Search Results - "BANERJEE, Joydipta"

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  1. 1

    Construction of master sintering curve of ThO2 pellets using optimization technique by Ray, A, Banerjee, J, Kutty, T R G, Kumar, A, Banerjee, S

    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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    Journal Article
  2. 2

    Nd3+-Y3Al5O12 system: Iso-valent substitution driven structural phase evolution and thermo-physical behavior by Bhandari, Koushik, Grover, V., Roy, Anushree, Sahu, Manjulata, Shukla, R., Banerjee, Joydipta

    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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    Journal Article
  3. 3

    Fuel clad chemical interaction of U-Mo fast reactor fuel by Chakraborty, Sibasis, Choudhuri, Gargi, Banerjee, Joydipta, Agarwal, Renu, Kumar, Arun

    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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    Journal Article
  4. 4

    Structural, microstructural and thermal analysis of U−(6-x)Zr−xNb alloys (x = 0, 2, 4, 6) by Kaity, Santu, Banerjee, Joydipta, Parida, S.C., Bhasin, Vivek

    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. 5

    Analysis of simulated high burnup nuclear fuel by laser induced breakdown spectroscopy by Singh, Manjeet, Sarkar, Arnab, Banerjee, Joydipta, Bhagat, R.K.

    “…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. 6

    Structural, microstructural and thermal analysis of U−(6-x)Zr−xMo alloys (x = 0, 2, 4, 6) by Kaity, Santu, Banerjee, Joydipta, Parida, S.C., Behere, P.G., Bhasin, Vivek

    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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    Journal Article
  7. 7

    Molar heat capacity of uranium-rich U−Zr−Nb and U−Zr−Mo alloys by Kaity, Santu, Banerjee, Joydipta, Parida, S.C., Behere, P.G., Bhasin, Vivek

    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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    Journal Article
  8. 8

    Studies on fuel-cladding chemical interaction between U−10 wt%Zr alloy and T91 steel by Kaity, Santu, Banerjee, Joydipta, Parida, S.C., Laik, Arijit, Basak, C.B., Bhasin, Vivek

    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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    Journal Article
  9. 9

    U-PuO^sub 2^, U-PuC, U-PuN cermet fuel for fast reactor by Mishra, Sudhir, Kaity, Santu, Banerjee, Joydipta, Nandi, Chiranjeet, Dey, GK, Khan, KB

    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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    Journal Article
  10. 10

    Studies on sintering kinetics of ThO2–UO2 pellets using master sintering curve approach by Banerjee, Joydipta, Ray, Aditi, Kumar, Arun, Banerjee, Srikumar

    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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    Journal Article
  11. 11

    ZrO2-NdO1.5 system: Investigations of phase relation and thermophysical properties by Nandi, Chiranjit, Jain, Dheeraj, Grover, V., Krishnan, K., Banerjee, Joydipta, Prakash, Amrit, Khan, K.B., Tyagi, A.K.

    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. 12
  13. 13

    U-PuO2, U-PuC, U-PuN cermet fuel for fast reactor by Mishra, Sudhir, Kaity, Santu, Banerjee, Joydipta, Nandi, Chiranjeet, Dey, G.K., Khan, K.B.

    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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    Journal Article
  14. 14

    (Y1-xNdx)3Zr5O14.5 solid solutions as inert matrices: Phase evolution, order-disorder dynamics and thermophysical behavior by Bhandari, Koushik, Grover, V., Roy, Anushree, Bhatt, Ranu, Banerjee, Joydipta, Tyagi, A.K.

    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. 15
  16. 16

    Trends of publications and patents on metallic fuel development for fast reactors by Banerjee, Joydipta, Prakasan, E. R., Kutty, T. R. G., Bhanumurthy, K.

    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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    Journal Article
  17. 17

    Microstructural and thermophysical properties of U―6 wt.%Zr alloy for fast reactor application by LAITY, Santu, BANERJEE, Joydipta, NAIR, M. R, RAVI, K, DASH, Smruti, KUTTY, T. R. G, KUMAR, Arun, SIGH, R. P

    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. 18

    Studies on sintering kinetics of ThO sub(2)-UO sub(2) pellets using master sintering curve approach by Banerjee, Joydipta, Ray, Aditi, Kumar, Arun, Banerjee, Srikumar

    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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    Journal Article
  19. 19

    Study of calcinations of ammonium diuranate at different temperatures by Manna, Subhankar, Karthik, Phani, Mukherjee, Abhishek, Banerjee, Joydipta, Roy, Saswati B., Joshi, Jyeshtharaj B.

    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. 20

    Thermophysical properties of U 2Mo intermetallic by Kutty, T.R.G., Dash, Smruti, Banerjee, Joydipta, Kaity, Santu, Kumar, Arun, Basak, C.B.

    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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