short construction period, rapid deployment capability, ease...
Study on the influence of inclination conditions on flow instability in parallel rectangular channels under natural circulation conditions
June 2026
An experimental study was investigated on the effect of inclination conditions on flow instability in parallel rectangular channels within natural circulation systems. Findsings reveal that at 12 MPa,...
Data-driven excess Xe reactivity modeling in CANDU nuclear reactor using machine learning methods
June 2026
The prediction and control of excess Xenon reactivity are critical challenges in ensuring the safe and stable operation of nuclear reactors, particularly in CANDU-type reactors, where xenon-induced...
Uncertainty and sensitivity analysis for small PWR station blackout accidents
June 2026
Based on the ASTRUM method, an uncertainty analysis of hydrogen production and severe accident process under severe accident conditions of small pressurized water reactors was conducted with respect...
Turbulent Prandtl number analysis of helium-xenon gas flow and heat transfer in the parallel channel
June 2026
The helium-xenon gas mixtures (15-40 g/mol) are used in various designs of small gas-cooled nuclear reactor systems with Prandtl number (Pr) from 0.2 to 0.3. The low Pr values have an effect on the...
Preliminary neutronic analysis of UN fuel and SiC cladding for advanced accident tolerant fuel in LWRs
June 2026
Accident Tolerant Fuel (ATF) technologies have emerged in response to the safety limitations of conventional UO2-Zr fuel systems in light water reactors (LWRs), particularly under high-temperature accident...
Analysis of stress and fatigue damage of centrifugal turbine in air Brayton cycle system under transient conditions
June 2026
The air Brayton cycle is distinguished by its high efficiency, flexible start-up and shutdown capabilities, and environmental friendliness—attributes that render it a suitable energy conversion system...
Theoretical and experimental study on heat transfer characteristics of water heat pipe
June 2026
The heat pipe is an efficient heat transfer element based on two-phase natural circulation. It offers the advantages of a simple structure, strong heat transfer capability, and excellent isothermal...
A sensor and actuator fault diagnosis method for supercritical carbon dioxide direct cooled nuclear reactor system
June 2026
The safe and stable operation of nuclear power plants heavily relies on the reliability of sensors and actuators within instrumentation and control systems. The supercritical carbon dioxide direct cooled...
Analysis of causes for high silicon content in the in-containment refueling water storage tank of a nuclear power plant
June 2026
Addressing the issue of abnormally high silicon content in the In-containment Refueling Water Storage Tank (IRWST) of a Hualong One unit at a nuclear power plant during its first cycle and subsequent...
Study on thermal-hydraulic response characteristics of internal compartments in the containment building under LOCA conditions
June 2026
Investigating the thermal-hydraulic response characteristics of internal compartments within the containment structure during LOCA accidents holds significant scientific, engineering, and safety value...
Advanced UZrH Research Reactor design, Part II: coolant and irradiation loop systems
June 2026
The Uranium–Zirconium Hydride (UZrH) Research Reactor is a type of research reactor that utilizes UZrH fuel as its core fuel, providing irradiation services and generating neutron beams. Currently,...
Advanced UZrH research reactor design, part I: thermal-hydraulic review
June 2026
Uranium–Zirconium Hydride (UZrH) research reactor is a type of research reactor that uses UZrH fuel as its core fuel. This reactor type typically employs a pool-type coolant system design, offering...
Multiphysics study on phase separation and thermal aggregation effects in the melt pool of the reactor lower head under severe accidents
June 2026
In the progression of severe accidents in light water reactors, the retention of core melt in the reactor pressure vessel (RPV) lower head, known as In-Vessel Retention (IVR), constitutes a core strategy...
Experimental investigation of the spatial evolution of local flow parameters in vertical LBE–N2 bubbly flow
June 2026
To support closure-model development for thermal-hydraulic analysis of SGTR/HXTR-related two-phase flow in lead-cooled fast reactors, a separate-effect experimental study was conducted on lead–bismuth...
Heat transfer characteristics of two-layer corium pool with additional metallic layer heat source
June 2026
Due to material oxidation, activation, and the presence of fission products and uranium, the metallic layer in a two-layer corium pool contains internal heat sources. This study investigated the influence...
Hybrid burnable absorber design based on ATF and application in 24-month long cycle fuel management
March 2026
In order to meet the requirement of reactivity control for 24-month long cycle, an optimization design of burnable absorber based on accident tolerant fuel (ATF) is carried out. The design of hybrid...
Experimental study on gravity settling of aerosols inside the containment vessel of nuclear power plants
March 2026
Gravity setting is an important factor in the natural removal of aerosols in the containment. In this text, it is carried out to the experimental study of aerosol gravity setting in the containment...
Back propagation neural network-based prediction of critical heat flux in vertical and inclined tubes
March 2026
Due to their unique advantages, offshore floating nuclear power plants have broad application prospects. Unlike land-based reactors, it is essential to conduct in-depth research on the characteristics...
Reactivity safety analysis of an air-cooled nuclear thermal propulsion reactor
March 2026
As the most promising alternative to chemical propulsion, nuclear thermal propulsion technology has been extensively studied in recent years. However, most existing research lacks comprehensive safety...