Search Results - "Suresh Kumar, V.A."

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  1. 1

    Investigation into steam generator tube life expectancy affected by SFR transients by Pathak, S.P., Velusamy, K., Pandey, S.K., Kumar, V.A Suresh

    Published in Progress in nuclear energy (New series) (01-01-2022)
    “…One of the decay heat removal systems in sodium cooled fast reactors (SFR) is the operation grade decay heat removal system (OGDHRS). During deployment of…”
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    Journal Article
  2. 2

    Failure analysis of a reducer section in the creep loop of INSOT facility by Prasanthi, T.N., Sudha, C., Chandran, T., Shanmughavel, M., Ganesan, V., Chandra Mouli, S., Prasad Reddy, G.V., Suresh Kumar, V.A., Sreedhar, B.K.

    Published in Engineering failure analysis (01-02-2023)
    “…•Sodium leak was observed in a reducer component of the INSOT (in-sodium testing) facility.•The reducer component was fabricated out of Ni based Alloy…”
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    Journal Article
  3. 3

    Experimental evaluation of the heat transfer performance of sodium heated once through steam generator by Vinod, V., Sivakumar, L.S., Kumar, V.A. Suresh, Noushad, I.B., Padmakumar, G., Rajan, K.K.

    Published in Nuclear engineering and design (01-07-2014)
    “…•PFBR has eight units of steam generators to transfer 1250MWt power.•A model steam generator was tested for its heat transfer performance.•The model steam…”
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    Journal Article
  4. 4

    Experimental evaluation of sodium to air heat exchanger performance by Vinod, V., Pathak, S.P., Paunikar, V.D., Suresh Kumar, V.A., Noushad, I.B., Rajan, K.K.

    Published in Annals of nuclear energy (01-08-2013)
    “…► Sodium to air heat exchangers are used to remove the decay heat produced in fast breeder reactor after shutdown. ► Finned tube sodium to air heat exchanger…”
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    Journal Article
  5. 5

    In-situ calibration of permanent magnet flow meters in PFBR using noise analysis technique by Ramakrishna, Ranga, Anup Kumar, P., Thirumalai, M., Vijayakumar, G., Suresh kumar, V.A., Suresh Kumar, K.V., Prakash, V., Rajan, K.K.

    Published in Flow measurement and instrumentation (01-12-2013)
    “…In Fast Breeder Reactor sodium circuits, permanent magnet flow meters (PMFM) are extensively used to measure the liquid sodium flow rate. The performance of…”
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    Journal Article
  6. 6

    Steam generator test facility—A test bed for steam generators of Indian sodium cooled fast breeder reactors by Suresh Kumar, V.A., Noushad, I.B., Rajan, K.K.

    Published in Nuclear engineering and design (01-07-2012)
    “…► Performance testing of a 5.5MW capacity once through straight tube steam generator. ► 5000h of endurance test has demonstrated the steam generator design. ►…”
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    Journal Article