Zobrazeno 1 - 7
of 7
pro vyhledávání: '"B. N. Rath"'
Autor:
B. N. Rath, S. J. Ghanwai, Mishra R., Bhattacharya S., Kaity S., Danani C., Kumar S., Alur V. D., Kumawat N., Sathiyamoorthy D., Anantharaman S.
Publikováno v:
Ceramics-Silikáty, Vol 58, Iss 2, Pp 123-131 (2014)
Beryllium oxide (BeO) can be used as a constituent for lithium titanate (Li2TiO3) based composite material for neutron multiplication and breeding in International Thermonuclear Experimental Reactor (ITER) having tritium breeding ratio (TBR) more tha
Externí odkaz:
https://doaj.org/article/b66b9c30ea434b33b7e6547c48655247
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:
B. N. Rath, R. N. Singh, J.K. Chakravartty, A.K. Bind, H. K. Khandelwal, Saurav Sunil, Per Ståhle
Publikováno v:
Materials Science and Engineering: A. 621:190-197
Previous work by one of the authors reported the stress-field for a fully-constrained hydride embedded in matrix computed using finite element method to develop an understanding of the temperature dependence of susceptibility of Zr-alloys to hydride
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b0cb4574ae43e5fdf880e302265eff77
https://doi.org/10.1016/j.msea.2014.10.052
https://doi.org/10.1016/j.msea.2014.10.052
Autor:
Dakshinamoorthy Sathiyamoorthy, R. V. Kulkarni, B. N. Rath, Chandan Danani, Santu Kaity, S. J. Ghanwat, S. Anantharaman, V.D. Alur
Publikováno v:
Journal of Materials Engineering and Performance. 22:3455-3460
The International Thermonuclear Experimental Reactor (ITER) is designed to demonstrate the scientific and technological feasibility of fusion power for energy purposes. Wide varieties of solid breeders and multiplier materials have been proposed for
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7ccdf1ec4a856c4f6f982b2038c9a636
https://doi.org/10.1007/s11665-013-0606-z
https://doi.org/10.1007/s11665-013-0606-z
Autor:
Dinesh Srivastava, E. Ramadasan, Indradev Samajdar, Suman Neogy, Gautam Kumar Dey, K.V. Manikrishna, S. Anatharaman, B. N. Rath, N. Saibaba, R.V. Kulkarni
Publikováno v:
Transactions of the Indian Institute of Metals. 64:395-399
β-transus boundary for the Zr-2.5%Nb alloy containing 1137 ppmw of O and 650 ppmw of Fe was established using quenching dilatometry technique. The solid cylindrical samples of the alloy were β homogenised at 1063°C and then quenched at different r
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c5dbd167f3d966bfe9cae7b5df432a38
https://doi.org/10.1007/s12666-011-0104-7
https://doi.org/10.1007/s12666-011-0104-7
Publikováno v:
Transactions of the Indian Institute of Metals. 63:671-674
Internal diameter measurements have been carried out on pressure tube S-07 of KAPS II and fifteen RAPS II pressure tubes. These data have been analyzed to derive empirical correlation for predicting diameter change in pressure tube during irradiation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5a2ad79fb18b3a815d2dcc5384259534
https://doi.org/10.1007/s12666-010-0102-1
https://doi.org/10.1007/s12666-010-0102-1
Autor:
J.B. Singh, R.N. Singh, A.K. Bind, J.K. Chakravartty, Sachin Kumar, H. K. Khandelwal, Saurav Sunil, B. N. Rath
Publikováno v:
Materials Performance and Characterization. 3:20130051
In heavy water cooled nuclear reactors, Zr–2.5Nb alloy is used for pressure tubes under cold worked and stress relieved (CWSR) condition in Canadian Deuterium Uranium (CANDU) reactors and under quenched and aged condition in RBMK and Fugen reactors
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7768c2110c541f3b75f0f7665c538880
https://doi.org/10.1520/mpc20130051
https://doi.org/10.1520/mpc20130051