Study on the flow and mechanical properties of the control rod guide tube assembly
September 2026
To investigate the impact of coolant flow within a 2×2 control rod guide tube (CRGT) assembly on the deformation and wear of control rods, this study employed a synergistic approach utilizing both experimental...
Enhancing the efficiency of Mo-99 production in an IAEA 10 MW research reactor through OpenMC-based neutron transport modeling
September 2026
Molybdenum-99 (Mo-99) is a crucial radioisotope widely used in nuclear medicine as the precursor of technetium-99 m (Tc-99 m), which plays a significant role in medical imaging and diagnosis. This study...
Proposal of a drag coefficient model for bubble chain rising in stagnant LBE pool based on volume of fluid method
September 2026
In the event of a steam generator tube rupture (SGTR) accident in a liquid lead-bismuth eutectic (LBE)-cooled reactor (LFR), a small rupture in the tube wall may lead to the leakage of high-pressure,...
Experimental study on disturbance wave characteristics of the bottom annular liquid film in a horizontal narrow rectangular channel
September 2026
The disturbance wave characteristics of annular flow in narrow rectangular channels are crucial for the accurate prediction of dry-out type critical heat flux in nuclear reactor fuel assembly systems....
Distribution-free fault-tree analysis for probabilistic risk assessment under uncertainty
September 2026
This paper proposes a Bayesian framework for a distribution-free fault-tree analysis using a probability-boxes and confidence-boxes to estimate the reliability of a complex coherent system. The approach...
Research on verification benchmarks for reactor thermal-hydraulic system analysis software
September 2026
Verification serves as the prerequisite for the engineering application of independently developed nuclear safety analysis software. Verification methods for reactor thermal-hydraulic system analysis...
Study on flow distribution characteristics of pool-type research reactor
September 2026
The core of a specific pool-type research reactor utilizes multiple closed plate-type fuel assemblies. Non-uniform coolant flow distribution among these assemblies can lead to localized overheating,...
Development of coupled analysis system for PWR design basis accidents using RETAC and ATHROC
September 2026
A coupled analysis framework based on RETAC and ATHROC was developed to support the safety evaluation of pressurized water reactors under design-basis accident conditions. The framework considers two...
Analysis of the effectiveness of in-vessel retention strategy under a three-layer corium pool configuration
September 2026
To cope with the corium cooling issue in severe PWR accidents, Generation III reactors commonly employ the IVR (in-vessel retention) approach, which involves flooding the reactor cavity. The stratification...
Simulation and analysis of typical operational conditions in a PWR based on Modelica
September 2026
With advantages such as rapid and simplified modeling and better compatibility with emerging technologies, Modelica is one of the key technical pathways driving the digitalization of future nuclear...
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...
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...
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...
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...
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...