Zobrazeno 1 - 10
of 21
pro vyhledávání: '"G. Melese-d'Hospital"'
Autor:
G. Melese-d'Hospital, R.H. Simon
Publikováno v:
Nuclear Engineering and Design. 40:5-12
Most gas-cooled fast breeder reactor (GCFR) programs in Europe and the US are now coordinated and focused on a 300 MW(e) GCFR demonstration plant program. Except for venting and artificial surface roughening, GCFR fuel is similar to liquid metal fast
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a694b1ebc4c1644c50f27cdb4780156f
https://doi.org/10.1016/0029-5493(77)90147-9
https://doi.org/10.1016/0029-5493(77)90147-9
Autor:
G. Melese-d'Hospital, C.L. Rickard
Publikováno v:
Annals of Nuclear Energy. 5:281-285
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a48e0c30b89bea874ac939de95af8e7e
https://doi.org/10.1016/0306-4549(78)90013-0
https://doi.org/10.1016/0306-4549(78)90013-0
Autor:
G.R Hopkins, G Melese-d'Hospital
Publikováno v:
Nuclear Engineering and Design. 26:215-230
Basic equations relating temperatures, pressure drop, power generation and geometry are derived for cooling the vaccum wall and blanket regions of a fusion reactor with pressurized helium. Numerical results are presented for two cases which are appli
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3d469d517b8dd9054ac7b336c9090fb8
https://doi.org/10.1016/0029-5493(74)90057-0
https://doi.org/10.1016/0029-5493(74)90057-0
Autor:
G. MeLese-D'Hospital
Publikováno v:
Nuclear Engineering and Design. 7:322-333
Simple relationships between dimensionless core parameters have been derived for the case where the maximum internal fuel temperature is fixed. The linear rating is found to be nearly proportional to the difference between maximum fuel and coolant te
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dfbdf9d8873334462a5c07923822a75b
https://doi.org/10.1016/0029-5493(68)90065-4
https://doi.org/10.1016/0029-5493(68)90065-4
Autor:
G. Melese-d'Hospital
Publikováno v:
Nuclear Engineering and Design. 12:153-166
In all-ceramic fuel elements for high temperature gas-cooled reactors, an unfueled moderator spine is often surrounded by a fuel compact consisting of a dispersion of fuel and fertile material in a moderator matrix with a ceramic cladding. For given
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ab35762dd4ffb73cf7d6d6372f9fbc59
https://doi.org/10.1016/0029-5493(70)90004-x
https://doi.org/10.1016/0029-5493(70)90004-x
Autor:
G. Melese-d'Hospital
Publikováno v:
Nuclear Science and Engineering. 42:64-68
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::57da47c56cdc502b61674790f8403c4e
https://doi.org/10.13182/nse70-a19328
https://doi.org/10.13182/nse70-a19328
Autor:
P. Fortescue, G. Melese-D'Hospital
Publikováno v:
Proceedings of the Institution of Mechanical Engineers, Conference Proceedings. 181:9-16
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6366cc37967a5ade96e387ce4fd0d8ea
https://doi.org/10.1243/pime_conf_1966_181_165_02
https://doi.org/10.1243/pime_conf_1966_181_165_02
Autor:
G. Melese-d’Hospital
Publikováno v:
Nuclear Science and Engineering. 35:165-175
If the coolant mass flow were constant across the core, the coolant temperature rise would be proportional to the channel power. But, without orificing, the coolant mass flow in the hot channel is ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::51e1f519392fcb1e8ee731af0883b8fe
https://doi.org/10.13182/nse69-a21132
https://doi.org/10.13182/nse69-a21132
Autor:
G. Melese-d’Hospital
Publikováno v:
Nuclear Science and Engineering. 50:83-85
A simple merit index has been derived to compare potential improvements in gas-cooled nuclear reactor cores, such as artificial surface roughening of the fuel rods. For given pumping-to-thermal pow...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fda2eadab432af68e0c7dac634a55e30
https://doi.org/10.13182/nse73-a22594
https://doi.org/10.13182/nse73-a22594
High-Temperature Gas-Cooled Reactor (HTGR) prototypes with a conventional steam cycle have been in operation since 1967; commercial stations are now starting or are under construction. The high helium temperature can also be used in a direct gas turb
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0662ecd993af25e5fb9818661a5eacac
https://doi.org/10.1016/b978-0-08-019610-7.50070-1
https://doi.org/10.1016/b978-0-08-019610-7.50070-1
