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Publikováno v:
Research in Nondestructive Evaluation. 24:223-234
Dispersion type plate fuel elements were fabricated with U3Si2 dispersoids in aluminium matrix and clad in Al-alloy for the modified core of APSARA reactor by standard picture framing technique followed by hot roll bonding operation. In general aroun
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d852a4fe4efb4576e112848a5c01802d
https://doi.org/10.1080/09349847.2013.800620
https://doi.org/10.1080/09349847.2013.800620
Publikováno v:
Journal of Nuclear Materials. 427:12-17
CERMET fuel with either PuO 2 or enriched UO 2 dispersed in uranium metal matrix has a strong potential of becoming a fuel for the liquid metal cooled fast breeder reactors (LMR’s). In fact it may act as a bridge between the advantages and disadvan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1d808b999f557c09303155c0b6297902
https://doi.org/10.1016/j.jnucmat.2012.04.008
https://doi.org/10.1016/j.jnucmat.2012.04.008
Publikováno v:
Journal of Alloys and Compounds. 506:253-262
Over the past decade considerable efforts have been put by many fuel designers to develop low enriched uranium (LEU 235 ) base U–Mo alloy as a potential fuel for core conversion of existing research and test reactors which are running on high enric
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a72706957630e59991504d5c64162a0a
https://doi.org/10.1016/j.jallcom.2010.06.187
https://doi.org/10.1016/j.jallcom.2010.06.187
Publikováno v:
Journal of Alloys and Compounds. 491:753-760
Over the years U 3 Si 2 compound dispersed in aluminium matrix has been used successfully as the potential low enriched uranium (LEU 235 ) base dispersion fuel for use in new research and test reactors and also for converting high enriched uranium (H
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::23bb6ab5e1e448b1f199715151c04e93
https://doi.org/10.1016/j.jallcom.2009.11.060
https://doi.org/10.1016/j.jallcom.2009.11.060
Publikováno v:
Journal of Alloys and Compounds. 473:238-244
Most of the research and test reactors worldwide have undergone core conversion from high enriched uranium base fuel to low enriched uranium base fuel under the Reduced Enrichment for Research and Test Reactor (RERTR) program, which was launched in t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e7f276c8b96367a8a51812cf9db24819
https://doi.org/10.1016/j.jallcom.2008.05.061
https://doi.org/10.1016/j.jallcom.2008.05.061
Publikováno v:
Journal of Nuclear Materials. 383:196-200
The Indian research reactor APSARA, which uses HEU based UAl 3 fuel dispersed in aluminium matrix, is to undergo core conversion to LEU based U 3 Si 2 dispersoid in aluminium matrix fuel. Work has been initiated at BARC, to prepare uranium silicide (
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c82a8a12fb64c8ef06b5c5847987d523
https://doi.org/10.1016/j.jnucmat.2008.08.046
https://doi.org/10.1016/j.jnucmat.2008.08.046
Publikováno v:
Transactions of the Indian Institute of Metals. 61:115-120
Most of the research and test reactors worldwide have undergone core conversion from high enriched uranium base fuel to low enriched uranium base fuel under the Reduced Enrichment for Research and Test Reactor (RERTR) programme, which was launched in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::956e200e5a8b811df977ad296e089d9f
https://doi.org/10.1007/s12666-008-0035-0
https://doi.org/10.1007/s12666-008-0035-0
Publikováno v:
Journal of Nuclear Materials. 335:462-470
ThO2 containing around 2–3% 233UO2 is the proposed fuel for the forthcoming Indian Advanced Heavy Water Reactor (AHWR). This fuel is prepared by powder metallurgy technique using ThO2 and U3O8 powders as the starting material. The densification beh
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::26274e9bd79500353a7671c0789cb384
https://doi.org/10.1016/j.jnucmat.2004.08.003
https://doi.org/10.1016/j.jnucmat.2004.08.003
Autor:
H.S. Kamath, K.B. Khan, T.R.G. Kutty, Joydipta Banerjee, P.V. Hegde, A.K. Sengupta, Sanjib Majumdar
Publikováno v:
Journal of Nuclear Materials. 327:211-219
A master sintering curve for ThO 2 containing 0.5 wt% CaO has been constructed with the help of combined-stage sintering model. The concept of the master sintering curve (MSC) has been used to calculate the activation energy for sintering for the abo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae9ac433f9dec8f43e42c5855f8e215e
https://doi.org/10.1016/j.jnucmat.2004.02.007
https://doi.org/10.1016/j.jnucmat.2004.02.007