Titanium Carbide: Synthesis, Properties and Applications

Mhadhbi, Mohsen

doi:10.36937/ben.2021.002.001

Cited by 37 publications

(14 citation statements)

References 107 publications

(92 reference statements)

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“…In another case, the general requirement for FW material is low neutronic absorption of cross-section, so light materials tend to lead to a low neutron absorption in high incident energy by (n, c) reaction cross-section, as seen in Figure 4. Hydrogen gas produced of (n, p) reaction [33] will be as high as (n, p) cross-section reaction in nuclides. It is similar to the α-particle that can produce helium gas bubbles [34].…”

Section: First Wall Designmentioning

confidence: 99%

Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Maemunah

Su’ud

Waris

et al. 2022

Science and Technology of Nuclear Installations

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Neutronic analysis in the HCLL blanket module has been established, and the calculation was performed by the ITER team, including the first wall (FW). In this study, seven materials have been investigated for FW material by considering characteristics such as high neutron fluence capability, low degradation, under irradiation, and high compatibility for blanket material. A three-dimensional configuration simulated in MCNP5 program codes was performed to investigate the neutronic performance and radiation damage effect. Employing seven candidates are vanadium carbide (VC), titanium carbide (TiC), vanadium alloy (V-5Cr-5Ti), graphite (C), tungsten alloy (W-CuCrZr), ceramic alloy (SiC), and HT-9 to study optimization of FW materials configurated in the HCLL blanket module. This novelty study concludes that vanadium alloy (V-5Cr-5Ti) is becoming a promising material candidate. This alloy has the highest number of neutronic performing for 1.27 TBR and 1.26 in multiplication energy factor in all investigations. Meanwhile, the amount of atomic displacement, hydrogen, and helium production are around 22.31 appm, 765.55 appm, and 281.57 appm, respectively. Even though vanadium alloy has a reasonably high radiation damage effect, it is still tolerable compared to several thresholds of DPA. So, it is considered excellent material for FW. Nevertheless, this alloy can replace after 13.45 years for radiation damage.

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Section: First Wall Designmentioning

confidence: 99%

Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Maemunah

Su’ud

Waris

et al. 2022

Science and Technology of Nuclear Installations

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“…The most studied methods of titanium carbide nanopowders production are chemical vapor deposition, self-propagating high-temperature synthesis with laser ignition, sol-gel method, selfpropagating high-temperature synthesis, etc. [12][13][14][15][16]. All these methods are characterized by very low productivity and rather high cost of the final product.…”

Section: Introductionmentioning

confidence: 99%

Studies of Highly Dispersed Titanium Carbide Powder Obtained from Scrap Tungstenless Cemented Carbide Alloys

Gavrish

2022

Materials Research Proceedings

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Abstract. The results of research of characteristics of highly dispersed titanium carbide powder obtained from carbide waste of TN-20, TN-25, TN-30 types are presented. The powder particles were studied using analytical methods including scanning microscopy, X-ray diffraction, differential thermal analysis. The obtained results confirm the formation of nanosized particles of titanium carbide of monocrystalline form.

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“…Due to its exceptional qualities, including high hardness, high chemical stability, high melting point, strong resistance to abrasion, etc., titanium carbide (TiC) is a promising material that is frequently used for cutting tools [1]. In addition, TiC is employed in optics, electronics, and other fields.…”

Section: Introductionmentioning

confidence: 99%

Spark Plasma Sintering of Nanostructured TiCrC Carbides Prepared via Mechanical Alloying

Mhadhbi¹,

Dağ²,

Avar³

et al. 2022

Preprint

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In order to produce nanostructured Ti0.9Cr0.1C powders, an elemental powder mixture of titanium, chromium, and graphite is milled in this work using a high-energy ball mill for various milling times. Microstructural characteristics such as crystallite size, microstrain, lattice parameter, and dislocation density are determined using X-ray diffraction (XRD). Mechanical alloying successfully produced nanocrystalline (Ti,Cr)C with an average crystallite size of 11 nm. This size of the crystallites is also directly verified using transmission electron microscopy (TEM). Scanning electron microscopy (SEM) was used to investigate the morphology of the samples. The novelty of this work is advancing the scientific understanding of the effect of milling time on the particle size distribution and crystalline structure, and also understanding the effect of the spark plasma sintering on the different properties of the bulks. Densified cermet samples were produced from the nanocrystalline powders, milled for 5, 10 and 20 hours by SPS process at 1800 degrees for 5 min under a pressure of 80 MPa. Phase changes of the produced cermets were examined according to XRD, SEM/EDX analyses. Significant amounts of Cr and Fe elements were detected, especially in the 20 h milled cermet. The bulk forms of the milled powders for 5 and 20 h had a relative density of 98.43 and 98.51 %, respectively. However, 5 h milled cermet had 93.3 HRA because of the more homogeneous distribution of the (Ti,Cr)C phase, the low iron content and high relative density. According to the 0.0011 mm/year corrosion rate, and 371.68 kΩ*cm2 charge transfer resistance obtained from the potentiodynamic polarization and EIS tests, the 20 h cermet was the specimen with the highest corrosion resistance.

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Titanium Carbide: Synthesis, Properties and Applications

Cited by 37 publications

References 107 publications

Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Studies of Highly Dispersed Titanium Carbide Powder Obtained from Scrap Tungstenless Cemented Carbide Alloys

Spark Plasma Sintering of Nanostructured TiCrC Carbides Prepared via Mechanical Alloying

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