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ISSN: 2468-6050

Analysis of explosion incidents in nuclear fuel reprocessing facilities and recommendations for their prevention

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...

Advanced nuclear power engine: A brief overview of gas core reactor for space exploration

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)...

Development status of small modular fast reactors

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...

Conceptual design of a novel megawatt portable nuclear power system by supercritical carbon dioxide brayton cycle coupled with heat pipe cooled reactor

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...

Review of spatial scale dispersion models (ATDMs) to simulate environmental dispersion and deposition of radionuclides and the overview of GIS coupling with dispersion models

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...

Thermal hydraulic study of NuScale iPWR passive containment cooling behaviour during loss-of-coolant accident

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 manufacturing technologies for enhancing security in nuclear and radiological materials transport

Advanced manufacturing technologies have transformed various industries, including nuclear security areas such as nuclear and radiological transport. This review manuscript describes the intersection...

Advancements in the research of high-temperature gas-cooled reactor fuel via additive manufacturing techniques

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...

Hybrid burnable absorber design based on ATF and application in 24-month long cycle fuel management

In order to meet the requirement of reactivity control for 24-month long cycle, an optimization design of burnable absorber based on accident tolerant fuel (ATF) is carried out. The design of hybrid...

Ensuring safety in the Air transport of radioactive materials: Regulations, methodologies, and probabilistic safety assessment

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...

Research progress on irradiation damage of Molybdenum-Rhenium alloys

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 mechanical response analysis of the first wall in laser initial confinement fusion reactors

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...

Research on leakage characteristics of labyrinth seal of air turbine used for small mobile reactor

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...

Steady-state thermal fluids analysis for the HTR-PM equilibrium core

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...

Experimental study on gravity settling of aerosols inside the containment vessel of nuclear power plants

Gravity setting is an important factor in the natural removal of aerosols in the containment. In this text, it is carried out to the experimental study of aerosol gravity setting in the containment...

Reactivity safety analysis of an air-cooled nuclear thermal propulsion reactor

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...

Implementation of Leak Before Break (LBB) criteria in fast spectrum reactor

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...

Study on the thermal and geometrical parameters of helical coil once-through steam generator system

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...

Validation and sensitivity analysis of the FLEXPART model using the Kincaid experiment data

FLEXPART, a Lagrangian particle dispersion model, is widely used in atmospheric dispersion and nuclear emergency response studies. However, a systematic sensitivity analysis of this model is still lacking....

Phenomena identification Ranking Table (PIRT) study for suppression containment of small modular reactor using new methodology

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...

Back propagation neural network-based prediction of critical heat flux in vertical and inclined tubes

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...

Study on thermal hydraulic characters of corrugated plate dryer based on DPM coupled ELFM method

To improve the structures and characteristics of the steam generator corrugated plate dryer and increase the steam-liquid separation efficiency, the discrete phase model (DPM) coupled with the Eulerian...

Experimental study on flow characteristics of rectangular narrow channel

Plate fuel elements is gradually used in advanced reactor structure design because of its advantages of high fuel consumption and high safety. The flow channel of the plate fuel element is a typical...

24-Month long cycle fuel management research based on accident tolerant fuel

As the installed nuclear power plants steadily increase in China, the demand for 24-month long cycle fuel management is gradually increasing as well. 18-month refueling strategy is mainly applied in...

Thermo-mechanical modeling of residual stress and filler metal optimization for SiC cladding joints

This study employed the finite element modeling method to investigate the thermodynamic behavior of brazed joints between silicon carbide (SiC) clad tubes and five metal-based filled alloys (Ti, Ni,...

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