Anamul. H Mir

Anamul. H Mir
University of Huddersfield · Department of Engineering and Technology

Ph.D

About

49
Publications
6,702
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469
Citations
Citations since 2017
36 Research Items
437 Citations
2017201820192020202120222023020406080100
2017201820192020202120222023020406080100
2017201820192020202120222023020406080100
2017201820192020202120222023020406080100
Introduction
EPSRC early career research fellow working on corrosion and radiation damage in nuclear materials and anything that seems intriguing and stimulating........... such as radiation damage in Japanese Macha (for curiosity of course), corrosion in randomly collected beach glasses, rocks, pieces of glasses from parking lots, streets, etc . A lot of this research will never see the light of the day!

Publications

Publications (49)
Article
As borosilicate glasses are used in many countries to immobilize fission products and minor actinides after spent fuel reprocessing before storage in a deep geological repository, assessing their chemical durability is of paramount importance. Here pristine and pre‐irradiated (952MeV, 136Xe) SiO2‐B2O3‐Al2O3‐Na2O glasses with the same molar ratios a...
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Full-text available
Churchite-type REPO4·2H2O (RE = Gd to Lu & Y) materials are a metastable polymorph of the rare-earth phosphate family and adopts a 2D layered structure with the water molecules occupying the interlayer regions. The synthesis and structural properties of churchite materials are not well-studied in comparison to those of other polymorphs of the rare-...
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Once nanomaterials have been synthesized, inducing further structural modifications is challenging. However, being able to do so in a controlled manner is crucial. In this context, germanium nanowires are irradiated in situ within a transmission electron microscope (TEM) by a 300 keV xenon ion beam at temperatures ranging from room temperature (RT)...
Article
The stability of β-precipitates in the Zr-1Nb alloy has been studied under Ne ion irradiation of energy 250 keV by in-situ Transmission Electron Microscope (TEM) as a function of irradiation dose. The irradiation was carried out up to ~136 dpa at 573 K. Microstructural investigations have shown that up to ~38 dpa, precipitates showed an increase in...
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Different types of glass-ceramic composites are being researched around the world as potential matrices for nuclear waste conditioning. To demonstrate their long-term durability and build a safety case for geological disposal, accelerated irradiation tests simulating He accumulation and the effects of recoil nucleus damage are needed. To study the...
Article
In this work, germanium nanowires rendered fully amorphous via xenon ion irradiation have been annealed within a transmission electron microscope to induce crystallization. During annealing crystallites appeared in some nanowires whilst others remained fully amorphous. Remarkably, even when nucleation occurred, large sections of the nanowires remai...
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We have investigated the microstructural and crystallographic evolution of nanocrystalline zirconia under heavy ion irradiation using in-situ transmission electron microscopy (TEM) and have studied the atomic configurations of defect clusters using aberration-corrected scanning transmission electron microscopy (STEM). Under heavy ion irradiation th...
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Thin foils of AISI 316L stainless steel were irradiated in-situ in a transmission electron microscope (TEM) with 325 keV Xe ions at 550°C at three different fluxes to study flux effects. The kinetics of the radiation-enhanced precipitation (REP) and the evolution of the precipitates were found to be correlated with the irradiation flux. At lower fl...
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Near stoichiometric and under stochiometric Cr2AlxC (x=0.9 and 0.75) amorphous compositions were deposited onto silicon substrate at 330 K in a layer-by-layer fashion using magnetron sputtering from elemental targets. The film thickness found to be 0.9 µm and 1.2 µm for the near and under stoichiometric compositions respectively. A transmission Ele...
Article
Due to the complexities associated with handling and characterizing the radiation damage in radioactive materials such as nuclear waste forms, ion irradiation has been widely used to simulate the effects of the self-irradiation damage. This often involves ion irradiation of nuclear waste surrogate glasses using ion accelerators. Such facilities all...
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This work addresses the impact of radiation damage on the leaching of international simple glass (ISG). Pristine and specimens irradiated with multi-energy Au ions were leached for 82 days at 90 oC in pure water and pH 9 and regularly sampled. Samples leached for 13 and 58 days were characterized using transmission electron microscopy (TEM) to stud...
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Understanding the microstructural evolution of glasses during their interaction with water and radiation is of fundamental importance in addressing the corrosion of nuclear waste forms under geological disposal conditions. Here we report the results of more than 21 years of corrosion of two borosilicate glasses showing the formation of mesoporous C...
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Mineral and glass dissolution is a scientific topic deeply investigated but incompletely understood and of a great interest for the geochemical and materials science communities. If the interfacial dissolution/reprecipitation mechanism seems to be applicable to most of silicate minerals, the debate remains open concerning glass. Here we studied two...
Article
Thin foils of AISI 316L stainless steel were irradiated in-situ in a transmission electron microscope (TEM) with 325 keV Xe ions at 550 °C at three different fluxes to study flux effects. The kinetics of the radiation-enhanced precipitation (REP) and the evolution of the precipitates were found to be correlated with the irradiation flux. At lower f...
Article
The stability of the β-Nb Second Phase Particles (SPPs) in two types of Zr–Nb alloys (recrystallised Zr-1.0Nb and Zr-2.5Nb) was studied by in-situ heavy ion irradiation in a transmission electron microscope (TEM), combined with ex-situ analysis by energy dispersive x-ray spectroscopy (EDX). TEM thin foils were irradiated by 1 MeV Kr⁺ ions at four d...
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Full-text available
Direct Comparison of Tungsten Nanoparticles and Foils under Helium Irradiation at High Temperatures Studied via In-Situ Transmission Electron Microscopy - Volume 25 Supplement - E. Aradi, J. Lewis-Fell, R.W. Harrison, G. Greaves, A.H. Mir, S.E. Donnelly, J.A. Hinks
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In this work, ion irradiations in-situ of a transmission electron microscope are performed on single-crystal germanium specimens with either xenon, krypton, argon, neon or helium. Using analysis of selected area diffraction patterns and a custom implementation of the Stopping and Range of Ions in Matter (SRIM) within MATLAB (which allows both the 3...
Article
In this work, a detailed analysis of He, Ne, Ar, Kr and Xe precipitates in a complex borosilicate glass using transmission electron microscopy (TEM) with in-situ ion implantation is presented. With in-situ monitoring, the real-time dynamics of precipitate and void evolution under ion implantation was followed. Using appropriate equations of state a...
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Full-text available
In this work, a detailed analysis of He, Ne, Ar, Kr and Xe precipitates in a complex borosilicate glass using transmission electron microscopy (TEM) with in-situ ion implantation is presented. With in-situ monitoring, the real-time dynamics of precipitate and void evolution under ion implantation was followed. Using appropriate equations of state a...
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Full-text available
Radiation damage is a complex dynamic process with multiple atomic mechanisms interacting and competing to determine the end state of the material. Transmission electron microscopy (TEM) with in-situ ion irradiation allows direct observation of the microstructural evolution of a sample from the virgin to end state. A new TEM with in-situ ion irradi...
Article
This work explores the behaviour of xenon precipitates in amorphous silica using a transmission electron microscope with in-situ ion implantation. The specimens were first implanted at high-temperature to form equilibrium Xe precipitates which were then cooled to room temperature to form under- pressurized precipitates. In-situ implantation and real...
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Materials exposed to plasmas in magnetic confinement nuclear reactors will accumulate radiation-induced defects and energetically implanted gas atoms (from the plasma and transmutations), of which insoluble helium (He) is likely to be the most problematic. The large surface-area-to-volume ratio exhibited by nanoporous materials provides an unsatura...
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Abstract Estimates of noble gas solubility in glasses and minerals are important to understand the origin of these gases, particularly xenon, in the atmosphere. However, technical difficulties and ambiguities in quantifying the dissolved gases introduce large uncertainties in the solubility estimates. We present here the use of transmission electro...
Article
A three oxide sodium borosilicate (BS3) and a complex, thirty oxide borosilicate glass (SON68) were irradiated with 2.3 MeV electrons to doses ranging from 0.15 GGy to 4.6 GGy at 350 K. The irradiated glasses were characterized using Raman and NMR spectroscopies, ToF-SIMS, AFM and microhardness to understand surface and bulk irradiation effects. Gl...
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A number of studies have suggested that the irradiation behavior and damage processes occurring during sequential and simultaneous particle irradiations can significantly differ. Currently, there is no definite answer as to why and when such differences are seen. Additionally, the conventional multi-particle irradiation facilities cannot correctly...
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Safe management of high level nuclear waste is a worldwide significant issue for which vitrification has been selected by many countries. There exists a crucial need for improving our understanding of the ageing of the glass under irradiation. While external irradiation by ions provides a rapid simulation of damage induced by alpha decays, short li...
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Full-text available
A sodium borosilicate glass was irradiated sequentially and simultaneously with alpha particles and gold ions. Alpha particles induced partial recovery of the network damage and mechanical properties in the gold pre-irradiated glass, while no such recovery effect was observed during gold irradiation of the alpha pre-irradiated glass. The damage cap...

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Projects (4)
Project
Nuclear materials (fuels, conditioning matrices, structural materials) are subjected to complex irradiation aging scenarios with multiple particle irradiations and specific thermal history. So as to desing new materials, my main research work aims at understanding what are the main parameters that control the final damage state of a material under complex irradiation aging conditions.