Search Results - "VISWANATHAN, U. K"

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  1. 1

    Effects of austenite reversion during overageing on the mechanical properties of 18 Ni (350) maraging steel by Viswanathan, U.K., Dey, G.K., Sethumadhavan, V.

    “…The sequence of austenite reversion during overageing in 18 Ni (350) maraging steel was examined and its effects on the mechanical properties were evaluated…”
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    Journal Article
  2. 2

    Influence of hydrogen content on impact toughness of Zr–2.5Nb pressure tube alloy by Singh, R.N., Viswanathan, U.K., Kumar, Sunil, Satheesh, P.M., Anantharaman, S., Chakravartty, J.K., Ståhle, P.

    Published in Nuclear engineering and design (01-07-2011)
    “…► For the first time impact behaviour of Zr–2.5Nb pressure tube material used in Indian Pressurized Heavy Water Reactor (IPHWR) as a function of hydrogen…”
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    Journal Article
  3. 3

    Post irradiation examination of thermal reactor fuels by Sah, D.N., Viswanathan, U.K., Ramadasan, E., Unnikrishnan, K., Anantharaman, S.

    Published in Journal of nuclear materials (15-12-2008)
    “…The post irradiation examination (PIE) facility at the Bhabha Atomic Research Centre (BARC) has been in operation for more than three decades. Over these years…”
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    Journal Article Conference Proceeding
  4. 4

    Behaviour of irradiated PHWR fuel pins during high temperature heating by Viswanathan, U.K., Unnikrishnan, K., Mishra, Prerna, Banerjee, Suparna, Anantharaman, S., Sah, D.N.

    Published in Journal of nuclear materials (15-12-2008)
    “…Fuel pins removed from an irradiated pressurised heavy water reactor (PHWR) fuel bundle discharged after an extended burn up of 15,000 MWd/tU have been…”
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    Journal Article Conference Proceeding
  5. 5

    Blind prediction exercise on modeling of PHWR fuel at extended burnup by Sah, D.N., Viswanathan, U.K., Viswanadham, C.S., Unnikrishnan, K., Rath, B.N.

    Published in Journal of nuclear materials (15-12-2008)
    “…A blind prediction exercise was organised on Indian Pressurised Heavy Water Reactor (PHWR) fuel to investigate the predictive capability of existing codes for…”
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    Journal Article Conference Proceeding
  6. 6

    Evaluation of effect of hydrogen on toughness of Zircaloy-2 by instrumented drop weight impact testing by Viswanathan, U.K., Singh, R.N., Basak, C.B., Anantharaman, S., Sahoo, K.C.

    Published in Journal of nuclear materials (01-05-2006)
    “…Hydride-assisted degradation in fracture toughness of Zircaloy-2 was evaluated by carrying out instrumented drop-weight tests on curved Charpy specimens…”
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    Journal Article
  7. 7

    Service-induced Changes in the Microstructure and Mechanical Properties of a Cr-Mo-Ni-V Turbine Steel by Yamashita, Mitsuo, Viswanathan, U. K., Yamamoto, Isamu, Kobayashi, Toshiro

    Published in ISIJ International (01-01-1997)
    “…The effect of service temperature on the degradation of mechanical properties of a low alloy Cr-Mo-Ni-V steel applied for turbine rotor, retired after 15.8…”
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    Journal Article
  8. 8

    Measurement of fission gas release, internal pressure and cladding creep rate in the fuel pins of PHWR bundle of normal discharge burnup by Viswanathan, U.K., Sah, D.N., Rath, B.N., Anantharaman, S.

    Published in Journal of nuclear materials (01-08-2009)
    “…Fuel pins of a Pressurised Heavy Water Reactor (PHWR) fuel bundle discharged from Narora Atomic Power Station unit #1 after attaining a fuel burnup of 7528…”
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    Journal Article
  9. 9

    Evaluation of hot hardness and creep of a 350 grade commercial maraging steel by VISWANATHAN, U. K, KUTTY, T. R. G, KESWANI, R, GANGULY, C

    Published in Journal of materials science (15-05-1996)
    “…The hardening response and the indentation creep of a 350 grade commercial maraging steel were evaluated using a hot hardness tester. The hardness versus…”
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    Journal Article
  10. 10

    Effect of thermal cycling on the mechanical properties of 350-grade maraging steel by VISWANATHAN, U. K, KISHORE, R, ASUNDI, M. K

    “…The effects of retained austenite produced by thermal cycling on the mechanical properties of a precipitation hardened 350 grade commercial maraging steel were…”
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    Journal Article
  11. 11

    Study of creep deformation of irradiated zircaloy cladding by isothermal heating of irradiated PHWR fuel pins in temperature range 700°C–900°C by Sah, D. N., Viswanathan, U. K., Anantharaman, S.

    “…Fuel pins removed from actual irradiated fuel bundles discharged from Pressurised Heavy Water Reactors (PHWRs) have been used for experimental study of high…”
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    Journal Article
  12. 12
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