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...
Study on the radioactive sludge retrieval technology
March 2026
In this paper, through the large radioactive liquid waste tank sludge retrieval engineering requirements, tank bottom sludge back technology status, combined with the large radioactive liquid waste...
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...
Numerical study on cladding burst behavior considering irradiation and oxidation with the multiphysics coupling method
March 2026
This study investigates alterations in the performance of fuel rod cladding during loss of coolant accident through the development of a two-dimensional axisymmetric burst analytical model using COMSOL...
Study on thermal hydraulic characters of corrugated plate dryer based on DPM coupled ELFM method
March 2026
To improve the structures and characteristics of the steam generator corrugated plate dryer and increase the steam-liquid separation efficiency, the discrete phase model (DPM) coupled with the Eulerian...
Method for measuring the adsorbed radioactivity source term of fission nuclide 131I in lead–bismuth reactors
March 2026
131I is a typical fission product in nuclear reactors. It has a strong affinity for the human thyroid gland and is an important nuclide of concern in radiation protection under both normal and accident...
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...
Study of cosCONT heat transfer model based on NUPEC M-7-1
March 2026
The cosCONT module within the COSINE code package is designed for containment thermal-hydraulic analysis. This study evaluates its heat transfer modeling capabilities by simulating the International...
Research on intelligent customization design technology for nuclear power unit systems
December 2025
Currently, nuclear power has been accepted by many countries as a safe and clean energy source. According to the nuclear power development policy, China will approve 6–8 units annually. The system of...
Study on pressure variation and its impact on the essential service water system of nuclear power plants
December 2025
The Essential Service Water (SEC) system of the CPR1000 unit serves as the ultimate heat sink for the nuclear island system of the power plant. Its distinctive redundant configuration (with standby...
Chemical speciation analysis of fission products in the PWR fuel pellet during accidents
December 2025
During the operation of a pressurized water reactor, large amounts of fission products (FP) are generated in the grains of fuel pellets. The transport behavior of different chemical species of fission...