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...
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...
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...
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...
Advanced nuclear power engine: A brief overview of gas core reactor for space exploration
June 2023
Space travel requires propulsion with high specific impulse. Gas core reactors using plasma nuclear fuel operate at high temperature (104-105K) and theoretically produce higher specific impulses (2500-7000s)...
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...
Review of spatial scale dispersion models (ATDMs) to simulate environmental dispersion and deposition of radionuclides and the overview of GIS coupling with dispersion models
December 2024
Estimation of the radiological consequences including the calculation of radiation doses to the exposed population requires numerical evaluation of atmospheric radioactive releases from nuclear facilities...
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....
Phenomena identification Ranking Table (PIRT) study for suppression containment of small modular reactor using new methodology
June 2023
The Phenomena Identification and Ranking Table (PIRT) is a significant method for analyzing the safety of nuclear reactors. It helps researchers identify important phenomena within the reactor, enabling...
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...
Conceptual design of a novel megawatt portable nuclear power system by supercritical carbon dioxide brayton cycle coupled with heat pipe cooled reactor
December 2023
In order to meet realistic requirements for flexible and reliable power supply in special scenarios such as remote areas and deep ocean exploration, a novel megawatt portable nuclear power system called...
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...
Analysis of explosion incidents in nuclear fuel reprocessing facilities and recommendations for their prevention
June 2024
Human society endeavors to harness nuclear energy for peaceful utilization, intertwining it with global strategies to address pressing issues such as energy demand, environmental preservation, and energy...
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,...
Thermal mechanical response analysis of the first wall in laser initial confinement fusion reactors
June 2025
This paper investigates the thermo-mechanical response characteristics of the first wall of a laser initial confinement fusion reactor under periodic transient heat flux loads. The first wall of the...
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 thermal and geometrical parameters of helical coil once-through steam generator system
2021
Due to the special structure, helical coil once-through steam generators (HCOTSGs) can withstand greater thermal expansion stress, have a larger heat exchange area, and cause the secondary flow phenomenon...
Steady-state thermal fluids analysis for the HTR-PM equilibrium core
2021
The high temperature gas-cooled reactor-pebble bed module (HTR-PM), designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, is a demonstration project of nuclear...
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...
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...
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...
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...
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...
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 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...