Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Sunil Belsare"'
Autor:
Kedar Satish Bhope, Vinay Menon, Sunil Belsare, Samir khirwadkar, Rajamannar swamy, Mayur Mehta, Premjit Singh Kongkham, Tushar Patel, Nikunj Patel, Prakash Mokariya
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::968e66ae2e6b25446c6bddf6ddd22593
https://doi.org/10.2139/ssrn.4402941
https://doi.org/10.2139/ssrn.4402941
Autor:
Tushar Patel, K. Premjit Singh, Mayur Mehta, Kedar Bhope, K. Deepu, Prakash Mokaria, S.S. Khirwadkar, Sunil Belsare, Rajamanar Swamy, Nikunj Patel, Vinay Menon, Alpesh A. Patel, Sudhir Tripathi, Kalpesh Galodiya
Publikováno v:
Fusion Engineering and Design. 146:2273-2276
The dome and reflector plate are the parts of divertor plasma facing components (PFCs) of ITER tokamak which are mainly aimed for the removal of heat load of maximum 5 MW/m2 in steady state condition. The dome is a curved tungsten armoured component
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0f3084ad61fb020d547aa8f292c2a4cb
https://doi.org/10.1016/j.fusengdes.2019.03.170
https://doi.org/10.1016/j.fusengdes.2019.03.170
Autor:
Tushar Patel, Sudhir Tripathi, Sunil Belsare, Nikunj Patel, Rajamannar Swamy, S.S. Khirwadkar, Prakash Mokaria
Publikováno v:
Fusion Engineering and Design. 124:252-256
High Heat Flux Test Facility (HHFTF) at Institute for Plasma Research in Bhat in India is established for testing thermal performance of plasma facing materials and components under intense heat loads expected in plasma fusion devices. It mainly cons
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2bb4bfe633c700e891aa381547929fe5
https://doi.org/10.1016/j.fusengdes.2017.04.109
https://doi.org/10.1016/j.fusengdes.2017.04.109
Autor:
Sunil Belsare, Nikunj Patel, K. Galodiya, Rajamannar Swamy, Tushar Patel, Kedar Bhope, S. Kanpara, S.S. Khirwadkar, P. Mokariya, Yashashri Patil
Publikováno v:
Materials Today: Proceedings. 3:3055-3063
Pure Tungsten (W) & Tungsten-lanthanum oxide (WL) were fabricated using Direct Sintering Press. W & WL found to be very good thermo-mechanical properties with higher densification desired for Plasma Facing Material. Both materials were subjected to t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d946223a301fb4b6c48c9eaac5625bb0
https://doi.org/10.1016/j.matpr.2016.09.020
https://doi.org/10.1016/j.matpr.2016.09.020
Autor:
Rajamannar Swamy, M. J. Singh, Arun Chakraborty, Kedar Bhope, S.S. Khirwadkar, Sudhir Tripathi, Mainak Bandyopadhyay, Venkata Nagaraju M, Hitesh Patel, Sunil Belsare, Jaydeep Joshi
Publikováno v:
Fusion Engineering and Design. 155:111543
Indian Test Facility (INTF) is a testbed to carry out neutral beam experiments where beam with peak power densities reach about 66 MW/m2 and incident on calorimeters. To survive such thermal fluxes, Hypervapotron (HV) elements are devised in designin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::800dc3b375789b49493b0c794d8bb343
https://doi.org/10.1016/j.fusengdes.2020.111543
https://doi.org/10.1016/j.fusengdes.2020.111543
Autor:
Kedar Bhope, Rajamannar Swamy, M. S. Khan, D. Krishnan, I. Antwala, Prakash Mokaria, Sunil Belsare, Nikunj Patel, Tushar Patel, Sudhir Tripathi, Yashashri Patil, Mayur Mehta, S.S. Khirwadkar, K. Galodiya
Publikováno v:
Fusion Engineering and Design. 95:84-90
Paper describes the newly established high heat flux test facility (HHFTF) at IPR in India. The facility is being used to simulate typical steady state and transient thermal load conditions for testing Divertor plasma facing components using a 200 kW
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::951245dea0b790fc57377f8a379d2728
https://doi.org/10.1016/j.fusengdes.2015.04.036
https://doi.org/10.1016/j.fusengdes.2015.04.036
Autor:
Kedar Bhope, Yashashri Patil, Sunil Belsare, Sudhir Tripathi, S.S. Khirwadkar, M. S. Khan, Rajamannar Swamy
Publikováno v:
Nukleonika, Vol 60, Iss 2, Pp 285-288 (2015)
This paper is focused on various aspects of the development and testing of water cooled divertor PFCs. Divertor PFCs are mainly designed to absorb the heat and particle fluxes outflowing from the core plasma of fusion devices like ITER. The Divertor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e0cc8c4a5d923cc1b556d73c4bec55da
https://doi.org/10.1515/nuka-2015-0053
https://doi.org/10.1515/nuka-2015-0053
Autor:
Satish D Patel, K. Sathyanarayana, Ronak Shah, Jatin Patel, Harshida Patel, Yury Belov, S. Laxmikant Rao, Pragnesh Dhorajiya, Rajan Babu, V. I. Belousov, Vipal Rathod, Mikhail Shmelev, Priyanka A. Solanki, D. Bora, Anjali Sharma, Sunil Belsare, B. K. Shukla, Vishal Bhavsar, Mahesh Kushwah
Publikováno v:
IEEE Transactions on Plasma Science. 41:1794-1798
High-power tests on chemical vapor deposited (CVD) diamond window are carried out using 82.6-GHz Gyrotron. To test CVD diamond window with calorimetric dummy load, a matching optic unit is designed and fabricated with special profiled mirrors. The mi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0a44a6aa833089171e0daa14f1979c2f
https://doi.org/10.1109/tps.2013.2251668
https://doi.org/10.1109/tps.2013.2251668
Autor:
Sudhir Tripathi, S.S. Khirwadkar, A. Patel, D. Krishnan, Yashashri Patil, Sunil Belsare, K. P. Singh
Publikováno v:
Journal of Nuclear Materials. 437:326-331
Plasma facing components (PFCs) of divertor will be exposed to steady state and transient heat loads up to 20 MW/m2, during operation of ITER-like plasma fusion device. The critical task in fusion research is to design, fabricate and test of PFCs. To
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2dbd510343acd26b66c11c88bd92fbc9
https://doi.org/10.1016/j.jnucmat.2013.02.014
https://doi.org/10.1016/j.jnucmat.2013.02.014