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...
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)...
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...
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...
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...
Thermal hydraulic study of NuScale iPWR passive containment cooling behaviour during loss-of-coolant accident
June 2025
Operation of the NuScale emergency core cooling system (ECCS) was studied, with an emphasis on the crucial role of the containment vessel (CNV). Design parameters such as vessel volume were varied to...
Advanced UZrH research reactor design, part I: thermal-hydraulic review
June 2026
Uranium–Zirconium Hydride (UZrH) research reactor is a type of research reactor that uses UZrH fuel as its core fuel. This reactor type typically employs a pool-type coolant system design, offering...
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...
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...
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...
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...
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...
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...
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...
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...
Advancements in the research of high-temperature gas-cooled reactor fuel via additive manufacturing techniques
March 2024
Recent advances in high-temperature gas-cooled reactor fuel research have captured the global spotlight, as modern operating contexts demand innovative responses to unprecedented challenges. This article...
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...
Simulation study of steam flow behavior and piping mechanical response analysis in safety valve discharge pipes with fluid-structure interaction
September 2025
This study numerically simulates the steam flow behavior and piping mechanical response within the safety valve discharge piping of a nuclear power system. A one-way Fluid-Structure Interaction (FSI)...
Advanced UZrH Research Reactor design, Part II: coolant and irradiation loop systems
June 2026
The Uranium–Zirconium Hydride (UZrH) Research Reactor is a type of research reactor that utilizes UZrH fuel as its core fuel, providing irradiation services and generating neutron beams. Currently,...
Multiphysics study on phase separation and thermal aggregation effects in the melt pool of the reactor lower head under severe accidents
June 2026
In the progression of severe accidents in light water reactors, the retention of core melt in the reactor pressure vessel (RPV) lower head, known as In-Vessel Retention (IVR), constitutes a core strategy...
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...
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...
Heat transfer characteristics of two-layer corium pool with additional metallic layer heat source
June 2026
Due to material oxidation, activation, and the presence of fission products and uranium, the metallic layer in a two-layer corium pool contains internal heat sources. This study investigated the influence...
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...