Multiphysics modeling of heat and solute transport in CRUD using two-phase film boiling approach
September 2026
Chalk River Unidentified Deposits (CRUD) on nuclear fuel cladding present persistent challenges in pressurized water reactors (PWRs), including cladding corrosion, elevated radiation fields, and CRUD-induced...
Study on the temperature characteristics of the primary side of the casing type once-through steam generator under single parameter transient conditions
September 2026
This study investigates the influence mechanisms of primary-side inlet temperature and flow rate on the axial temperature distribution of heat transfer tubes under transient conditions, based on a single-channel...
Research on the natural circulation capability and heat transfer capacity of the new separated water tank for the passive containment cooling system and secondary passive residual heat removal system
September 2026
Passive Containment Cooling System (PCS) and the Secondary Passive Residual Heat Removal System (PRS) are two major passive systems that ensure the safety of nuclear power plants under accident conditions....
A real-time digital twin simulation platform for the AHPR1000 safety system test facility
September 2026
To address the high risk of high-temperature and high-pressure physical testing, the long testing cycle, and the low efficiency of control logic integration in integrated safety system tests for advanced...
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...
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
Available online 19 August 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...
Research on Verification Benchmarks for Reactor Thermal-Hydraulic System analysis software
Available online 10 August 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...
Experimental study on Siphon break of pool reactor under various water levels
Available online 1 July 2026
To prevent core exposure in pool reactor following the coolant inventory reduction due to the siphon effect, it is necessary to keep the pool coolant inventory by designing a siphon-breaking method...
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...