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...
TURBULENT PRANDTL NUMBER ANALYSIS OF HELIUM-XENON GAS FLOW AND HEAT TRANSFER IN THE PARALLEL CHANNEL
Available online 19 March 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...
Data-Driven Excess Xe Reactivity Modeling in CANDU Nuclear Reactor using Machine Learning Methods
Available online 18 March 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
Available online 18 March 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...
Study on the Influence of Inclination Conditions on Flow Instability in Parallel Rectangular Channels under Natural Circulation Conditions
Available online 11 March 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,...
Development status of small modular fast reactors
Available online 26 February 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...
Research Progress on Irradiation Damage of Molybdenum-Rhenium Alloys
Available online 10 February 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...
Maintainable container loader with high repeatability positioning accuracy for use in hot cell
December 2025
In the hot cell, the hermetically sealed transport container must be transferred across multiple workstations prior to placement into the storage well. The minimal clearance between the outer wall of...
Experimental research on siphon break characteristics in pool-type reactor
December 2025
In order to ensure that the core of a pool-type reactor is submerged after a loss of coolant accident, a siphon break pipeline needs to be designed to prevent the continuous loss of pool water due to...
Research and application of plutonium inventory monitoring system for solution systems
December 2025
In order to monitor the plutonium inventory of the solution system, the “point model” equations originated from the nuclear safeguard for plutonium monitoring were improved to make it applicable to...
Study on the flow and heat transfer characteristics of Li4SiO4 pebble bed based on DEM-CFD coupling
December 2025
The blanket is a key component for producing tritium in fusion reactors. To ensure the blanket operates effectively and safely, it is crucial to maintain efficient heat transfer in the pebble bed. Furthermore,...
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...
Validation of the subchannel code LINDEN for void fraction simulation based on the NUPEC PWR tests (PSBT)
December 2025
Subchannel analysis code is one of the most important thermal-hydraulic analysis tools for nuclear reactor cores. A new subchannel analysis code for PWRs named LINDEN code has been developed by China...
Proposal of an online univariate monitoring algorithm for sensors in primary circuit of nuclear reactor based on sliding-window kernel density estimation and quantitative metrics
December 2025
The reliability and accuracy of safety-related sensors in the primary circuit of a nuclear reactor are crucial to ensure the safety and economic viability of power plants. In recent years, substantial...
Research on modeling and fuel performance assessing of silicon-modified ferritic-martensitic steel cladding in flowing lead–bismuth eutectic corrosion environment
December 2025
Lead-bismuth coolant corrosion causes thinning of stainless steel fuel rod cladding through oxidation, dissolution, and erosion effects, thereby weakens fuel rod mechanical performance and degrades...
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...
Implementation of Leak Before Break (LBB) criteria in fast spectrum reactor
December 2025
Sodium is employed as a coolant in the primary and secondary loops of fast reactors to transfer heat from the reactor and deliver it to the expander. However, handling sodium poses challenges and can...