Search Results - "Kamath, H.S."

Refine Results
  1. 1

    Densification strain rate in sintering of Tho2 and ThO2-0.25% Nb2O5 pellets by Kutty, T.R.G., Khan, K.B., Kumar, A., Kamath, H.S.

    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…”
    Get full text
    Journal Article
  2. 2

    Determination of activation energy of sintering of ThO2-U3O8 pellets using the master sintering curve approach by Kutty, T.R.G., Khan, K.B., Hegde, P.V., Sengupta, A.K., Majumdar, S., Kamath, H.S.

    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…”
    Get full text
    Journal Article
  3. 3

    Phase transformation of metastable cubic γ-phase in U–Mo alloys by Sinha, V.P., Hegde, P.V., Prasad, G.J., Dey, G.K., Kamath, H.S.

    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…”
    Get full text
    Journal Article
  4. 4

    An evaluation of the properties of As-cast U-rich U–Zr alloys by Basak, Chandrabhanu, Prasad, G.J., Kamath, H.S., Prabhu, N.

    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…”
    Get full text
    Journal Article
  5. 5
  6. 6
  7. 7

    Effect of molybdenum addition on metastability of cubic γ-uranium by Sinha, V.P., Hegde, P.V., Prasad, G.J., Dey, G.K., Kamath, H.S.

    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…”
    Get full text
    Journal Article
  8. 8

    Densification behaviour and sintering kinetics of ThO 2–4%UO 2 pellet by Banerjee, Joydipta, Kutty, T.R.G., Kumar, Arun, Kamath, H.S., Banerjee, Srikumar

    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…”
    Get full text
    Journal Article
  9. 9
  10. 10

    Phase transformations in U–2 wt% Zr alloy by Basak, Chandra Bhanu, Keswani, R., Prasad, G.J., Kamath, H.S., Prabhu, N.

    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…”
    Get full text
    Journal Article
  11. 11

    Development of Impregnated Agglomerate Pelletization (IAP) process for fabrication of (Th,U)O 2 mixed oxide pellets by Khot, P.M., Nehete, Y.G., Fulzele, A.K., Baghra, Chetan, Mishra, A.K., Afzal, Mohd, Panakkal, J.P., Kamath, H.S.

    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…”
    Get full text
    Journal Article
  12. 12

    CO 2 laser assisted removal of UO 2 and ThO 2 particulates from metal surface by Kumar, Aniruddha, Nilaya, J.P., Biswas, D.J., Bhatt, R.B., Afzal, Mohd, Panakkal, J.P., Kamath, H.S.

    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. ►…”
    Get full text
    Journal Article
  13. 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 by Kelkar, Anoop, Prakash, Amrit, Afzal, Mohd, Panakkal, J.P, Kamath, H.S

    “…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+],…”
    Get full text
    Journal Article
  14. 14

    Thermal expansion of simulated thoria–urania fuel by high temperature XRD by Bhagat, R.K., Krishnan, K., Kutty, T.R.G., Kumar, Arun, Kamath, H.S., Banerjee, S.

    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…”
    Get full text
    Journal Article
  15. 15

    Creep behaviour of δ-phase of U–Zr system by impression creep technique by Kutty, T.R.G., Basak, C.B., Kumar, Arun, Kamath, H.S.

    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…”
    Get full text
    Journal Article
  16. 16

    Non destructive determination of PuO 2 content in MOX fuel pins for fast reactors using Passive Gamma Scanning by Vrinda devi, K.V., Soreng, T., Mukherjee, D., Panakkal, J.P., Kamath, H.S.

    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…”
    Get full text
    Journal Article
  17. 17
  18. 18
  19. 19

    Characterization of (Th,U)O 2 fuel pellets made by impregnation technique by Kutty, T.R.G., Nair, M.R., Sengupta, P., Basak, U., Kumar, Arun, Kamath, H.S.

    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…”
    Get full text
    Journal Article
  20. 20