Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Piotr Mazgaj"'
Publikováno v:
Energies, Vol 14, Iss 16, p 4884 (2021)
In this study, uncertainty and sensitivity analyses were performed with MELCOR 2.2.18 to study the hydrogen generation (figure-of-merit (FoM)) during the in-vessel phase of a severe accident in a light water reactor. The focus of this work was laid o
Externí odkaz:
https://doaj.org/article/2d4292874e4d4c8fa76916480d99fc61
Publikováno v:
Proc. ICONE28-POWER2020-28th Conf. on Nuclear Engineering Joint collocated with the ASME 2020 Power Conf.
Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering
Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering
The paper studies influence the ageing effects on the failure of a Reactor Pressure Vessel (RPV) during a severe accident with a core meltdown in a Nuclear Power Plant (NPP). The studied plant is a generic high-power Generation III Pressurized Water
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::af994fd42872122608b9359129d8f46a
Publikováno v:
Procedia Engineering. 157:333-340
This paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuclear Power Plant Westinghouse PWR reactor.Two thermal-hydraulic system codes were applied: RELAP5 and CATHARE 2 to simulate steady state conditions and a tran
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::930f88a69a8dd422dba5b896a0678010
https://doi.org/10.1016/j.proeng.2016.08.374
https://doi.org/10.1016/j.proeng.2016.08.374
Publikováno v:
Nuclear Engineering and Design. 289:8-18
In this paper the results of severe accident simulations for the EPR reactor in the case of loss of offsite power combined with total failure of all diesel generators (total loss of AC power) are presented. Calculations were performed with MELCOR 2.1
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::12f1ba63eeb168324b97d34f1d14a617
https://doi.org/10.1016/j.nucengdes.2015.03.020
https://doi.org/10.1016/j.nucengdes.2015.03.020
Publikováno v:
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2016, 2, pp.1. ⟨10.1051/epjn/e2015-50020-7⟩
EPJ Nuclear Sciences & Technologies, Vol 2, p 1 (2016)
EPJ N-Nuclear Sciences & Technologies, 2016, 2, pp.1. ⟨10.1051/epjn/e2015-50020-7⟩
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2016, 2, pp.1. ⟨10.1051/epjn/e2015-50020-7⟩
EPJ Nuclear Sciences & Technologies, Vol 2, p 1 (2016)
EPJ N-Nuclear Sciences & Technologies, 2016, 2, pp.1. ⟨10.1051/epjn/e2015-50020-7⟩
International audience; Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant design and operation. In the field of Loss Of Coolant Accident, evolutions of the regulations are discussed in various countries ta
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9f7b96eccb74062427b7febe017a2ea5
https://hal-cea.archives-ouvertes.fr/cea-02305417/file/Maz.pdf
https://hal-cea.archives-ouvertes.fr/cea-02305417/file/Maz.pdf
Autor:
Piotr Mazgaj, Piotr Darnowski, Aleksej Kaszko, Javier Hortal, Milorad Dusic, Rafael Mendizábal, Fernando Pelayo
Publikováno v:
Reliability Engineering and System Safety
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bd7254b81e652468f8aa5a70ad1d6f68