Zobrazeno 1 - 10
of 36
pro vyhledávání: '"Joydipta Banerjee"'
Publikováno v:
Nuclear Fuel Cycle ISBN: 9789819909483
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::67420814cdc364ccaaf2cb982672b4ac
https://doi.org/10.1007/978-981-99-0949-0_3
https://doi.org/10.1007/978-981-99-0949-0_3
Autor:
P.G. Behere, N. Keskar, Manisha P Gupta, Suman Neogy, Joydipta Banerjee, Ranu Bhatt, Aniruddha Kumar, Debabrata Biswas
Publikováno v:
Lasers in Manufacturing and Materials Processing. 6:158-172
Joining of materials is an essential process step in manufacturing industry. The need to weld dissimilar thin materials is growing lately with applications in MEMS devices involving different materials. Welding of thin dissimilar materials is a chall
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::994d9259fd4aada6178597a514d3a39e
https://doi.org/10.1007/s40516-019-00088-w
https://doi.org/10.1007/s40516-019-00088-w
Publikováno v:
Journal of Nuclear Materials. 516:1-10
U-33 at.% Mo (16.8 wt.%) metallic fuel is a candidate material for metallic fuel Fast Reactor. One of the life-limiting factors of fast breeder reactor clad is the fuel clad chemical interaction due to formation of low melting eutectics between U and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a28df753ffb547e2c79069e18aeb6edd
https://doi.org/10.1016/j.jnucmat.2019.01.011
https://doi.org/10.1016/j.jnucmat.2019.01.011
Publikováno v:
Journal of Nuclear Materials. 513:16-32
The chemical interaction of U−Zr based fast reactor fuel with T91 grade steel cladding was investigated by employing DTA (differential thermal analysis), diffusion couple experiment and SEM/EDS, SEM/EBSD analyses. The DTA results revealed a strong
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4a1f4226d4e8ad6d3f917203289d2147
https://doi.org/10.1016/j.jnucmat.2018.10.041
https://doi.org/10.1016/j.jnucmat.2018.10.041
Publikováno v:
Journal of Molecular Structure. 1264:133206
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5e01f5fd342ebf3624ccebde0a43816f
https://doi.org/10.1016/j.molstruc.2022.133206
https://doi.org/10.1016/j.molstruc.2022.133206
Autor:
Chiranjit Nandi, Amrit Prakash, A. K. Tyagi, Sudhir Mishra, Koushik Bhandari, Joydipta Banerjee, Shovit Bhattacharya, Vinita Grover
Publikováno v:
Journal of Nuclear Materials. 508:82-91
The investigations in phase behavior of plutonia-based system are generally carried out by employing surrogates for the ease of handling. However, the curiosity to understand the phase relations by employing PuO2 directly instead of surrogates led to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::710817630fb37df53f0173747821c311
https://doi.org/10.1016/j.jnucmat.2018.05.009
https://doi.org/10.1016/j.jnucmat.2018.05.009
Publikováno v:
Journal of Nuclear Materials. 504:234-250
Uranium-rich U–Zr–Nb alloy is considered as a good alternative fuel for fast reactors from the perspective of excellent dimensional stability and desired thermo-physical properties to achieve higher burnup. Detailed investigations related to the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::215f9e6fd4c08c6e185cd2f5a3a86eac
https://doi.org/10.1016/j.jnucmat.2018.03.044
https://doi.org/10.1016/j.jnucmat.2018.03.044
Publikováno v:
Journal of Nuclear Materials. 499:272-283
Cermet fuel combines beneficial properties of both ceramic and metal and attracts global interest for research as a candidate fuel for nuclear reactors. In the present study, U matrix PuC/PuN/PuO2 cermet for fast reactor have been fabricated on labor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2293d85b3de079a723c2a011305cd6fd
https://doi.org/10.1016/j.jnucmat.2017.11.010
https://doi.org/10.1016/j.jnucmat.2017.11.010
Publikováno v:
Spectrochimica Acta Part B: Atomic Spectroscopy. 132:1-7
Advanced Heavy Water Reactor (AHWR) grade (Th-U)O 2 fuel sample and Simulated High Burn-Up Nuclear Fuels (SIMFUEL) samples mimicking the 28 and 43 GWd/Te irradiated burn-up fuel were studied using laser-induced breakdown spectroscopy (LIBS) setup in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6c57be2473eb861f46e13d9be129c47c
https://doi.org/10.1016/j.sab.2017.03.012
https://doi.org/10.1016/j.sab.2017.03.012
Autor:
Chiranjit Nandi, Amrit Prakash, Joydipta Banerjee, Dheeraj Jain, K.B. Khan, A. K. Tyagi, K. Krishnan, Vinita Grover
Publikováno v:
Materials & Design, Vol 121, Iss, Pp 101-108 (2017)
Exploring the structural and thermophysical behaviour of Nd-Substituted ZrO2 is vital in context of matrices for minor actinide transmutation. Hence, phase relations have been studied in this system using high temperature sintered samples prepared by
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2d247e9893d4edf1690cbd6cc0f11121
https://doi.org/10.1016/j.matdes.2017.02.030
https://doi.org/10.1016/j.matdes.2017.02.030