Recent Articles

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ISSN: 2468-6050

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...

Research on temperature composite control system for radioactive waste incineration equipment

This paper presents a multi-mode control scheme for the temperature regulation of radioactive waste incineration equipment, integrating modern and fuzzy control theories. Separate controllers were designed...

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...

Vibration response simulation of centrifuge excited by liquid medium based on SPH-FEM

A coupled Smoothed Particle Hydrodynamics-Finite Element Method (SPH-FEM) framework is implemented to study flow-induced vibration problems of a decanter centrifuge drum under operational conditions....

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 fluid-structure interaction of spent fuel storage and transportation basket

The structural form of the spent fuel storage and transportation basket is different from that of the traditional rack, and the FSI parameters depend on the structural form. It is uncertain whether...

Design and research of an online continuous monitoring instrument for Iodine-129 in reprocessing facilities

This paper presents the design of an I-129 online continuous monitor based on the I-129 measurement scenario in the reprocessing plant, the characteristics of the NaI(Tl) crystal, the results of MCNP...

Research for radiological consequence analysis for extended design case of multiple SGTR accidents

In order to verify that the multiple heat transfer tubes rupture of steam generator (SGTR) in the third-generation passive nuclear power plants which use light water as coolant and moderator (TPLWNPPs)...

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...

Dynamic analysis of cold end accident conditions for a space gas-cooled reactor coupled with He–Xe brayton cycle system

Space nuclear power systems are promising for deep space missions. As the critical component of the space nuclear power system, radiators' performance significantly impacts both the cycle efficiency...

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...

Application of isomorphic remote manipulators with haptic feedback in the development of automatic analysis equipment for spent fuel reprocessing samples

Acid concentration and plutonium valence state in samples are crucial analytical parameters for process control during spent fuel reprocessing. Due to the high radioactivity and strong corrosiveness...

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...

Research and Application of Plutonium Inventory Monitoring System for solution systems

In order to monitor the plutonium inventory of the solution system, the “point model” equations originated from the nuclear safeguard for plutonium monitoring were improved to make it applicable to...

Experimental Research on Siphon Break Characteristics in Pool-type Reactor

In order to ensure that the core of a pool-type reactor is submerged after a loss of coolant accident, a siphon break pipeline needs to be designed to prevent the continuous loss of pool water due to...

Maintainable container loader with high repeatability positioning accuracy for use in hot cell

In the hot cell, the hermetically sealed transport container must be transferred across multiple workstations prior to placement into the storage well. The minimal clearance between the outer wall of...

A study on data analysis utilizing the K-edge absorption spectroscopy in mixed thorium and uranium solutions

X-ray absorption spectroscopy stands as a non-destructive assay technique commonly employed in nuclear fuel reprocessing plants to analyze the concentration of elements such as uranium, plutonium,thorium.The...

Research on applicability of containment test data for HPR1000 based on phenomena scaling

The volume of the nuclear power plant containment is huge, making it difficult to conduct equal-scale or large-scale thermal-hydraulic tests. Currently the test data mainly come from small-scale tests....

A general two-group constants estimator for 17x17 PWR assembly configurations using artificial neural networks

In this study, a preliminary general two-group constants predictor using artificial neural networks (ANNs) for pressurized water reactor (PWR) based assembly designs is established. Users can input...

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