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ISSN: 2468-6050

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)...

Study on prediction model of nitrogen oxide concentration in reprocessing plant based on random forest

During the spent fuel reprocessing process, nitrogen oxides (NOx) gases are generated. The treatment and emission control of NOx rely on measurements from instrumentation. In situations where operating...

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...

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...

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...

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...

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...

A comparative neutronic analysis of U–Th fuels as potential alternatives to traditional UO2 fuel for enhanced performance and safety in the ACP-100 SMR

This study examines U–Th-based alternative fuel options for the ACP-100 reactor core through a neutronic lens. Neutronic simulations were performed utilizing the Monte Carlo SERPENT code for 540 EFPDs....

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...

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....

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....

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...

Multi-objective optimization of 200 kW air centripetal turbine based on artificial neural networks

The air-Brayton cycle has the characteristics of safety and high efficiency, which can be used as an energy conversion system for mobile small reactors. The air turbine is one of the key components...

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...

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...

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...

Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code

In this research, a conceptual approach is presented to obtain the neutron flux at a reactor core. A simple spherical reactor core was analyzed by a mathematical model defined by Delphi programming...

Research on fault diagnosis method for nuclear power plants rotating machinery based on MoCo Siamese neural network

Rotating machinery is a kind of significant equipment that widely used in nuclear power plants (NPPs). The harsh operating environment and long-term continuous operation of the rotating machinery can...

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...

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...

Experimental progress of 209Bi(n,G)210gBi cross-section measurement based on polonium self-deposition technique

Lead bismuth eutectic alloy (LBE:44.5 wt%Pb+55.5 wt%Bi) is an important coolant candidate for fourth-generation reactors due to its good physical and chemical properties. However, the risk of radioactive...

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...

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...

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...

Performance of sodium cooled traveling wave reactor core with axial fuel shuffling strategy

A prototype sodium cooled traveling wave reactor core with axial fuel shuffling, consist of an ignition and breeding region, was designed in this paper. Neutronic and depletion calculation was performed...

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