Search Results - "Shriwastaw, R. S."

Post irradiation examination of reactor operated pressure tube S-07 of KAPS-2 by Sah, D.N., Ramadasan, E., Unnikrishnan, K., Singh, J.L., Ouseph, P.M., Rath, B.N., Singh, H.N., Kondejkar, P.B., Alur, V.D., Banerjee, Suparna, Shriwastaw, R.S., Mishra, Prerna, Jathar, V.P., Kumawat, N., Dhotre, M.P.

“…An irradiated Zr–2.5% Nb pressure tube removed from Kakrapar Atomic Power Station unit #2 (KAPS-2) after eight effective full power years was subjected to post…”
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Evaluation of ultimate tensile strength using Miniature Disk Bend Test by Kumar, Kundan, Pooleery, Arun, Madhusoodanan, K., Singh, R.N., Chakravartty, J.K., Shriwastaw, R.S., Dutta, B.K., Sinha, R.K.

“…Since inception of Miniature Disk Bend Test (MDBT) technique, UTS correlations have been an open issue. Correlations based on Pmax of load–displacement curve…”
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Mechanical properties of Zr–2.5%Nb pressure tube material subjected to heat treatments in α+β phase field by Kulkarni, R.V., Mani Krishna, K.V., Neogy, S., Srivastava, D., Ramadasan, E., Shriwastaw, R.S., Rath, B.N., Saibaba, N., Jha, S.K., Dey, G.K.

“…Heat treatment studies from α+β phase field were carried out on Zr–2.5wt%Nb alloy pressure tube (PT) material using quenching dilatometry. The effects of…”
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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.

“…Fracture toughness of irradiated Zr–2.5Nb alloy pressure tube, fabricated by the cold pilgering and stress relieving route, was evaluated using disk compact…”
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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.

“…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…”
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Post irradiation examination of tight fit garter springs from Indian PHWR by Dubey, J.S., Shriwastaw, R.S., Kumar, Ashwini, Shah, Priti Kotak, Rath, B.N., Kumar, Sunil, Mishra, Prerna, Alur, V.D., Mallik, G.K., Anantharaman, S.

“…Garter springs play an important role in maintaining the annulus gap between hot pressure tubes and cold calandria tubes of PHWRs. Post irradiation examination…”
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Determination of correlation parameters for evaluation of mechanical properties by Small Punch Test and Automated Ball Indentation Test for Zr–2.5% Nb pressure tube material by Kulkarni, R.V., Mani Krishna, K.V., Neogy, S., Srivastava, D., Ramadasan, E., Dey, G.K., Saibaba, N., Jha, S.K., Shriwastaw, R.S., Anantharaman, S.

“…•Empirical correlations for mechanical property evaluation of Zr–2.5% Nb by SPT and ABI determined.•Correlation parameters have been established as a function…”
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Estimation of ring tensile properties of steam oxidized Zircaloy-4 fuel cladding under simulated LOCA condition by Shriwastaw, R.S., Sawarn, Tapan K., Banerjee, Suparna, Rath, B.N., Dubey, J.S., Kumar, Sunil, Singh, J.L., Bhasin, Vivek

“…The present study involves the estimation of ring tensile properties of Indian Pressurised Heavy Water Reactor (IPHWR) fuel cladding made of Zircaloy-4,…”
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Influence of temperature and hydrogen content on the transverse mechanical properties of Zircaloy-4 fuel cladding by Sawarn, T.K., Shriwastaw, R.S., Banerjee, Suparna, Samanta, Akanksha, Kumar, Suraj, Sunil, Saurav, Shah, P. Kotak, Singh, R.N.

“…This paper presents the results of the investigation on the influence of hydrogen on the transverse mechanical properties of the Zircaloy-4 fuel cladding at…”
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Numerical evaluation of J-R curve using small punch test data by Kumar, Pradeep, Dutta, B.K., Chattopadhyay, J., Shriwastaw, R.S.

“…•A numerical approach is proposed to generate J-R data from SPT experiments.•It is utilized for three structural materials from six SPT experiments.•Acceptable…”
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Tensile strength of Zr-2.5 Nb pressure tubes: A statistical study by Shah, Priti Kotak, Dubey, J.S., Datta, D., Shriwastaw, R.S., Rath, B.N., Singh, R.N., Anantharaman, S., Chakravartty, J.K.

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Anisotropy in impact behavior of Zr-2.5Nb pressure tube alloy by Shah, Priti Kotak, Satheesh, P. M., Singh, R. N., Dubey, J. S., Shriwastaw, R. S., Balakrishnan, K. S., Kulkarni, A. P., Mishra, Prerna, Jathar, V. P., Majumdar, S., Alur, V. D., Anantharaman, S., Chakravartty, J. K.

“…Zr-2.5Nb alloy tubes in cold worked and stress relieved (CWSR) condition serve as pressure boundary for hot coolant in Indian Pressurized Heavy Water Reactor…”
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