Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Avinash Gopalan"'
Autor:
Arnomitra Chatterjee, Kundan Kumar, Avinash Gopalan, Y. Pushpalatha Devi, R. N. Singh, S. K. Sinha
Publikováno v:
International Journal of Fracture. 233:195-210
Publikováno v:
Transactions of the Indian National Academy of Engineering. 7:575-582
Zr–2.5Nb alloy, with its high yield strength and low hydrogen absorption, is used in Pressurized Heavy Water Reactor (PHWR) as pressure tube. Hydrogen in solid solution form and in hydride precipitate form may alter the mechanical properties of the
Autor:
Vivek Patel, Avinash Gopalan, Harshit K. Khandelwal, Nachiket Keskar, Y. Pushpalatha Devi, R.N. Singh
Publikováno v:
International Journal of Pressure Vessels and Piping. 200:104844
Publikováno v:
Journal of Nuclear Materials. 569:153903
Publikováno v:
International Journal of Fracture. 205:103-109
Effect of loading rate on cleavage failure probability for ferritic/martensitic steels using Weibull stress analysis is studied. Calibration of Weibull slope for two grades of fusion reactor blanket steels namely, Indian Reduced Activation Ferritic/M
Autor:
Akanksha Samanta, Amit Soren, Ripandeep Singh, Avinash Gopalan, A.K. Bind, T.N. Murty, Rishi Sharma, Saurav Sunil
Publikováno v:
Journal of Nuclear Materials. 544:152681
The effect of radial hydride on the room temperature fracture toughness of the Zr-2.5Nb pressure tube material with 100% radial hydrides and hydrogen content up to 320wppm was investigated using curved compact tension (CCT) specimens. The hydride con
Publikováno v:
Journal of Nuclear Materials. 542:152457
Delayed Hydride Cracking (DHC) behaviour of Zr-2.5Nb Pressure Tube (PT) material used in Indian 200MWe Pressurised Heavy Water Reactor (PHWR) containing radial hydrides and circumferential hydrides was studied in the temperature range of 200–250 °
Autor:
S.A. Chandanshive, T.N. Murty, A.K. Bind, Avinash Gopalan, Saurav Sunil, Bhupendra K. Kumawat, R.N. Singh
Publikováno v:
Journal of Nuclear Materials. 536:152187
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 samples made from pressure tube were tested in air atmosphere at 300 °C and 350 °C at different
Publikováno v:
Journal of Nuclear Materials. 465:424-432
In this work, fracture behaviour of 20MnMoNi55 reactor pressure vessel (RPV) steel in the ductile to brittle transition regime (DBTT) is characterised. Compact tension (CT) and single edged notched bend (SENB) specimens of two different sizes were te
Publikováno v:
Proceedings of the 5th International Congress on Computational Mechanics and Simulation.