Zobrazeno 1 - 10
of 25
pro vyhledávání: '"R.S. Shriwastaw"'
Autor:
T.K. Sawarn, R.S. Shriwastaw, Suparna Banerjee, Akanksha Samanta, Suraj Kumar, Saurav Sunil, P. Kotak Shah, R.N. Singh
Publikováno v:
Progress in Nuclear Energy. 153:104439
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3b3ae3c8f473f880cfdb02699b435967
https://doi.org/10.1016/j.pnucene.2022.104439
https://doi.org/10.1016/j.pnucene.2022.104439
Autor:
J.L. Singh, Suparna Banerjee, J.S. Dubey, Baidyanath Rath, Sunil Kumar, Tapan K. Sawarn, Vivek Bhasin, R.S. Shriwastaw
Publikováno v:
Journal of Nuclear Materials. 493:460-470
The present study involves the estimation of ring tensile properties of Indian Pressurised Heavy Water Reactor (IPHWR) fuel cladding made of Zircaloy-4, subjected to experiments under a simulated loss-of-coolant-accident (LOCA) condition. Isothermal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7009abd4ac9eb4f01f7429850d9adba4
https://doi.org/10.1016/j.jnucmat.2017.06.032
https://doi.org/10.1016/j.jnucmat.2017.06.032
Autor:
P. K. Mishra, K.M. Pandit, V.P. Jathar, Anil Bhandekar, J.L. Singh, Baidyanath Rath, P. M. Satheesh, R.S. Shriwastaw, Sunil Kumar, G. K. Mallik, Harveer Singh
Publikováno v:
Thorium—Energy for the Future ISBN: 9789811326578
Different aspects of thorium fuel cycle have been studied for the development of thorium fuel-based Advanced Heavy Water Reactor (AHWR) in India. In order to study the irradiation performance of thoria-based mixed oxide (MOX) fuels, short-length fuel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8634f1a5be0f0315d9e71911a10c06b3
https://doi.org/10.1007/978-981-13-2658-5_22
https://doi.org/10.1007/978-981-13-2658-5_22
Autor:
S. Anantharaman, B. N. Rath, J.K. Chakravartty, R.N. Singh, D.P. Datta, R.S. Shriwastaw, Priti Kotak Shah, J.S. Dubey
Publikováno v:
Nuclear Engineering and Design. 295:789-796
In order to get an idea of the statistical variation in the tensile properties of the double-melted as well as quadruple melted Zr-2.5 Nb pressure tubes (PTs) and also the variation in tensile properties between the two ends of the pressure tubes, te
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d4dea3aef5cca893dd4d26baf0310df2
https://doi.org/10.1016/j.nucengdes.2015.07.019
https://doi.org/10.1016/j.nucengdes.2015.07.019
Autor:
Sunil Kumar, G.K. Mallik, R.S. Shriwastaw, P. K. Mishra, Ashwini Kumar, Baidyanath Rath, J.S. Dubey, V.D. Alur, S. Anantharaman, Priti Kotak Shah
Publikováno v:
Journal of Nuclear Materials. 462:205-213
Garter springs play an important role in maintaining the annulus gap between hot pressure tubes and cold calandria tubes of PHWRs. Post irradiation examination (PIE) was carried out on the garter springs removed from Indian PHWR after around 8 and 15
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a674214efc970cd3a75e5fb80c13a21b
https://doi.org/10.1016/j.jnucmat.2015.04.008
https://doi.org/10.1016/j.jnucmat.2015.04.008
Autor:
B.K. Dutta, Kundan Kumar, Arun Pooleery, R.K. Sinha, R.S. Shriwastaw, Ripandeep Singh, K. Madhusoodanan, J.K. Chakravartty
Publikováno v:
Journal of Nuclear Materials. 461:100-111
Correlations for evaluation of Ultimate Tensile Strength (UTS) using Miniature Disk Bend Test (MDBT) or Small Punch Test (SPT) has been an open issue since the development of the techniques. The larger plastic strains, in tri-axial state of stress du
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bfbc750a4dba78cb6dad9ed9c30e204e
https://doi.org/10.1016/j.jnucmat.2015.02.029
https://doi.org/10.1016/j.jnucmat.2015.02.029
Autor:
J.S. Dubey, Baidyanath Rath, S. Anantharaman, V.D. Alur, Ashwini Kumar, Priti Kotak Shah, K.M. Pandit, M.P. Dhotre, Prabha Shankar Mishra, R.S. Shriwastaw
Publikováno v:
Journal of Nuclear Materials. 460:1-4
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 operation. Disc compact tension type specimens were used for the DHC tests at 210 °C, 250 °
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::187ba260c5d2d807547d94899863e8ed
https://doi.org/10.1016/j.jnucmat.2015.01.046
https://doi.org/10.1016/j.jnucmat.2015.01.046
Autor:
R.N. Singh, J.K. Chakravartty, Priti Kotak Shah, J.S. Dubey, R.S. Shriwastaw, Anil Bhandekar, M.P. Dhotre, K.M. Pandit, S. Anantharaman
Publikováno v:
Journal of Nuclear Materials. 458:319-325
Fracture toughness of irradiated Zr–2.5Nb alloy pressure tube, fabricated by the cold pilgering and stress relieving route, was evaluated using disk compact tension type specimens. These specimens were punched out from the irradiated pressure tube
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c138d692ce1185befe8a1ca5cff0e8d2
https://doi.org/10.1016/j.jnucmat.2014.12.066
https://doi.org/10.1016/j.jnucmat.2014.12.066
Autor:
K.V. Mani Krishna, R.V. Kulkarni, E. Ramadasan, R.S. Shriwastaw, Dinesh Srivastava, S.K. Jha, S. Anantharaman, Suman Neogy, N. Saibaba, Gautam Kumar Dey
Publikováno v:
Nuclear Engineering and Design. 265:1101-1112
Empirical correlation parameters for evaluation of key mechanical properties of anisotropic Zr–2.5% Nb pressure tube (PT) material have been determined for Small Punch Test (SPT) and Automated Ball Indentation (ABI) Test. Parameters have been devel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0bd212c0b6c40199613df95e52b9ce51
https://doi.org/10.1016/j.nucengdes.2013.10.009
https://doi.org/10.1016/j.nucengdes.2013.10.009
Autor:
J.K. Chakravartty, Priti Kotak Shah, A.P. Kulkarni, P. K. Mishra, P. M. Satheesh, Sanjib Majumdar, S. Anantharaman, V.P. Jathar, V.D. Alur, R.N. Singh, K. S. Balakrishnan, J.S. Dubey, R.S. Shriwastaw
Publikováno v:
Transactions of the Indian Institute of Metals. 64:67-70
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 (IPHWR). Due to both microstructural and crystallographic anisotropy, the mechanical propert
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::45b75300ab26e8e9986f227e92dae7a6
https://doi.org/10.1007/s12666-011-0013-9
https://doi.org/10.1007/s12666-011-0013-9