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)...
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...
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...
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...
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...
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...
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...
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...
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...
Ensuring safety in the Air transport of radioactive materials: Regulations, methodologies, and probabilistic safety assessment
June 2024
The paper is focused on comprehensive study on air transportation of radioactive materials, covering regulations and requirements, hazard identification and proposed a methodology to apply the Probabilistic...
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...
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...
Advanced manufacturing technologies for enhancing security in nuclear and radiological materials transport
September 2023
Advanced manufacturing technologies have transformed various industries, including nuclear security areas such as nuclear and radiological transport. This review manuscript describes the intersection...
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...
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...
Back propagation neural network-based prediction of critical heat flux in vertical and inclined tubes
March 2026
Due to their unique advantages, offshore floating nuclear power plants have broad application prospects. Unlike land-based reactors, it is essential to conduct in-depth research on the characteristics...
Research on leakage characteristics of labyrinth seal of air turbine used for small mobile reactor
December 2025
Brayton cycle has the characteristics of safety, high efficiency and compactness, which is the primary option for the energy conversion system of small mobile reactors. The performance of the turbine...
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...
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...
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)...
Numerical simulation of humidification process by spray evaporation under different air pressure and temperature
September 2025
In special industrial fields, when dry compressed air enters process fluids containing radioactive substances, it often carries radioactive water vapour. To effectively solve this problem, it is necessary...
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...
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...
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...