Experimental study on siphon break of pool reactor under various water levels
December 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...
Numerical investigation on the thermal-hydraulic performance of LFR fuel assemblies with multi-parameter wire wrap geometries
December 2026
Lead-cooled fast reactors (LFRs) represent a highly promising fourth-generation nuclear technology, characterized by low operating pressures, inherent safety, and compact core configurations. Within...
Opportunities and challenges in the application of high-temperature resistant yttrium hydride neutron moderators in microreactors
December 2026
Metal hydrides possess excellent neutron moderating power and favorable thermal conductivity, making them ideal high-temperature neutron moderator materials for micro-nuclear reactors. Zirconium hydride...
Preliminary thermodynamic design and optimization of a steam Rankine cycle for CFEDR
December 2026
The China Fusion Engineering Demo Reactor (CFEDR) serves as a vital bridge toward commercial fusion energy, necessitating a highly efficient Power Conversion System (PCS) to manage its multi-grade heat...
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...
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...
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...
Thermal-hydraulic characteristics of a high-efficiency zirconium heat exchanger: a multiscale CFD and porous-media study
Available online 16 September 2026
Compact heat exchangers require high heat-transfer capacity within a limited volume and acceptable hydraulic resistance. Zirconium alloys are attractive for selected nuclear-related components because...
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...
Study on the Influence of the Accelerating Structure on the Beam in a Compact High-Voltage High-Current Neutron Source
Available online 8 September 2026
This paper investigates the accelerating structure parameters of a compact high-voltage accelerator neutron source. A three-dimensional model of the acceleration system was established using SIMION....
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,...