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...
Study on the influence of the accelerating structure on the beam in a compact high-voltage high-current neutron source
December 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....
Thermal-hydraulic characteristics of a high-efficiency zirconium heat exchanger: a multiscale CFD and porous-media study
December 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...
Preliminary analysis on oxidation and embrittlement behavior at the burst region of zirconium alloy cladding
December 2026
In the event of a LOCA scenario, the fuel rod cladding experiences a progressive sequence of ballooning, burst and double-side oxidation. Ballooning and burst alter the geometric dimensions of the cladding,...
Deposition characteristics and filtration performance of inertial-impact aerosol filter units
December 2026
Inertial impact filters for small-reactor containment venting must balance high capture efficiency with low pressure drop. Reducing pore size or increasing the turning angle improves particle collection...
A study on deep learning-based methods for evaluating data quality in nuclear power plants
December 2026
To address the efficiency bottlenecks and lack of dimensions in nuclear power plant data quality assessment, this paper proposes a multidimensional data quality assessment method (referred to as the...
Flow and heat transfer characteristics and cooling-structure optimization of a fully radial-ventilated rotor in a 1000-MW nuclear turbine generator
December 2026
The turbine generator is the key energy-conversion equipment in the conventional islands of large nuclear power plants, and rotor cooling directly affects unit reliability. As unit capacity and rotor...
Research on power distribution reconstruction for small modular reactors based on PINN
December 2026
To address scarce training samples and lack of physical consistency in core power distribution reconstruction for small integrated pressurized water reactors, this study integrates forward high-fidelity...
Experimental study on hydraulic characteristics of the passive valves for the waste heat removal system of pool-type sodium-cooled fast reactor
December 2026
As the control module of the waste heat removal system, the passive valve is a key safeguard for the safe operation of pool-type sodium-cooled fast reactors. Passive valves rely on the rise and fall...
Numerical Study on the Closing Characteristics of a Passive Check Valve in the Decay Heat Removal System
Available online 31 October 2026
The passive check valve (PCV) is an important component of the passive Decay Heat Removal System (DHRS) in an integrated fast reactor, and it directly affects the decay heat removal capability of the...
ULCAR Framework for Unsupervised Audit of Expert Labels in Nuclear Reactor Operational Events
Available online 29 October 2026
Expert-defined fault labels for nuclear reactors may exhibit structural mismatches with intrinsic data distributions, reducing diagnostic robustness. This paper introduces the Unsupervised Label Consistency...
3D Fuel Performance Analysis Code Development and Application to Pellet Eccentricity Simulation
Available online 28 October 2026
With the development of advanced fuels characterized by complex structural designs and refined analysis requirements, traditional 1.5D fuel performance analysis codes are unable to meet the demands,...
Transient and Safety Analysis of a Small Lead-Bismuth Reactor Under Loss-of-Heat-Sink Accident
Available online 24 October 2026
Small modular lead-bismuth fast reactors offer advantages such as inherent passive safety, high power density, and long refueling cycles, yet their system-level dynamic response patterns and accident...
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...