Results 21 to 30 of about 10,588 (115)

Optimization of Debinding-sintering Processes and Densification Study on Fabricating Complex-shaped UO2-W Fuel via Powder Extrusion Printing

open access: yesYuanzineng kexue jishu
To meet the demands of future complex space missions, more advanced space propulsion systems are essential. Among these, nuclear thermal propulsion (NTP) systems offer high specific impulse, high thrust, and long operating times, making them an ideal ...
SHAO Zongyi1, 2, ZHAO Yumeng1, 2, XUN Yuxuan1, 2, ZHANG Zhengrong2, CAO Junwen1, 2, LIU Wei2, LIU Wentao2
doaj   +1 more source

Radiation release characterization of PWR spent fuel assemblies generated from Korean nuclear power plants [PDF]

open access: yesNuclear Technology and Radiation Protection, 2009
Spent nuclear fuel should be kept under safe management until it is disposed of permanently. Because of this, it is important to understand its radiation release characteristics.
Moon Hyun Joo
doaj   +1 more source

Enhancing Thermal Conductivity of SiC Matrix Pellets for Accident-Tolerant Fuel via Atomic Layer Deposition of Al2O3 Coating

open access: yesEnergies
This study investigates the enhancement of thermal conductivity in silicon carbide (SiC) matrix pellets for accident-tolerant fuels via atomic layer deposition (ALD) of alumina (Al2O3) coatings. Pressure-holding ALD protocols ensured precursor saturation,
Yumeng Zhao   +7 more
doaj   +1 more source

METHODS OF XS DATA PREPARATION FOR GEOMETRY WITH FUEL DUMMY

open access: yesActa Polytechnica CTU Proceedings, 2020
3D deterministic core calculation represents important category of the nuclear fuel cycle and safe Nuclear Power Plant operation. The appropriate solution was not published yet.
Pavel Suk
doaj   +1 more source

Improved Passive Gamma Emission Tomography image quality in the central region of spent nuclear fuel

open access: yesScientific Reports, 2022
Reliable non-destructive methods for verifying spent nuclear fuel are essential to draw credible nuclear safeguards conclusions from spent fuel. In Finland, spent fuel items are verified prior to the soon starting disposal in a geological repository with
Riina Virta   +5 more
doaj   +1 more source

Method for panoramic image stitching of nuclear fuel assembly based on key point detection network

open access: yesNuclear Engineering and Technology
This paper belongs to the technical field related to video image processing of nuclear fuel assemblies, and describes a panoramic stitching method for vertical motion videos of nuclear fuel assemblies.
Jinyuan Zhang
doaj   +1 more source

Structural integrity assessment and stress measurement of CHASNUPP-1 fuel assembly

open access: yesEPJ Nuclear Sciences & Technologies, 2016
Fuel assembly of the PWR nuclear power plant is a long and flexible structure. This study has been made in an attempt to find the structural integrity of the fuel assembly (FA) of Chashma Nuclear Power Plant-1 (CHASNUPP-1) at room temperature in air. The
Waseem   +3 more
doaj   +1 more source

In-air and in-water performance comparison of Passive Gamma Emission Tomography with activated Co-60 rods

open access: yesScientific Reports, 2023
A first-of-a-kind geological repository for spent nuclear fuel is being built in Finland and will soon start operations. To make sure all nuclear material stays in peaceful use, the fuel is measured with two complementary non-destructive methods to ...
Riina Virta   +5 more
doaj   +1 more source

Computational design and characterization of a subcritical reactor assembly with TRIGA fuel

open access: yesNuclear Engineering and Technology, 2019
The TRIGA fuel of the Philippine Research Reactor-1 (PRR-1) will be used in a subcritical reactor assembly (SRA) to strengthen and advance nuclear science and engineering expertise in the Philippines. SRA offers a versatile and safe training and research
Alvie Asuncion-Astronomo   +3 more
doaj   +1 more source

Geometric configuration of fuel assembly for small lightweight lead-bismuth reactor

open access: yesHe jishu, 2023
BackgroundThe neutronics and thermal-hydraulic characteristics of lead-bismuth cooled reactors are significantly affected by the geometric configuration of fuel assembly and lattice parameters.
WANG Chang   +5 more
doaj   +1 more source

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