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pro vyhledávání: '"F. Tantillo"'
Akademický článek
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Akademický článek
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Publikováno v:
Nuclear Engineering and Design. 329:167-176
The HTR code package (HCP) allows for the simulation of several safety-related aspects of a High Temperature Reactor core in a highly integrated manner. HCP currently couples the thermo-fluid dynamics and time dependent neutronics code MGT, the spect
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::21c9272d17953ea797bf78a9b98b9e2e
https://doi.org/10.1016/j.nucengdes.2017.11.044
https://doi.org/10.1016/j.nucengdes.2017.11.044
Akademický článek
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Publikováno v:
Nuclear Engineering and Design. 379:111174
Nowadays, nuclear reactor safety simulations of real nuclear plants are still performed using approximated system codes which rely on one-dimensional lumped-parameters or subchannel methods. Many of these one-dimensional codes are not able to fully s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::30a49ee6f6a22f1012c1b8364d19bf6f
https://doi.org/10.1016/j.nucengdes.2021.111174
https://doi.org/10.1016/j.nucengdes.2021.111174
Publikováno v:
Nuclear Engineering and Design. 306:154-159
The problem of calculating the amounts of a coupled nuclide system varying with time especially when exposed to a neutron flux is a well-known problem and has been addressed by a number of computer codes. These codes cover a broad spectrum of applica
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2dca35d71ce9428a1f7ec46e718b95bc
https://doi.org/10.1016/j.nucengdes.2016.03.016
https://doi.org/10.1016/j.nucengdes.2016.03.016
Publikováno v:
Nuclear Engineering and Design. 306:145-153
To simulate the different aspects of High Temperature Reactor (HTR) cores, a variety of specialized computer codes have been developed at Forschungszentrum Julich (IEK-6) and Aachen University (LRST) in the last decades. In order to preserve knowledg
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5fc0a478bf569f542ecc5a88bd9f3a47
https://doi.org/10.1016/j.nucengdes.2016.04.028
https://doi.org/10.1016/j.nucengdes.2016.04.028
Publikováno v:
Nuclear Engineering and Design. 362:110603
The HTR Code Package (HCP) is a code system well suited to simulate most of relevant aspects related to the design and the safety assessment of a high temperature gas reactor in a consistent and integrated way. HCP has seen the addition of new functi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::58cd17c6b029533c7a7c57692febe50a
https://doi.org/10.1016/j.nucengdes.2020.110603
https://doi.org/10.1016/j.nucengdes.2020.110603
Autor:
De Luca, Daniele1,2 (AUTHOR) daniele.deluca@unisob.na.it, Piredda, Roberta3 (AUTHOR), Scamardella, Sara1 (AUTHOR), Martelli Castaldi, Monica1 (AUTHOR), Troisi, Jacopo4,5 (AUTHOR), Lombardi, Martina4,6 (AUTHOR), De Castro, Olga2,7 (AUTHOR), Cennamo, Paola1 (AUTHOR) paola.cennamo@unisob.na.it
Publikováno v:
Scientific Reports. 11/1/2024, Vol. 14 Issue 1, p1-12. 12p.
Autor:
Vlachou, Mikela1 (AUTHOR) vlachoumikvet@uth.gr, Pexara, Andreana1 (AUTHOR) apexara@vet.uth.gr, Solomakos, Nikolaos1 (AUTHOR) agovaris@vet.uth.gr, Govaris, Alexander1 (AUTHOR), Palaiogiannis, Dimitrios2 (AUTHOR) dipaleog@med.uth.gr, Athanasiadis, Vassilis2 (AUTHOR) vaathanasiadis@uth.gr, Lalas, Stavros I.2 (AUTHOR) slalas@uth.gr
Publikováno v:
Toxins. Oct2024, Vol. 16 Issue 10, p421. 11p.