Zobrazeno 1 - 10
of 36
pro vyhledávání: '"Giacomino Bandini"'
Autor:
Giacomino Bandini, Paride Meloni, Massimiliano Polidori, Maddalena Casamirra, Francesco Castiglia, Mariarosa Giardina
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2008 (2008)
The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of the European EUROTRANS Integral Project. In normal opera
Externí odkaz:
https://doaj.org/article/21f245bc3a474326868b7d05ddbb6948
Autor:
T. Hollands, M. Stempniewicz, M. Barnak, P. Vokac, D. Angelova, M. Behler, R. Dagan, Claudia López, Algirdas Kaliatka, G.L. Horvath, D.F. Da Cruz, Ivo Kljenak, P. Matejovic, B.S. Jäckel, O. Kotsuba, Giacomino Bandini, M. Matkovic, Martin Steinbrück, Yu. Vorobyov, Luis E. Herranz, V. Vileiniskis, F. Rocchi, O. Zhabin, Olivia Coindreau, R. Thomas, D.C. Visser, F. Alcaro, Terttaliisa Lind, K. Mancheva, S. Ederli, P. Drai
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2018, 120, pp.880-887. ⟨10.1016/j.anucene.2018.06.043⟩
Annals of Nuclear Energy, Elsevier Masson, 2018, 120, pp.880-887. ⟨10.1016/j.anucene.2018.06.043⟩
International audience; Spent fuel pools (SFPs) are large structures equipped with storage racks designed to temporarily storeirradiated nuclear fuel removed from the reactor. SFP severe accidents have long been considered ashighly improbable since t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1a141d57553ae7b281b6f0a491fb6d3e
https://doi.org/10.1016/j.anucene.2018.06.043
https://doi.org/10.1016/j.anucene.2018.06.043
Autor:
V. Matuzas, M. Haselbauer, S. Ederli, Laurent Laborde, Luis E. Herranz, A. Flores y Flores, Sara Perez-Martin, C. Berna, N. Girault, Giacomino Bandini, Werner Pfrang
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2018, 119, pp.427-439. ⟨10.1016/j.anucene.2017.12.016⟩
Annals of Nuclear Energy, Elsevier Masson, 2018, 119, pp.427-439. ⟨10.1016/j.anucene.2017.12.016⟩
International audience; This paper describes the work performed within the WP2.1 of the JASMIN project to validate the thermal-hydraulic models of ASTEC-Na code. The experiments used for validation purposes have been BI1, E8 and EFM1, carried out in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a14f32c36866b28d9d2248311c800f13
https://doi.org/10.1016/j.anucene.2017.12.016
https://doi.org/10.1016/j.anucene.2017.12.016
Publikováno v:
Nuclear Engineering and Design. 307:181-187
This paper deals with the assessment of an innovative decay heat removal system for the MYRRHA reactor, based on the analysis of the selected transients with two different system codes. The application to liquid metal cooled reactors has the disadvan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c0ab000857cbc15946d7f62deb3d0199
https://doi.org/10.1016/j.nucengdes.2016.07.017
https://doi.org/10.1016/j.nucengdes.2016.07.017
Autor:
Sara Perez-Martin, S. Ederli, A. Flores y Flores, L. Ammirabile, Werner Pfrang, Giacomino Bandini, V. Matuzas
Publikováno v:
Annals of Nuclear Energy. 94:175-188
This paper presents simulation results of the CABRI BI1 test using the code ASTEC-Na, currently under development, as well as a comparison of the results with available experimental data. The EU-JASMIN project (7th FP of EURATOM) centres on the devel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8e3415102e92946dd3e768c4455bb444
https://doi.org/10.1016/j.anucene.2016.02.032
https://doi.org/10.1016/j.anucene.2016.02.032
Publikováno v:
Nuclear Engineering and Design. 281:39-50
In the frame of THINS Project of the 7th Framework EU Program on Nuclear Fission Safety, some experiments were carried out on the large scale LBE-cooled CIRCE facility at the ENEA/Brasimone Research Center to investigate relevant safety aspects assoc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cc0326661d5f7d76ce45f3aae2198e09
https://doi.org/10.1016/j.nucengdes.2014.11.005
https://doi.org/10.1016/j.nucengdes.2014.11.005
Autor:
M. Schyns, L. Andriolo, Rui Li, Fabrizio Gabrielli, Giacomino Bandini, Massimo Sarotto, D. Castelliti, E. Bubelis, Andrei Rineiski, Liancheng Guo, X-N. Chen, F. Belloni
The presented studies are carried out within the European 7th framework project MAXSIMA, in which the MYRRHA reactor, which stands for Multi-purpose hYbrid Research Reactor for High-tech Applications, developed at SCK-CEN (Belgian Nuclear Research Ce
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::772dbe7e3efc4ea9c66c45c24abd63be
https://www.scopus.com/inward/record.uri?eid=2-s2.0-85027685331&doi=10.1016/j.anucene.2017.08.021&partnerID=40&md5=1dd3dc3ac6ecaae30e2f09872599850d
https://www.scopus.com/inward/record.uri?eid=2-s2.0-85027685331&doi=10.1016/j.anucene.2017.08.021&partnerID=40&md5=1dd3dc3ac6ecaae30e2f09872599850d
Autor:
Michael Buck, Ivo Kljenak, Siegfried Arndt, A. Bleyer, Bohumir Kujal, Thimo Brähler, P. Chatelard, Giacomino Bandini, B. Atanasova
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2014, 272, pp.136-151. ⟨10.1016/j.nucengdes.2013.10.013⟩
Nuclear Engineering and Design, Elsevier, 2014, 272, pp.136-151. ⟨10.1016/j.nucengdes.2013.10.013⟩
International audience; Significant efforts are put into the assessment of the severe accident integral code ASTEC, jointly developed since several years by IRSN and GRS, either through comparison with results of the most important international expe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5438b8babda0728e1209f556e2e8aed5
https://doi.org/10.1016/j.nucengdes.2013.10.013
https://doi.org/10.1016/j.nucengdes.2013.10.013
Publikováno v:
Nuclear Engineering and Design. 241:4662-4671
The PERSEO experimental program was performed in the framework of a domestic research program on innovative safety systems with the purpose to increase the reliability of passive decay heat removal systems implementing in-pool heat exchangers. The co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3cdc3f752ce6f74eb5001f60328b30fe
https://doi.org/10.1016/j.nucengdes.2011.02.034
https://doi.org/10.1016/j.nucengdes.2011.02.034
Publikováno v:
Nuclear Engineering and Design. 241:1165-1171
Among the next generation of nuclear reactors, well-known as Gen-IV, the LFR (Lead Fast Reactor) is one of the most promising advanced reactor able to comply the principles of sustainability, economics, safety and proliferation resistance. The ELSY p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8cf91d1a551b12c98364972d5af6d20d
https://doi.org/10.1016/j.nucengdes.2010.04.034
https://doi.org/10.1016/j.nucengdes.2010.04.034