• Journal of Korea Foundry Society
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• v.43 no.2
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• pp.88-91
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• 2023

• Bulletin of the Korean Chemical Society
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• v.19 no.10
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• pp.1113-1116
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• 1998

A new graphite intercalation compound (GIC), n-octylammonium tetrachlorofeffate(Ⅲ)-graphite, has been derived from well-known ferric chloride graphite intercalation compound. X-ray diffration study shows that the basal spacing of this new GIC is 20.8 Å. In order to investigate the local geometry around the iron atom in the graphite layers, X-ray absorption spectroscopy experiments were performed. The first discharge capacity of its exfoliated form is found to be 862 mAh/g, which is more than double the value of pristine graphite (384 mAh/g). Such a drastic increase implies that the exfoliated graphite is a promising electrode material.

• Bulletin of the Korean Chemical Society
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• v.29 no.6
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• pp.1121-1124
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• 2008

A carbon composite was synthesized by mechanical mixing of ball-milled graphite and PVC powders, followed by pyrolysis reaction of PVC. Natural graphite ball milled under atmosphere of argon or air leads to a disordered structure. It appears that the electrochemical lithium intercalation reaction is dependent on the atmosphere in which the graphite is ball milled. The carbon composite obtained using air-milled graphite shows a high reversible capacity and high initial coulombic efficiency compared to argon-milled graphite. This is attributed to the enhanced thermal stability of a disordered structure in the air milled sample. For the one with air-milled graphite, the disordered structure is maintained during heat treatment, while argon-milled graphite is partially crystallized.

• Journal of the Korean Society of Manufacturing Process Engineers
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• v.11 no.1
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• pp.82-87
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• 2012

For different ferrite-pearlite matrix structure, contain more than 90% spheroidal ratio of graphite, GCD 45-3, GCD 50, GCD 60 series and 70%, 80%, 90% spheroidal ratio of graphite, GCD 40, GCD 45-1, GCD 45-2 series, this paper has carried out rotary bending fatigue test, estimated maximum and mean size of spheroidal graphite, investigated correlation. It was concluded as follows. (1) Fatigue limit in $10^7$cycles and numbers of spheroidal graphite per 1$mm^2$ was linear relation. (2) projection area of graphite can be used to predict fatigue limit of Ductile Cast Iron. The Statistical distribution of extreme values of projection area of defects may be used as a guideline for the control of inclusion size in the steelmaking processes.

• Journal of Korea Foundry Society
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• v.7 no.1
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• pp.38-44
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• 1987

The spiral fluidity of graphite-dispersed Al-Si alloys has been investigated as a function of contents of Si and graphite, and of particle size of graphite. The dispersion of uncoated graphite is carred out by the vortex process of preheat-treated graphite into molten metal. The fluidity of hyper-eutectic Al-Si alloys is observed to the better than that of hypo-eutectic ones. In the case of graphite-dispersed Al-Si alloys they fluidity increases in hypo-eutectic alloys and decreases in hyper-eutectic ones in comparison with that of the corresponding undispersed alloys. Fluidity decreases with an increase of amount of dispersed graphite particles and inversely proportional to the total surface area of graphite particles.

• Proceedings of the Korean Vacuum Society Conference
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• 2012.02a
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• pp.555-555
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• 2012

The thermal stability of poly(sodium 4-styrenesulfonate) intercalated graphite oxide has been investigated using a differential scanning calorimeter. The poly(sodium 4-styrenesulfonate) intercalated graphite oxide composite shows a prominent exothermic reaction near $207^{\circ}C$ and an endothermic reaction near $453^{\circ}C$. Graphite oxide is responsible for the exothermic reaction while the endothermic reaction is caused by the poly(sodium 4-styrenesulfonate) used in the synthesis of poly(sodium 4-styrenesulfonate) intercalated graphite oxide. The onset temperature of the exothermic reaction of poly(sodium 4-styrenesulfonate) intercalated graphite oxide decreased by $92^{\circ}C$ in comparison with that of graphite oxide, indicating the addition of poly(sodium 4-styrenesulfonate) in the composite has diminished the thermal stability of graphite oxide.

• Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference
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• 2000.11a
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• pp.318-331
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• 2000

Electrical and tribological behaviours of a copper-graphite brush in a slipring-brush assembly were investigated to evaluate the characteristics of electric signal transmission between a slipring and a brush. Five brush materials containing different amounts of copper and graphite were studied. The result showed that a copper-graphite brush at a particular graphite content exhibited the most stable frictional and electrical behaviour suggesting an optimum amount of a solid lubricant in a metal-graphite brush system. Microscopic observation and the surface analysis showed good agreements with this phenomena. In addition, the deviation of the friction coefficient and electric signal distortion has a close relationship with a microscopic mechanical vibration and the change of a real contact area.

• Journal of the Korean Ceramic Society
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• v.22 no.6
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• pp.5-8
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• 1985

Graphite has been oxidized to graphite hydrogen sulfate in concentrated $H_2SO_4$. Anodic oxidation and chemical oxidation of graphite in $H_2SO_4$ generally leads to the formation of intercalation compounds of the ionic salt type through incorporation of $H_2SO_4^-$ions and $H_2SO_4$ molecules into the graphite. Several other reactions also accur at various points of the charging cycle. But there is no satisfactory kinetics and mechanism of intercalationin graphite. We have studied them with anodic oxidation and chemical oxidation. We found six distinct phenomena between 2nd stage and 1st stage in chemical oxidation. We examined them in detail by the following in the measurements electrical oxidation. X-ray diffractions UV-Vis spectroscopy density measurements. We could obtained a equation for kinetic according to the reaction rate from this results and mechanism of intercalation between 2nd stage and 1st stage with hydrogen sulfate in graphite. Three thesis were written for the mechanism of intercalation compounds in graphite with hydrogen sulfate ; first thesis is anodic oxidation second thesis is chemical oxidation and definition of transit phase between 2nd etc the third thesis is the kinetic mechanism of intercalation compounds in graphite with Hydrogen sulfate. This thesis is the first paper among three thesis as anodic oxidation.

• Journal of the Korean Ceramic Society
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• v.34 no.5
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• pp.443-448
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• 1997

Titanium carbonitride (Ti(CxN1-x)) ceramics were prepared by hot pressing of the mixture of TiN and graphite. Hot pressing was performed in a graphite mold at 198$0^{\circ}C$ for 40 min under 44 MPa in N2 atmosphere. The effect of graphite addition on sinterability and the mechanical properties of titanium carbonitride were investigated. In this study, the solubility limit of graphite in Ti(CxN1-x) was slightly below 10 wt% based on the results of XRD analysis. Within the solubility limit, graphite dissolved completely into titanium nitride and formed the single phase Ti(CxN1-x) solid solution. Peak relative density of 99% and hardness of 16 GPa were observed for Ti(CxN1-x) ceramics with 7 wt% graphite while maximum flexural strength of 500 MPa and fracture toughness of 4.0 MPa.m1/2 were observed for Ti(CxN1-x) ceramics with 10 wt% graphite. The electrical resistivities of the ceramics with 7 wt% and 10 wt% graphite were observed 40 {{{{ mu OMEGA }}cm and 50 {{{{ mu OMEGA }}cm respectively.

• Nuclear Engineering and Technology
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• v.49 no.5
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• pp.1010-1018
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• 2017

The European Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste project sought to develop best practices in the retrieval, treatment, and disposal of irradiated graphite including other irradiated carbonaceous waste such as structural material made of graphite, nongraphitized carbon bricks, and fuel coatings. Emphasis was given on legacy irradiated graphite, as this represents a significant inventory in respective national waste management programs. This paper provides an overview of the characteristics of graphite irradiated during its use, primarily as a moderator material, within nuclear reactors. It describes the potential techniques applicable to the retrieval, treatment, recycling/reuse, and disposal of these graphite wastes. Considering the lifecycle of nuclear graphite, from manufacture to final disposal, a number of waste management options have been developed. These options consider the techniques and technologies required to address each stage of the lifecycle, such as segregation, treatment, recycle, and ultimate disposal in a radioactive waste repository, providing a toolbox to aid operators and regulators to determine the most appropriate management strategy. It is noted that national waste management programs currently have, or are in the process of developing, respective approaches to irradiated graphite management. The output of the Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste project is intended to aid these considerations, rather than dictate them.