Egidijus Babilas
Energy Institute
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Featured researches published by Egidijus Babilas.
Science and Technology of Nuclear Installations | 2015
Egidijus Babilas; Eugenijus Uspuras; Sigitas Rimkevicius; Gintautas Dundulis; Mindaugas Vaisnoras
The decommissioning of nuclear facilities requires adequate planning and demonstration that dismantling and decontamination activities can be conducted safely. Existing safety standards require that an appropriate safety assessment be performed to support the decommissioning plan for each facility (International Atomic Energy Agency, 2006). This paper presents safety assessment approach used in Lithuania during the development of the first dismantling and decontamination project for Ignalina NPP. The paper will mainly focus on the identification and assessment of the hazards raised due to dismantling and decontamination activities at Ignalina Nuclear Power Plant and on the assessment of the nonradiological and radiological consequences of the indicated most dangerous initiating event. The drop of heavy item was indicated as one of most dangerous initiating events for the discussed Ignalina Nuclear Power Plant dismantling and decontamination project. For the analysis of the nonradiological impact the finite element model for the load drop force calculation was developed. The radiological impact was evaluated in those accident cases which would lead to the worst radiological consequences. The assessments results show that structural integrity of the building and supporting columns of building structures will be maintained and radiological consequences are lower than the annual regulatory operator dose limit.
Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition | 2006
Egidijus Babilas; Egidijus Urbonavičius; Sigitas Rimkevicius
Accident Localisation System (ALS) of Ignalina NPP is a “pressure suppression” type confinement, which protects the population, employees and environment from the radiation hazards. According to the Safety Analysis Report for Ignalina NPP ∼110 m3 of hydrogen is released to ALS compartments during the Maximum Design Basis Accident. However in case of beyond design basis accident, when the oxidation of zirconium starts, the amount of generated hydrogen could be significantly higher. If the volume concentration of hydrogen in the compartment reaches 4%, there is a possibility for a combustible mixture to appear. To prevent the possible hydrogen accumulation in the ALS of the Ignalina NPP during an accident the H2 control system is installed. The results of the performed analysis derived the places of the possible H2 accumulation in the ALS compartments during the transient processes and assessed the mixture combustibility in these places for a beyond design basis accident scenario. Such analysis of H2 distribution in the ALS of Ignalina NPP in case of BDBA was not performed before.Copyright
Nuclear Engineering and Design | 2004
B Cesna; Sigitas Rimkevicius; Egidijus Urbonavičius; Egidijus Babilas
Nuclear Engineering and Design | 2012
A. Kontautas; Egidijus Babilas; Egidijus Urbonavičius
Annals of Nuclear Energy | 2016
Sigitas Rimkevicius; Mindaugas Vaisnoras; Egidijus Babilas; Eugenijus Uspuras
Nuclear Engineering and Design | 2013
Mantas Povilaitis; Egidijus Urbonavičius; Sigitas Rimkevicius; Egidijus Babilas
Progress in Nuclear Energy | 2015
Egidijus Babilas; Boris Brendebach
Nuclear Engineering and Technology | 2018
Egidijus Babilas; Pavel Dokucajev; Darius Janulevicius; Aleksej Markelov; Raimondas Pabarčius; Sigitas Rimkevicius; Eugenijus Uspuras; Mindaugas Vaisnoras
Progress in Nuclear Energy | 2015
Eugenijus Uspuras; Sigitas Rimkevicius; Egidijus Babilas
Archive | 2005
Egidijus Babilas; Egidijus Urbonavièius; Sigitas Rimkevièius