Zobrazeno 1 - 10
of 24
pro vyhledávání: '"Valentino Di Marcello"'
Autor:
Bradut-Eugen Ghidersa, Bruno Gonfiotti, André Kunze, Valentino Di Marcello, Mihaela Ionescu-Bujor, Xue Zhou Jin, Robert Stieglitz
Publikováno v:
Applied Sciences, Vol 11, Iss 24, p 12010 (2021)
The experimental investigation of a prototypical set-up simulating a loss of flow accident in a helium-cooled breeding blanket first wall mock-up under typical heat load conditions is presented. The experimental campaign reproduces the expected DEMO
Externí odkaz:
https://doaj.org/article/474ef77ec1d541efabad46ba2ac58412
Autor:
Valentino Di Marcello, Riccardo Mereu, Aldo Ianni, Nicola Rossi, David Bravo-Berguño, Frank Calaprice, Attilio Di Giacinto, Antonio Di Ludovico, Andrea Ianni, Lidio Pietrofaccia
Publikováno v:
Journal of Fluids Engineering. 144
The Borexino detector at Gran Sasso National Laboratories (INFN) has obtained extraordinary achievements for solar neutrino and geoneutrino physics during its lifetime. More recently, Borexino has provided the first experimental evidence of the subdo
Publikováno v:
Nuclear Engineering and Design. 321:318-327
Validation and qualification of thermal-hydraulics system codes based on measured plant data are essential for their reliability when applied to nuclear power plant analyses. To this purpose, the Institute for Neutron Physics and Reactor Technology (
Publikováno v:
Nuclear Engineering and Design. 307:284-298
This paper is aimed at the validation and application of the system code ATHLET-CD for the simulation of severe accident phenomena in Boiling Water Reactors (BWR). The corresponding models for core degradation behaviour e.g., oxidation, melting and r
Publikováno v:
Publons
A VTT Fukushima Daiichi Unit 3 (1F3) method for estimation of liquids and consequences of releases (MELCOR) model was modified to simulate the Fukushima Daiichi Unit 2 (1F2) accident. Five simulations were performed using different modeling approache
Publikováno v:
Nuclear Engineering and Design. 288:183-194
Validation and qualification of thermal-hydraulic system codes based on separate effect tests are essential for the reliability of numerical tools when applied to nuclear power plant analyses. To this purpose, the Institute for Neutron Physics and Re
Publikováno v:
Fusion Engineering and Design
In the frame of the development of the equatorial outboard blanket module of the EU DEMO (Demonstration Fusion Power Plant) blanket concepts, the qualification and testing of mock-ups are foreseen by means of different experiments to validate models
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::910f9349ba05f11159123ac316bfdc7c
https://publikationen.bibliothek.kit.edu/1000074344
https://publikationen.bibliothek.kit.edu/1000074344
This chapter summarizes some specific aspects concerning the thermal hydraulics of liquid-fueled molten salt reactors (MSRs), including the presence of an internally heated fluid that serves both as fuel and coolant. Throughout the chapter, in order
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f842481031af97f50823b33ef460f49e
https://doi.org/10.1016/b978-0-08-101126-3.00006-3
https://doi.org/10.1016/b978-0-08-101126-3.00006-3
Autor:
Michel Allibert, Charalampos Andreades, A.S. Bakai, Stephen Boyd, Wayne Boyes, Mariya Brovchenko, Antonio Cammi, Konrad Czerski, Zhimin Dai, Alexey M. Degtyarev, Sylvie Delpech, Lindsay Dempsey, Leslie Dewan, Valentino Di Marcello, Elling Disen, Thomas J. Dolan, I.V. Dulera, Victor Dykin, Lyndon Edwards, L. Berrin Erbay, Yu S. Fedorov, Charles Forsberg, Kazuro Furukawa, Stephan Gottlieb, Sophie Grape, Eduardo D. Greaves, Carl Hellesen, Fabian Herrmann, Daniel Heuer, Yasuo Hirose, Zara Hodgson, Boris Hombourger, Armin Huke, Ahmed Hussein, Yongjin Jeong, Lars Jorgensen, Motoyasu Kinoshita, Esben Klinkby, Jan L. Kloosterman, Jiří Křepel, John Kutsch, Vince Lackowski, Axel Laureau, David LeBlanc, Deokjung Lee, A.A. Lizin, Lelio Luzzi, Mark Massie, Elsa Merle, Andrey A. Myasnikov, Sergii Nichenko, Andreas Pautz, Imre Pázsit, Bent Lauritzen, Alessandro Pini, Leonid I. Ponomarev, Michael Prasser, Magdi Ragheb, A. Rama Rao, Andrei Rineiski, Sean Robertson, Cyril Rodenburg, Götz Ruprecht, Laszlo Sajo-Bohus, Raluca Scarlat, Troels Schønfeldt, Ian Scott, Yoichiro Shimazu, R.K. Sinha, Stephen Smith, Christopher Taylor, S.V. Tomilin, Jan Uhlíř, Evgeny P. Velikhov, P.K. Vijayan, Abdul Waris, Daniel Weißbach, Ritsuo Yoshioka
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::da3894176bd489c9d0991700629800eb
https://doi.org/10.1016/b978-0-08-101126-3.00036-1
https://doi.org/10.1016/b978-0-08-101126-3.00036-1
Publikováno v:
Nuclear Engineering and Design. 276:19-29
The TRANSURANUS fuel performance code was extended in order to take into account large creep strains for the simulation of clad ballooning occurring during loss-of-coolant accidents (LOCA). Additionally, the application range has been assessed. While