Search Results - "Murty, T.N."

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  1. 1

    Deformation behaviour and microstructure evolution of Ti-2.3Al-2.6Zr alloy in the temperature range of 700–1000 °C by Behera, A.N., Murty, T.N., Sarkar, A., Kapoor, R., Singh, R.N., Vaibhaw, Kumar, Arora, U.K., Kapoor, K.

    Published in Journal of alloys and compounds (15-12-2024)
    “…Ti-2.3Al-2.6Zr alloy was hot deformed at temperatures from 700 to 1000 °C and strain rates from 10−2 −30 s−1. The uniaxial compression tests were conducted in…”
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    Journal Article
  2. 2

    Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging by Shukla, Shefali, Singh, R.N., Kashyap, Y.S., Murty, T.N., Keskar, Nachiket, Roy, Tushar, Singh, Prashant, Shukla, Mayank

    Published in Journal of nuclear materials (01-07-2023)
    “…•Hydrogen diffusion anisotropy studied for Zr-2.5%Nb alloy.•The diffusivity values for radial direction are 25–30% less than axial and circumferential.•The…”
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    Journal Article
  3. 3

    Fish-mouth opening of an ammonia cracker tube of Alloy 625 by Singh, J.B., Verma, A., Murty, T.N., Karri, M., Khan, S., Keskar, N.

    Published in Engineering failure analysis (01-10-2022)
    “…•Reports the Fish-mouth failure of an alloy 625 tube.•The failure is attributed to short-term temperature excursion above 1050 °C.•The failure temperature is…”
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    Journal Article
  4. 4

    Effect of radial hydride on delayed hydride cracking behaviour of Zr-2.5Nb pressure tube material by Sunil, Saurav, Gopalan, Avinash, Bind, A.K., Sharma, R.K., Murty, T.N., Singh, R.N.

    Published in Journal of nuclear materials (15-12-2020)
    “…Delayed Hydride Cracking (DHC) behaviour of Zr-2.5Nb Pressure Tube (PT) material used in Indian 200MWe Pressurised Heavy Water Reactor (PHWR) containing radial…”
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    Journal Article
  5. 5

    Isothermal stress reorientation of hydrides in Zr-2.5Nb pressure tube alloy by Murty, T.N., Vidhan, R.V.S. Krishna, G., Avinash, Sunil, Saurav, Sarkar, A., Singh, R.N.

    Published in Journal of nuclear materials (01-02-2022)
    “…•For the first time, in-situ hydride reorientation phenomenon in Zr-2.5Nb alloy has been investigated.•Threshold stress for reorientation of hydrides was…”
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    Journal Article
  6. 6

    Effect of radial hydride on room temperature fracture toughness of Zr-2.5Nb pressure tube material by Gopalan, Avinash, Bind, A.K., Sunil, Saurav, Murty, T.N., Sharma, R.K., Samanta, Akanksha, Soren, Amit, Singh, R.N.

    Published in Journal of nuclear materials (01-02-2021)
    “…•The effect of radial hydride on the room temperature fracture toughness of the Zr-2.5Nb pressure tube material was investigated.•The curved compact tension…”
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    Journal Article
  7. 7

    Stress assisted oxide cracking of Zr-2.5Nb pressure tube material by Gopalan, Avinash, Sunil, Saurav, Murty, T.N., Bind, A.K., Kumawat, B.K., Chandanshive, S.A., Singh, R.N.

    Published in Journal of nuclear materials (01-08-2020)
    “…The crack growth rates of un-irradiated and un-hydrided Zr-2.5Nb pressure tube material has been investigated in both air and in vacuum. Pre-cracked CCT…”
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    Journal Article