Zobrazeno 1 - 10
of 83
pro vyhledávání: '"E., Rajendra Kumar"'
Publikováno v:
In Fusion Engineering and Design October 2018 135 Part A:102-109
Autor:
Atchutuni, Sarada Sree, Saraswat, Abhishek, Sasmal, Chandra Sekhar, Verma, S., Prajapati, Ashok K., Jaiswal, Ankur, Gupta, Sandeep, Chauhan, Jignesh, Pandya, Karishma B., Makwana, Mayank, Tailor, Hardik, Agravat, Hemang S., P., Prasad Rao, E., Rajendra Kumar
Publikováno v:
In Fusion Engineering and Design July 2018 132:52-59
Publikováno v:
Fusion Engineering and Design. 145:87-93
Institute for Plasma Research (IPR) is developing an Experimental Helium Cooling Loop (EHCL) as a part of R&D activities in fusion blanket technologies. This system is designed to test various nuclear fusion blanket mock-ups. The primary loop is desi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::70683dc581485265ff2f15c8fa8db00e
https://doi.org/10.1016/j.fusengdes.2019.05.015
https://doi.org/10.1016/j.fusengdes.2019.05.015
Autor:
G.K. Dey, E. Rajendra Kumar, S. Bhattacharya, Surinder Kumar, Shiju Sam, Atik Mistry, Santosh Kumar, Narender Singh
Publikováno v:
Fusion Engineering and Design. 136:771-776
The conceptual design of the Indian Lead Lithium Ceramic Breeder (LLCB) Test Blanket Module (TBM) First Wall (FW) presents a single U-shaped component made of IN-RAFM steel having 65 square channels of 20 mm × 20 mm running along the toroidal and ra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::27011f7325ec0143cd2a62e9de9079fb
https://doi.org/10.1016/j.fusengdes.2018.04.007
https://doi.org/10.1016/j.fusengdes.2018.04.007
Publikováno v:
Fusion Engineering and Design. 135:102-109
Corrosion study of IN-RAFM (India specific reduced activation ferritic martensitic) steel with static lead-lithium, Pb-16Li has been carried out at 550 °C for different time durations, 2500, 5000 and 9000 h. Flat and tensile IN-RAFM samples were exp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0e933f8b88966caf7cfcc3497dc73d03
https://doi.org/10.1016/j.fusengdes.2018.07.015
https://doi.org/10.1016/j.fusengdes.2018.07.015
Publikováno v:
Fusion Engineering and Design. 134:51-61
The First Wall (FW) of Indian Lead Lithium Ceramic Breeder (LLCB) Test Blanket Module (TBM) is a U-shaped structure made of India specific Reduced Activation Ferritic Martensitic Steel (IN-RAFMS). As the FW is directly exposed to high heat flux from
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3abdb01c9f7ab4343e2e2ba262b1101b
https://doi.org/10.1016/j.fusengdes.2018.06.019
https://doi.org/10.1016/j.fusengdes.2018.06.019
Publikováno v:
Fusion Engineering and Design. 132:119-126
Indian Reduced Activation Ferritic Martensitic Steel (IN-RAFMS) has been selected as the reference structural material for Lead-Lithium Ceramic Breeder Test Blanket Module (LLCB TBM). Qualification requirements for the selected structural material in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6e0b2812f61eaaae4e3d340c6f69dfcc
https://doi.org/10.1016/j.fusengdes.2018.05.067
https://doi.org/10.1016/j.fusengdes.2018.05.067
Autor:
Mayank Makwana, Sandeep Gupta, Sarada Sree Atchutuni, Hemang S. Agravat, Sudheer Verma, C.S. Sasmal, Karishma B. Pandya, Abhishek Saraswat, Ashok K. Prajapati, Hardik Tailor, Jignesh Chauhan, P. Prasad Rao, Ankur Jaiswal, E. Rajendra Kumar
Publikováno v:
Fusion Engineering and Design. 132:52-59
Corrosion experiments were carried out in a pump driven loop, exposing IN-RAFM (India specific Reduced Activation Ferritic Martensitic) steel samples to lead-lithium, Pb-16Li. In this loop, flat and tensile samples, made of IN-RAFM steel were exposed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c3be7dfc47cd0a265c79a276746df5ed
https://doi.org/10.1016/j.fusengdes.2018.05.020
https://doi.org/10.1016/j.fusengdes.2018.05.020
Autor:
Jignesh Chauhan, Shiju Sam, Shaju K. Albert, N.N. Singh, C.S. Sasmal, H.M. Tailor, Ashokkumar Prajapati, A.N. Mistry, K. Laha, Saroja Saibaba, A.K. Bhaduri, E. Rajendra Kumar
Publikováno v:
Fusion Engineering and Design. 125:263-268
India is developing the Lead Lithium Ceramic Breeder Test Blanket Module (LLCB TBM) for in-situ experiments in ITER. India-specific Reduced Activation Ferritic-Martensitic (IN-RAFM) steel is the chosen structural material for the fabrication of LLCB
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1c3703857a184cdec482bffa0c5be875
https://doi.org/10.1016/j.fusengdes.2017.07.010
https://doi.org/10.1016/j.fusengdes.2017.07.010
Publikováno v:
Fusion Engineering and Design. 124:710-718
One of the key missions of ITER is to test and validate the various design concepts of tritium breeding blankets relevant to a power-producing reactor like DEMO. India is developing lead-lithium cooled ceramic breeder (LLCB) test blanket module (TBM)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::36bee1ac86615cfa9b6e270cdc83cac4
https://doi.org/10.1016/j.fusengdes.2017.05.097
https://doi.org/10.1016/j.fusengdes.2017.05.097