Mohd Idzat Idris

Mohd Idzat Idris
Universiti Kebangsaan Malaysia | ukm · Departmen of Applied Physics

Doctor of Engineering

About

18
Publications
3,742
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76
Citations
Citations since 2017
14 Research Items
71 Citations
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2017201820192020202120222023051015
Introduction
Mohd Idzat Idris currently works at the School of Applied Physics, National University of Malaysia. Mohd does research in Nuclear Engineering. Their most recent publication is 'Recovery behavior of SiC f /SiC composites by post-irradiation annealing up to of 1673 K'.

Publications

Publications (18)
Preprint
Full-text available
This paper documented the synthesis of cellulose nanocrystals (CNCs) extracted from commercially-sourced microcrystalline cellulose (MCC) via acid hydrolysis and the subsequent characterization analyses of the yield. The hydrolysis process was completed using 64% sulphuric acid at 45°C for 1 hour. The yield of (CNCs) exhibited prominent physicochem...
Preprint
Full-text available
This paper documented the synthesis of cellulose nanocrystalline (CNCs) extracted from commercially-sourced microcrystalline cellulose (MCC) via acid hydrolysis and the subsequent characterization analyses of the yield. The hydrolysis process was completed using 64% sulphuric acid at 45°C for 1 hour. The yield exhibited prominent physicochemical pr...
Article
Microstructures of monolithic high purity SiC and SiC with sintering additives after neutron irradiation to a fluence of 2.0–2.5 × 10²⁴ n/m² (E > 0.1 MeV) at 333–363 K and after post-irradiation annealing up to 1673 K were observed using a transmission electron microscopy. Results showed that no black spot defects or dislocation loops in SiC grains...
Preprint
Full-text available
15 This study involves a comprehensive analysis of 226 Ra, 232 Th, and 40 K concentration 16 from irrigation water samples. Water samples were obtained, and the physical 17 parameters were examined. Subsequently, the corresponding radiological risks to human 18 health were estimated. The concentration levels of 226 Ra, 232 Th, and 40 K in water 19...
Article
Full-text available
Clay is one of the most important industrial minerals that have been used to improve the quality of product and economize the production cost. Clay and their minerals, both in its natural and modified forms, have the ability to absorb various radioactive materials from aqueous solution, such as Uranium, Thorium and Caesium as discussed extensively...
Article
This study elucidates a gamma irradiation-reduction approach in producing small gadolinium nanoparticles specifically gadolinium oxide nanoparticles coated with chitosan (GdNPs-Cs). Chitosan was used as a natural stabilizer and coating agent, whereas gadolinium (III) chloride hexahydrate (GdCl3.6H2O) was used as a precursor. The gadolinium nanopart...
Article
Full-text available
In recent years, the importance of actinide element mobile fractions in risk assessment evaluation of contaminated sites has increased. The knowledge of the sorption kinetics of ²³⁸ U and ²³² Th and the thermodynamics behind the sorption process on radioactive waste is important to understand their mobility. In this study, the leaching process of ²...
Article
Full-text available
The only factory that currently processes ilmenite to produce synthetic rutile is Tor Minerals in Ipoh, Perak, Malaysia. These two minerals contain radioactive elements such as uranium and thorium. Furthermore, this factory was built close to the residential areas. Thus, the primary issues are radiation exposure attributed to the decay of the radio...
Conference Paper
Full-text available
Raw kaolin from Kota Tinggi, Johor, Malaysia and local industrial grade barite (BaSO4) were used in this study to produce a ceramic mullite (3Al2O22SiO2) for radiation shielding materials. In this work, an attempt is made to study the potential of local minerals to be used as a shielding barrier for diagnostic radiology facilities in hospitals and...
Article
Full-text available
Silicon carbide fiber-reinforced silicon carbide composite (SiCf/SiC) has been proposed as a satisfied material to accommodate an extreme and corrosive irradiation ambience such as first wall of fusion reactors. Chemical Vapor Infiltration (CVI) and Electrophoretic Deposition (EPD) are the processes those have been conducted in order to fabricate t...
Article
Full-text available
SiC fiber-reinforced SiC matrix composites (SiCf/SiC) are considered as one of the candidates for blanket materials in future fusion reactors and as an advanced fuel cladding material for next-generation fission reactors. Generally, the densification of SiC needs sintering additives and oxides such as Al2O3, Y2O3, and yttrium-aluminum garnet (YAG,...
Article
Full-text available
Numerous studies on the recovery behavior of neutron-irradiated high-purity SiC have shown that most of the defects present in it are annihilated by post-irradiation annealing, if the neutron fluence is less than 1×1026 n/m2 (>0.1MeV) and the irradiation is performed at temperatures lower than 973K. However, the recovery behavior of SiC fabricated...
Article
Full-text available
Silicon carbide (SiC) is used as a layer in TRISO fuel of high temperature gas-cooled reactors because of its excellent thermal and mechanical properties. SiC fiber-reinforced SiC composites (SiCf/SiC) are also a candidate material for structural material for fusion reactor blanket and cladding materials of advance fission reactors. In this researc...
Article
Full-text available
Silicon carbide fiber-reinforced silicon carbide matrix composites (SiCf/SiC) are considered as one of the candidates for blanket materials in future fusion reactors. Generally, densification of SiC needs sintering additives due to the covalent nature of Si-C bonding, and sintering additives such as Al2O3, Y2O3, and YAG are frequently added to SiC....

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Projects

Projects (2)
Project
to study the correlation between physicochemical properties of irrigation with radionuclide concentration.