Mechanical and Microstructural Study of Silicon Carbide and Pyrolytic Carbon Coatings in TRISO Fuel Particles

Mechanical and Microstructural Study of Silicon Carbide and Pyrolytic Carbon Coatings in TRISO Fuel Particles

Author: Huixing Zhang

Publisher:

Published: 2012

Total Pages:

ISBN-13:

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TRISO fuel particles have been developed as nuclear fuels used for a generation IV nuclear reactor: high temperature reactor. Such particle consists of a fuel kernel, pyrolytic carbon (PyC) and silicon carbide (SiC) coatings. This study has been carried out to establish a relationship between mechanical properties and microstructures of SiC coating and PyC coatings produced by fluidized bed chemical vapour deposition. Indentations were used to measure hardness, Young's modulus and fracture behaviour of SiC and PyC coatings. Fracture strength of SiC coatings was measured by crush test. Microstructure of SiC and PyC was mainly characterised by transmission/scanning electron microscopy and Raman spectroscopy. For SiC coatings produced at 1300 oC, Young's modulus is an exponential function of relative density. Hardness of SiC coatings is higher than the bulk SiC produced by CVD, and it is attributed to the high density of dislocations and their interactions. The deformation mechanism of SiC coatings under indentation is explained by presence of defects, such as grain boundaries and nano-pores. The fracture of these coatings beneath the Vickers indentation is the Palmqvist cracks, and indentation fracture toughness was in the range of 3.5-4.9 MPa m1/2. The stress-induced micro-cracks are assumed to be the mechanism for the high indentation fracture toughness. Different hardness and fracture toughness in these SiC coatings are attributed to influences of defects and grain morphology. Measurement of fracture strength was carried out on SiC coatings deposited at 1300-1500 oC. Weibull modulus and fracture strength of the full shell are dominated by the ratio of radius to thickness of coatings, and decrease linearly with the increase of this ratio. The influence of SiC/PyC interfacial roughness on fracture strength of the SiC was quantified by self-affine theory. The fracture strength decreases linearly with the increase of the roughness ratio, which is the long-wavelength roughness characteristic. After thermal treatment at 2000 oC, fracture strength decreased in SiC coatings due to the formation of pores, which are results of diffusion of native defects in as-deposited SiC coatings, and the change of Weibull modulus is related to the size and distribution of pores. For low density PyC coatings, Young's modulus and the mean pressure increase with the increase of the density; however, for high density PyC coatings, they are determined by interstitial defects. The hysteresis deformation behaviour under nano-indenation has been found be affected by density variation and thermal treatment, which is proposed to be due to the disorder structure in PyC coatings.


Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3

Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3

Author: Chengmin Liu

Publisher: Springer Nature

Published: 2023-05-09

Total Pages: 1260

ISBN-13: 9811988994

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This is the third in a series of three volumes of proceedings of the 23rd Pacific Basin Nuclear Conference (PBNC 2022) which was held by Chinese Nuclear Society. As one in the most important and influential conference series of nuclear science and technology, the 23rd PBNC was held in Beijing and Chengdu, China in 2022 with the theme “Nuclear Innovation for Zero-carbon Future”. For taking solid steps toward the goals of achieving peak carbon emissions and carbon neutrality, future-oriented nuclear energy should be developed in an innovative way for meeting global energy demands and coordinating the deployment mechanism. It brought together outstanding nuclear scientists and technical experts, senior industry executives, senior government officials and international energy organization leaders from all across the world. The proceedings highlight the latest scientific, technological and industrial advances in Nuclear Safety and Security, Operations and Maintenance, New Builds, Waste Management, Spent Fuel, Decommissioning, Supply Capability and Quality Management, Fuel Cycles, Digital Reactor and New Technology, Innovative Reactors and New Applications, Irradiation Effects, Public Acceptance and Education, Economics, Medical and Biological Applications, and also the student program that intends to raise students’ awareness in fully engaging in this career and keep them updated on the current situation and future trends. These proceedings are not only a good summary of the new developments nuclear science and technology, but also a useful guideline for the researchers, engineers and graduate students.


Effects of Deposition Conditions on the Properties of Pyrolytic Carbon Deposited in a Fluidized Bed

Effects of Deposition Conditions on the Properties of Pyrolytic Carbon Deposited in a Fluidized Bed

Author:

Publisher:

Published: 2005

Total Pages:

ISBN-13:

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The high-density, isotropic pyrolytic carbon layer beneath the silicon carbide (IPyC) plays a key role in the irradiation performance of coated particle fuel. The IPyC layer protects the kernel from reactions with chlorine during deposition of the SiC layer, provides structural support for the SiC layer, and protects the SiC from fission products and carbon monoxide. The process conditions used by the Germans to deposit the IPyC coating produced a highly isotropic, but somewhat permeable IPyC coating. The permeability of the IPyC coating was acceptable for use with the dense German UO2 kernels, but may not be suitable when coating UCO kernels. The UCO kernels are typically more porous and thus have a larger surface area than UO2 kernels. The lower density and the higher surface area of UCO kernels could make them more susceptible to attack by HCl gas during the silicon carbide (SiC) coating process, which could result in heavy metal dispersion into the buffer and IPyC coatings and a higher level of as-manufactured SiC defects. The relationship between IPyC deposition conditions, permeability, and anisotropy must be understood and the appropriate combination of anisotropy and permeability for particle fuel containing UCO kernels selected. A reference set of processing conditions have been determined from review of historical information and results of earlier coating experiments employing 350 and 500 {micro}m UO2 kernels. It was decided that a limited study would be conducted, in which only coating gas fraction (CGF) and temperature would be varied. Coatings would be deposited at different rates and with a range of microstructures. Thickness, density, porosity and anisotropy would be measured and permeability evaluated using a chlorine leach test. The results would be used to select the best IPyC coating conditions for use with the available natural enrichment uranium carbide/uranium oxide (NUCO) kernels. The response plots from the investigation of the deposition of pyrolytic carbon in a fluidized bed graphically depict the relationships between processing parameters and coating properties. The additional figures present optical, scanning electron microscopy, and other images to highlight microstructural details. For the study, only two parameters (factors), coating gas fraction and deposition temperature, were varied. The plots reveal obvious trends and links between factors and responses. The dominant relationships determined by this study for this range of coating conditions are: (1) rate is dependent upon coating gas fraction or in other terms, reactant concentration; (2) density is controlled by deposition temperature; (3) efficiency is influenced by both CGF and temperature; (4) anisotropy is affect by CGF and temperature, however, the relationship is more complex than for other properties; (5) permeability is dependent upon deposition temperature (thus density); and (6) open porosity is affect by CGF thus is influenced by coating rate. The response plots can be used as 'maps' for the deposition process and are thus valuable for selecting coating conditions necessary to produce desired combinations of properties. The information is useful in predicting the effects of changes to processing on properties and is beneficial in optimizing the process and product properties. Although the study was limited to only two parameters, the information provides a foundation from which other aspects of the coating process can be more easily investigated.


Advanced Ceramic Coatings and Interfaces V

Advanced Ceramic Coatings and Interfaces V

Author: Dongming Zhu

Publisher: John Wiley & Sons

Published: 2010-11-23

Total Pages: 204

ISBN-13: 0470943955

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The present volume contains sixteen contributed papers from the symposium, with topics including advanced coating processing, advanced coating for wear, corrosion, and oxidation resistance, and thermal and mechanical properties, highlighting the state-of-the-art ceramic coatings technologies for various critical engineering applications.


Comprehensive Nuclear Materials

Comprehensive Nuclear Materials

Author:

Publisher: Elsevier

Published: 2020-07-22

Total Pages: 4871

ISBN-13: 0081028660

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Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field