Zobrazeno 1 - 10
of 24
pro vyhledávání: '"V.A. Suresh Kumar"'
Autor:
T.N. Prasanthi, C. Sudha, T. Chandran, M. Shanmughavel, V. Ganesan, S. Chandra Mouli, G.V. Prasad Reddy, V.A. Suresh Kumar, B.K. Sreedhar
Publikováno v:
Engineering Failure Analysis. 144:106991
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::948fd77309988f9a9697cf1f391bb489
https://doi.org/10.1016/j.engfailanal.2022.106991
https://doi.org/10.1016/j.engfailanal.2022.106991
Publikováno v:
Progress in Nuclear Energy. 143:104059
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a6d56715b1c2ec096bdfeac59c34baff
https://doi.org/10.1016/j.pnucene.2021.104059
https://doi.org/10.1016/j.pnucene.2021.104059
Akademický článek
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Autor:
P. C. Clinsha, T. Muthu Ambika, Sajal Ghosh, S. Shyamkumar, V. Jayaraman, A. Sree Rama Murthy, S. Premalatha, K.I. Gnanasekar, Rajesh Ganesan, Madhugiri Prakash Venkatesh, I. Lakshmigandhan, P.R. Reshmi, E. Prabhu, Nair Afijith Ravindranath, K.H. Mahendran, V.A. Suresh Kumar
Publikováno v:
Nuclear Engineering and Design. 382:111388
A comprehensive hydrogen detection system is developed to track steam leak into sodium by monitoring hydrogen in liquid sodium and in argon cover gas simultaneously and its performance is demonstrated. A fraction of hydrogen, generated from steam lea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b7751ef54d4a970555586f63fc4c8d81
https://doi.org/10.1016/j.nucengdes.2021.111388
https://doi.org/10.1016/j.nucengdes.2021.111388
Autor:
Bojja Sreedhar, S. Chandramouli, I.B. Noushad, S. Sakthivel Murugan, Sanjeev Kumar, R. K. Sharma, P. Selvaraj, K. Sathishkumar, R. Punniamoorthy, C. Meikandamurthy, P. Vasudevan, S. Harishkumaran, S. D. Sajish, V.A. Suresh Kumar, Ranjith Jovin Cyriac, R. Ramakrishna, Vishal D. Paunikar, Sudheer Patri
Publikováno v:
Lecture Notes in Mechanical Engineering ISBN: 9789811387661
An eddy current flow sensor (ECFS) is used for measuring the sodium flow through the reactor core in prototype fast breeder reactor (PFBR). Being a safety critical system, ensuring the structural integrity of the sensor and associated support systems
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3c66fd132143ea443f3a8ac46db420a7
https://doi.org/10.1007/978-981-13-8767-8_67
https://doi.org/10.1007/978-981-13-8767-8_67
Publikováno v:
Nuclear Engineering and Design. 273:412-420
Steam generator is a crucial component in a nuclear power plant because its availability is directly linked to the availability of heat transport system and thus the plant availability. In Prototype Fast Breeder Reactor (PFBR) which is in advanced st
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3e30227a20b9efe0ae2ff5f48511ffd4
https://doi.org/10.1016/j.nucengdes.2014.03.034
https://doi.org/10.1016/j.nucengdes.2014.03.034
Autor:
V.A. Suresh Kumar, P. Anup Kumar, K.K. Rajan, K.V. Suresh Kumar, V. Prakash, R. Ramakrishna, M. Thirumalai, G. S. Vijayakumar
Publikováno v:
Flow Measurement and Instrumentation. 34:76-82
In Fast Breeder Reactor sodium circuits, permanent magnet flow meters (PMFM) are extensively used to measure the liquid sodium flow rate. The performance of PMFM can degrade with respect to time due to various reasons. This degradation results in red
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::05f904b8bc2e742880365f23db5d08e6
https://doi.org/10.1016/j.flowmeasinst.2013.08.004
https://doi.org/10.1016/j.flowmeasinst.2013.08.004
Publikováno v:
Annals of Nuclear Energy. 58:6-11
Sodium to air heat exchangers (AHXs) is used in Prototype Fast Breeder Reactor (PFBR) circuits to reject the decay heat produced by the radioactive decay of the fission products after reactor shutdown, to the atmospheric air. The heat removal through
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6140ca1e4db70cbbaddeba37277aeb29
https://doi.org/10.1016/j.anucene.2013.01.063
https://doi.org/10.1016/j.anucene.2013.01.063
Autor:
M. Radhika, I.B. Noushad, V. Thomas Paul, P. Parameswaran, S. Saroja, M. Vijayalakshmi, V.A. Suresh Kumar
Publikováno v:
Journal of Failure Analysis and Prevention. 13:47-54
The failure of the stainless steel housing of Electro Chemical Hydrogen Metre (ECHM) in the Steam Generator Test Facility resulting in a minor sodium fire has been investigated through systematic metallographic and fractographic analyses. The root ca
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6578a73620483a70619d21406a27e929
https://doi.org/10.1007/s11668-012-9631-8
https://doi.org/10.1007/s11668-012-9631-8
Publikováno v:
Nuclear Engineering and Design. 248:169-177
Second stage of India's three stage nuclear power programme consisting of the development and operation of fast breeder reactors (FBRs) commenced with the construction, commissioning and operation of fast breeder test reactor (FBTR) at Indira Gandhi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::98bb9fc11dcb0177cff55ef747535ef6
https://doi.org/10.1016/j.nucengdes.2012.03.021
https://doi.org/10.1016/j.nucengdes.2012.03.021