Zobrazeno 1 - 10
of 32
pro vyhledávání: '"E. Ramadasan"'
Autor:
K.K. Vaze, Kamal Sharma, A.K. Ghosh, K. Madhusoodanan, R.N. Singh, B Gaur, Vivek Bhasin, E. Ramadasan, K.V. Kasiviswanathan, K. S. Balakrishnan, P.K. Singh, B.B. Rupani, V. Karthik, S. Anantharaman
Publikováno v:
Nuclear Engineering and Design. 330:303-316
This paper presents outcome of round robin exercise on usage of ball indentation technique to predict strength properties of three different materials which are used in Indian nuclear reactors. The main objectives were to evolve a standardized proced
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7e46d54b0ce6662e281c31679249fb7d
https://doi.org/10.1016/j.nucengdes.2018.01.015
https://doi.org/10.1016/j.nucengdes.2018.01.015
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:
Suman Neogy, Suparna Banerjee, N. Saibaba, Dinesh Srivastava, Gautam Kumar Dey, S. Anantharaman, E. Ramadasan
Publikováno v:
Advanced Materials Research. 585:56-61
The Indian PHWR uses Zr-2.5% Nb pressure tubes and its in-reactor performance mainly irradiation creep and growth depends strongly on its microstructure. A detailed microstructural examination was carried out on unirradiated pressure tubes off-cuts a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2d958f978d988ff62f784b18b356b87
https://doi.org/10.4028/www.scientific.net/amr.585.56
https://doi.org/10.4028/www.scientific.net/amr.585.56
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:
Defect and Diffusion Forum. :49-67
This paper presents hydrogen concentration profiles in notched tensile test specimens which have been charged electrolytically with hydrogen, with and without the application of a tensile load. A standard 8mm ASTM tensile specimen, extended at one en
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ab4e8c6221d2b60cb8af2d2558532a29
https://doi.org/10.4028/www.scientific.net/ddf.295-296.49
https://doi.org/10.4028/www.scientific.net/ddf.295-296.49
Publikováno v:
Journal of Nuclear Materials. 383:45-53
The post irradiation examination (PIE) facility at the Bhabha Atomic Research Centre (BARC) has been in operation for more than three decades. Over these years this facility has been utilized for examination of experimental fuel pins and fuels from c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::000dbeb3e40a8adc3156085d89749424
https://doi.org/10.1016/j.jnucmat.2008.08.022
https://doi.org/10.1016/j.jnucmat.2008.08.022
Autor:
Baidyanath Rath, E. Ramadasan, V.P. Jathar, N. Kumawat, P. K. Mishra, Suparna Banerjee, K. Unnikrishnan, M.P. Dhotre, R.S. Shriwastaw, J.L. Singh, P.M. Ouseph, D.N. Sah, V.D. Alur, P.B. Kondejkar, H.N. Singh
Publikováno v:
Journal of Nuclear Materials. 383:128-131
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 irradiation examination in BARC hot cells facility. The examination included visual exam
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::788f7307e9ab9d89efc82df5cf009f02
https://doi.org/10.1016/j.jnucmat.2008.08.054
https://doi.org/10.1016/j.jnucmat.2008.08.054
Publikováno v:
Applied Surface Science. 253:4404-4408
Metallographic investigation of the microstructure of sintered Thoria pellets necessitates appropriate surface preparation of these pellets. Conventional etching methods involving either chemical or thermal etching techniques being unsuitable for sur
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6520af259b6b870abf8c809fd466097b
https://doi.org/10.1016/j.apsusc.2006.09.055
https://doi.org/10.1016/j.apsusc.2006.09.055
Autor:
N. Saibaba, S. K. Jha, S. Tonpe, Kumar Vaibhaw, V. Deshmukh, S. V. Ramana Rao, K. V. Mani Krishna, S. Neogy, D. Srivastava, G. K. Dey, R. V. Kulkarni, B. B. Rath, E. Ramadasan, S. A. Anantharaman
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0549e69d6fc743e28de35505f831770f
https://doi.org/10.1520/stp152920120015
https://doi.org/10.1520/stp152920120015
Publikováno v:
Metallurgical Transactions A. 24:495-501
The observations reported in the present communication were made in the course of a microstructural investigation on dilute Zr-Ni alloys. The alloys were prepared from nuclear-grade sponge zirconium and high-purity nickel by nonconsumable arc melting
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d40f8bc83fa3a938c3395157e7a5ebc2
https://doi.org/10.1007/bf02657337
https://doi.org/10.1007/bf02657337