Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Janos Bodi"'
Autor:
Ben Lindley, Francisco Álvarez Velarde, Una Baker, Janos Bodi, Paul Cosgrove, Alan Charles, Carlo Fiorina, Emil Fridman, Jiri Krepel, Jean Lavarenne, Konstantin Mikityuk, Evgeny Nikitin, Alexander Ponomarev, Stefan Radman, Eugene Shwageraus, Brendan Tollit
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 9
The objective of this paper is to quantify the coupling effect on the power distribution of sodium-cooled fast reactors (SFRs), specifically the European SFR. Calculations are performed with several state-of-the-art reactor physics and Multiphysics c
Autor:
Michel Allibert, Fatih Aydogan, Janos Bodi, Shridhar K. Chande, Perumal Chellapandi, Lin Chen, Yoshitaka Chikazawa, Luciano Cinotti, Michel Claessens, Gerald Clark, Dahvien Dean, Sylvie Delpech, Nikita Dort-Goltz, Alexey Dragunov, Romney B. Duffey, Indravadan Dulera, Rami S. El-Emam, Seyun Eom, Natalia M. Fialko, Kamiel S. Gabriel, Arnold A. Gad-Briggs, Delphine Gerardin, Enrico Girardi, Filip Grochowina, Joel Guidez, Dohee Hahn, Daniel Heuer, Mohammad Hosseiny, Dan Hughes, Brian Ikeda, Hideki Kamide, Pavel L. Kirillov, Ken Kirkhope, Natalia P. Kozioura, Shigenobu Kubo, Axel Laureau, Laurence K.H. Leung, Mohammed Mahdi, Jennifer McKellar, Elsa Merle, Konstantin Mikityuk, Sarah J. Mokry, Theoklis Nikolaidis, Thambiayah Nitheanandan, Hiroyuki Ohshima, Emmanuel O. Osigwe, Wargha Peiman, Pericles Pilidis, Igor L. Pioro, Roman M. Pioro, Evgen N. Piśmennyi, Roman Popov, Victor G. Razumovskiy, Jovica Riznic, Gilles H. Rodriguez, Eugene Saltanov, Suresh Sampath, Thomas Schulenberg, Ratan K. Sinha, Anton D. Smirnov, Craig F. Smith, Gopala I. Srinivasan, Joao Amaral Teixeira, Georgy V. Tikhomirov, Mark Tsai, Pavel Tsvetkov, Georges Van Goethem, Pallippattu K. Vijayan, Hanqing Xie, Xing L. Yan, Calin Zamfirescu, Dalin Zhang, Constantin O. Zvorykin
Publikováno v:
Handbook of Generation IV Nuclear Reactors ISBN: 9780128205884
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9aabecef8c7e66d4c1f2b08ca1887c3b
https://doi.org/10.1016/b978-0-12-820588-4.09994-1
https://doi.org/10.1016/b978-0-12-820588-4.09994-1
Publikováno v:
Handbook of Generation IV Nuclear Reactors ISBN: 9780128205884
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b4c84f30e2da57d210dc9b3c6735a522
https://doi.org/10.1016/b978-0-12-820588-4.00022-0
https://doi.org/10.1016/b978-0-12-820588-4.00022-0
Publikováno v:
Journal of Nuclear Engineering and Radiation Science
As part of the European sodium fast reactor (ESFR)-safety measures assessment and research tools (SMART) project, safety assessments are being conducted on the updated ESFR design. An important part of the study is the evaluation of the reactor's beh
Publikováno v:
Journal of Nuclear Engineering and Radiation Science
Based on feedback from existing reactors and current projects, the European sodium fast reactor-safety measures assessment and research tools (ESFR-SMART) project proposes an optimization of the secondary circuit with the main aim of improving safety
Publikováno v:
Journal of Nuclear Engineering and Radiation Science
Following up the previous collaborative project on European sodium fast reactor (CP-ESFR project), the European sodium fast reactor—safety measures assessment and research tools (ESFR-SMART project) considers the safety objectives envisaged for gen
Publikováno v:
Journal of Nuclear Engineering and Radiation Science.
In this paper, a reactor core mechanical analysis method is introduced to provide a tool to calculate the reactivity effect of the fuel subassembly displacement in the reactor core which is an important problem for reactor types such as the Sodium-co
Autor:
F. Álvarez-Velarde, Konstantin Mikityuk, Pablo Romojaro, Janos Bodi, Antoine Gerschenfeld, Joel Guidez, U. Diaz-Chiron
Publikováno v:
EPJ Web of Conferences, Vol 247, p 01002 (2021)
Even before Fukushima accident occurred, the safety authorities have required that new power plant designs must take into account beyond design-basis accidents including possible core meltdown. Among the mitigation strategies, the corium retention mu
Autor:
Konstantin Mikityuk, Haileyesus Tsige-Tamirat, Enrico Girardi, Joel Guidez, Janos Bodi, Antoine Gerschenfeld, Aleksander Grah
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 8(1)
The decay heat removal system (DHRS) for the European sodium-cooled fast reactor (ESFR) concept consists of three cooling systems, which provide highly reliable, redundant, and diversified decay heat removal functions. Two of the systems provide a st