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ISSN: 2468-6050

Validation of the subchannel code LINDEN for void fraction simulation based on the NUPEC PWR tests (PSBT)

Subchannel analysis code is one of the most important thermal-hydraulic analysis tools for nuclear reactor cores. A new subchannel analysis code for PWRs named LINDEN code has been developed by China...

Proposal of an online univariate monitoring algorithm for sensors in primary circuit of nuclear reactor based on sliding-window kernel density estimation and quantitative metrics

The reliability and accuracy of safety-related sensors in the primary circuit of a nuclear reactor are crucial to ensure the safety and economic viability of power plants. In recent years, substantial...

Research on modeling and fuel performance assessing of silicon-modified ferritic-martensitic steel cladding in flowing lead–bismuth eutectic corrosion environment

Lead-bismuth coolant corrosion causes thinning of stainless steel fuel rod cladding through oxidation, dissolution, and erosion effects, thereby weakens fuel rod mechanical performance and degrades...

Study on pressure variation and its impact on the essential service water system of nuclear power plants

The Essential Service Water (SEC) system of the CPR1000 unit serves as the ultimate heat sink for the nuclear island system of the power plant. Its distinctive redundant configuration (with standby...

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...

Analysis on the influence law of the rotating reactor supporting roller load affected by manufacturing and installation errors

The supporting structure of the rotating wheel is an important component of a certain rotating reactor. In order to improve the safety strength of the rotating reactor, the support system adopts a statically...

Research on ventilation of nuclear facilities based on Modelica

Taking the ventilation system of a comprehensive experimental platform in the experimental base as the research, a multi-zone ventilation model was established based on Modelica, and ventilation simulation...

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...

Experimental investigation on the operational characteristics of a steam separator under marine conditions

In this study, a novel steam separator featuring a two-stage separation structure was evaluated for its performance in marine scenes. The operational characteristics of the separator were assessed under...

Effects of turbulent heat diffusion and viscosity on the simulation of turbulent mixing in autonomous PWR subchannel analysis software

In this paper the turbulent mixing models of several domestic autonomous PWR subchannel software under review by the national nuclear safety administration were evaluated and studied. Firstly, it is...

Chemical speciation analysis of fission products in the PWR fuel pellet during accidents

During the operation of a pressurized water reactor, large amounts of fission products (FP) are generated in the grains of fuel pellets. The transport behavior of different chemical species of fission...

Development and application of an engineering simulator for an integrated heating reactor

The integrated heating reactor is a novel design intended to meet diverse energy demands, including industrial steam supply, district heating, and seawater desalination. To address key challenges 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,...

Study on the direct measurement method for trace plutonium in samples from spent fuel reprocessing

To directly, rapidly, and accurately measure trace plutonium in reprocessing samples, two α scintillation counters were developed for the direct measurement of liquids and solids after source preparation....

Numerical simulation of humidification process by spray evaporation under different air pressure and temperature

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...

Study on the method of measuring the interface of radioactive liquid by air blowing

Aiming at the interfacial measurement method of radioactive liquids, we propose and validate a program to realize the interfacial measurement of radioactive liquids by using the air blowing method....

Research on container for high-level radioactive waste vitrification product

Product containers for high-level radioactive waste liquid vitrified glass are critical components for ensuring continuous and stable operation of vitrification plants. Given the substantial demand...

Research on skin dose assessment methods after severe accidents in nuclear power plants

In the event of a severe accident at the nuclear power plant, the radioactive plume can cause external immersion exposure and deposition exposure to the skin. The predominant code utilized for estimating...

Impact of revised RG 1.183 on source terms and radiological consequences of rod ejection accident for the HRP1000 reactor

This paper compares and analyzes the impact of the revised RG 1.183 on the source term and radioactive consequences of the rod ejection accident. The revision of RG 1.183 has resulted in changes to...

Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise

The fission products residing in the fuel rod void volume (plenum and pellet-to-cladding gap) are available for release upon cladding breach, and the fission products release fraction is a key parameter...

Vibration-absorbing design and comparing research on spent fuel transport cask

The safe transportation of spent fuel is an important part of the sustainable development of nuclear power industry, the research and independent design of spent fuel transport cask is particularly...

Study on the evolution and collection characteristics of droplet impact on a collector under space conditions

The Liquid Droplet Radiator (LDR) exhibits superior specific thermal radiation capacity, yet its performance is hindered by droplet splashing and subsequent loss during high-speed collisions with the...

Simulation study of steam flow behavior and piping mechanical response analysis in safety valve discharge pipes with fluid-structure interaction

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)...

Study on X-ray fluorescence measurement method for Fe content in secondary circuit sampling filter membranes of nuclear power plants

The measurement of iron (Fe) content in second-loop sampling filter membranes is critical for evaluating corrosion product deposition in pressurized water reactor (PWR) nuclear power plants. Traditional...

Effects of feedback color and icon shape on touch interaction performance under unstable conditions of floating nuclear power platforms

In floating nuclear power platforms (FNPPs), the main control interface will gradually transition from traditional physical control panels to highly integrated, intelligent touchscreens. Existing research...

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