Search Results - "Kamath, H.S."
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1
Densification strain rate in sintering of Tho2 and ThO2-0.25% Nb2O5 pellets
Published in Science of sintering (01-01-2009)“…The densification behavior of ThO2 and ThO2 containing 0.25%Nb2O5 powder compacts was studied with the help of a high temperature push-rod type dilatometer…”
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2
Determination of activation energy of sintering of ThO2-U3O8 pellets using the master sintering curve approach
Published in Science of sintering (01-01-2003)“…ThO2 containing around 2 to 3 % U233O2 is considered as fuel for the forthcoming Indian Advanced Heavy Water Reactor (AHWR). High-density ThO2-UO2 pellets have…”
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3
Phase transformation of metastable cubic γ-phase in U–Mo alloys
Published in Journal of alloys and compounds (10-09-2010)“…Over the past decade considerable efforts have been put by many fuel designers to develop low enriched uranium (LEU < 20%U 235) base U–Mo alloy as a potential…”
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4
An evaluation of the properties of As-cast U-rich U–Zr alloys
Published in Journal of alloys and compounds (08-07-2009)“…The present study involves evaluation of some basic properties of as-cast uranium rich U–Zr alloys, i.e. uranium alloys containing 2 wt%, 5 wt%, 7 wt% and 10…”
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5
Development of a master sintering curve for ThO2
Published in Journal of nuclear materials (01-05-2004)Get full text
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6
Classical molecular dynamics simulation of UO2 to predict thermophysical properties
Published in Journal of alloys and compounds (06-10-2003)Get full text
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7
Effect of molybdenum addition on metastability of cubic γ-uranium
Published in Journal of alloys and compounds (18-02-2010)“…Over the years U 3Si 2 compound dispersed in aluminium matrix has been used successfully as the potential low enriched uranium (LEU < 20%U 235) base dispersion…”
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Densification behaviour and sintering kinetics of ThO 2–4%UO 2 pellet
Published in Journal of nuclear materials (2011)“…ThO 2–⩽4% 233UO 2 fuel will be the driver fuel for the forthcoming Advanced Heavy Water Reactor (AHWR) in India. Densification behaviour such as shrinkage and…”
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9
Densification behaviour and sintering kinetics of ThO2-4%UO2 pellet
Published in Journal of nuclear materials (31-01-2011)Get full text
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10
Phase transformations in U–2 wt% Zr alloy
Published in Journal of alloys and compounds (05-03-2009)“…Phase transformation studies of uranium–2 wt% zirconium alloy have been carried out using optical microscopy, SEM with EDS, XRD and dilatometer as analytical…”
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11
Development of Impregnated Agglomerate Pelletization (IAP) process for fabrication of (Th,U)O 2 mixed oxide pellets
Published in Journal of nuclear materials (2012)“…► A new fabrication technique Impregnated Agglomerate Pelletization (IAP) has been developed for making (Th,U)O 2 pellets. ► Useful technique for fabrication…”
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12
CO 2 laser assisted removal of UO 2 and ThO 2 particulates from metal surface
Published in Applied surface science (01-06-2011)“…► Pulsed laser irradiation can remove radioactive particulates from metal surface. ► Adhesion of ThO 2 particulates are more than UO 2 particulates. ►…”
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13
Determination of alkali, alkaline earth and transition metal ions in U[O.sub.2] Th[O.sub.2] powders and sintered [O.sub.2] pellets by ion chromatography
Published in Journal of radioanalytical and nuclear chemistry (01-05-2010)“…An ion chromatographic method has been developed for the determination of traces of [Li.sup.+], [Na.sup.+], [K.sup.+], [Ca.sup.2+], [Mg.sup.2+], [Sr.sup.2+],…”
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14
Thermal expansion of simulated thoria–urania fuel by high temperature XRD
Published in Journal of nuclear materials (01-03-2012)“…The thermal expansion behavior of polycrystalline samples of ThO2–3.45% UO2 and SIMFUEL corresponding to burn-up of 43,000MWd/Te has been investigated from…”
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15
Creep behaviour of δ-phase of U–Zr system by impression creep technique
Published in Journal of nuclear materials (2011)“…In this study, the impression creep behaviour of δ-phase of U–50 wt.% Zr (U–72.29 at.% Zr) system was studied in the temperature range 525–575 °C at different…”
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16
Non destructive determination of PuO 2 content in MOX fuel pins for fast reactors using Passive Gamma Scanning
Published in Journal of nuclear materials (2010)“…Use of Passive Gamma Scanning for non destructive evaluation of PuO 2 content in mixed oxide (MOX) fuels for fast reactors is demonstrated. Experiments have…”
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17
Non destructive determination of PuO2 content in MOX fuel pins for fast reactors using Passive Gamma Scanning
Published in Journal of nuclear materials (01-04-2010)Get full text
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18
Investigation on the martensitic transformation and the associated intermediate phase in U–2wt%Zr alloy
Published in Journal of nuclear materials (01-08-2009)Get full text
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19
Characterization of (Th,U)O 2 fuel pellets made by impregnation technique
Published in Journal of nuclear materials (29-02-2008)“…Impregnation technique is an attractive alternative for manufacturing highly radiotoxic 233U bearing thoria based mixed oxide fuel pellets, which are remotely…”
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20
Phase transformations in U–2wt%Zr alloy
Published in Journal of alloys and compounds (01-03-2009)Get full text
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