Search Results - "BANERJEE, Joydipta"
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Construction of master sintering curve of ThO2 pellets using optimization technique
Published in Science of sintering (2012)“…Sintering kinetics and densification behavior of pure ThO2 have been studied using high temperature dilatometer experiments at constant rate of heating…”
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2
Nd3+-Y3Al5O12 system: Iso-valent substitution driven structural phase evolution and thermo-physical behavior
Published in Journal of molecular structure (15-09-2022)“…•Y3-xNdxAl5O12 system studied to mimic substituted garnets for MA transmutation.•Synthesis route enabled stabilization of 33 mol% Nd3+ substituted garnet…”
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3
Fuel clad chemical interaction of U-Mo fast reactor fuel
Published in Journal of nuclear materials (01-04-2019)“…U-33 at.% Mo (16.8 wt.%) metallic fuel is a candidate material for metallic fuel Fast Reactor. One of the life-limiting factors of fast breeder reactor clad is…”
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4
Structural, microstructural and thermal analysis of U−(6-x)Zr−xNb alloys (x = 0, 2, 4, 6)
Published in Journal of nuclear materials (01-06-2018)“…Uranium-rich U–Zr–Nb alloy is considered as a good alternative fuel for fast reactors from the perspective of excellent dimensional stability and desired…”
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5
Analysis of simulated high burnup nuclear fuel by laser induced breakdown spectroscopy
Published in Spectrochimica acta. Part B: Atomic spectroscopy (01-06-2017)“…Advanced Heavy Water Reactor (AHWR) grade (Th-U)O2 fuel sample and Simulated High Burn-Up Nuclear Fuels (SIMFUEL) samples mimicking the 28 and 43GWd/Te…”
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6
Structural, microstructural and thermal analysis of U−(6-x)Zr−xMo alloys (x = 0, 2, 4, 6)
Published in Journal of nuclear materials (15-04-2020)“…Uranium rich U–Zr–Mo alloys are considered to be good alternative fuel for fast reactors due to their many favourable properties to achieve higher burnup…”
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7
Molar heat capacity of uranium-rich U−Zr−Nb and U−Zr−Mo alloys
Published in Journal of nuclear materials (01-12-2020)“…•Measurement of molar heat capacity of U−6(Zr+Nb) and U−6(Zr+Mo) alloys using DSC.•Molar heat capacity decreases with addition of 6wt% alloying element…”
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8
Studies on fuel-cladding chemical interaction between U−10 wt%Zr alloy and T91 steel
Published in Journal of nuclear materials (01-01-2019)“…The chemical interaction of U−Zr based fast reactor fuel with T91 grade steel cladding was investigated by employing DTA (differential thermal analysis),…”
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9
U-PuO^sub 2^, U-PuC, U-PuN cermet fuel for fast reactor
Published in Journal of nuclear materials (01-02-2018)“…Cermet fuel combines beneficial properties of both ceramic and metal and attracts global interest for research as a candidate fuel for nuclear reactors. In the…”
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10
Studies on sintering kinetics of ThO2–UO2 pellets using master sintering curve approach
Published in Journal of nuclear materials (01-11-2013)“…Three different compositions of thoria–urania pellets, namely, ThO2–4%UO2, ThO2–10%UO2 and ThO2–20%UO2 (all compositions are in wt% containing natural uranium)…”
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11
ZrO2-NdO1.5 system: Investigations of phase relation and thermophysical properties
Published in Materials & design (05-05-2017)“…Exploring the structural and thermophysical behaviour of Nd-Substituted ZrO2 is vital in context of matrices for minor actinide transmutation. Hence, phase…”
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12
ZrO 2 -NdO 1.5 system: Investigations of phase relation and thermophysical properties
Published in Materials & design (01-05-2017)Get full text
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13
U-PuO2, U-PuC, U-PuN cermet fuel for fast reactor
Published in Journal of nuclear materials (01-02-2018)“…Cermet fuel combines beneficial properties of both ceramic and metal and attracts global interest for research as a candidate fuel for nuclear reactors. In the…”
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14
(Y1-xNdx)3Zr5O14.5 solid solutions as inert matrices: Phase evolution, order-disorder dynamics and thermophysical behavior
Published in Materials today communications (01-06-2021)“…•(Y1-xNdx)3Zr5O14.5 system studied to mimic heavy-loaded minor actinides substituted zirconia.•About 60 mol% solubility of Nd3+ as analysed by XRD shows F-type…”
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15
Corrigendum to “U-PuO2, U-PuC, U-PuN cermet fuel for fast reactor” [J. Nucl. Mater. 499 (2018) 272–283]
Published in Journal of nuclear materials (15-12-2018)Get full text
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16
Trends of publications and patents on metallic fuel development for fast reactors
Published in Current science (Bangalore) (10-01-2016)“…Higher breeding ratio, high thermal conductivity, shorter doubling time and high plutonium production make metallic fuels a viable solution compared to…”
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17
Microstructural and thermophysical properties of U―6 wt.%Zr alloy for fast reactor application
Published in Journal of nuclear materials (01-08-2012)“…The microstructural and high temperature behavior of U-6 wt.%Zr alloy has been investigated in this study. U-6 wt.%Zr alloy sample for this study was prepared…”
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18
Studies on sintering kinetics of ThO sub(2)-UO sub(2) pellets using master sintering curve approach
Published in Journal of nuclear materials (01-01-2013)“…Three different compositions of thoria-urania pellets, namely, ThO sub(2)-4%UO sub(2), ThO sub(2)-10%U0 sub(2) and ThO sub(2)-20%UO sub(2) (all compositions…”
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19
Study of calcinations of ammonium diuranate at different temperatures
Published in Journal of nuclear materials (01-07-2012)“…Effect of calcination temperature has been studied on tap density, surface area, porosity, O/U ratio, morphology and crystal phases of uranium oxides. The…”
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20
Thermophysical properties of U 2Mo intermetallic
Published in Journal of nuclear materials (2012)“…► Fabrication of U 2Mo intermetallic. ► Characterization using XRD and SEM indicates the presence of only U 2Mo phase. ► The transformation of U 2Mo phase to…”
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