Search Results - "Pandit, K.M."

  • Showing 1 - 4 results of 4
Refine Results
  1. 1

    High temperature steam oxidation study on Zr–2.5%Nb pressure tube under simulated LOCA condition by Banerjee, Suparna, Sawarn, Tapan K., Alur, V.D., Rath, B.N., Kaity, Santu, Pandit, K.M., Anantharaman, S., Sah, D.N.

    Published in Journal of nuclear materials (01-08-2013)
    “…Study of high temperature steam oxidation kinetics and microstructural evolution during the oxidation was carried out on the coupons of Zr–2.5%Nb pressure tube…”
    Get full text
    Journal Article Conference Proceeding
  2. 2

    Study of clad ballooning and rupture behavior of fuel pins of Indian PHWR under simulated LOCA condition by Sawarn, Tapan K., Banerjee, Suparna, Pandit, K.M., Anantharaman, S.

    Published in Nuclear engineering and design (01-12-2014)
    “…•We study ballooning and rupture characteristic of Indian PHWR fuel cladding.•Burst pressure and temperature, circumferential and diametral strain and burst…”
    Get full text
    Journal Article
  3. 3

    Fracture toughness of irradiated Zr–2.5Nb pressure tube from Indian PHWR by Shah, Priti Kotak, Dubey, J.S., Shriwastaw, R.S., Dhotre, M.P., Bhandekar, A., Pandit, K.M., Anantharaman, S., Singh, R.N., Chakravartty, J.K.

    Published in Journal of nuclear materials (01-03-2015)
    “…Fracture toughness of irradiated Zr–2.5Nb alloy pressure tube, fabricated by the cold pilgering and stress relieving route, was evaluated using disk compact…”
    Get full text
    Journal Article
  4. 4

    Delayed hydride crack growth study on irradiated Zr–2.5Nb pressure tube by Shah, Priti Kotak, Dubey, J.S., Kumar, Ashwini, Shriwastaw, R.S., Rath, B.N., Pandit, K.M., Dhotre, M.P., Mishra, P., Alur, V.D., Anantharaman, S.

    Published in Journal of nuclear materials (01-05-2015)
    “…Delayed hydride crack (DHC) growth study was carried out on irradiated Indian Zr–2.5Nb pressure tube which had seen around 8 effective full power years of…”
    Get full text
    Journal Article