Dynamic reliability and risk assessment of the accident localization system of the Ignalina NPP RBMK-1500 reactor von Kopustinskas, V., Augutis, J., Rimkevičius, S.

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Modeling of atmosphere stratification in containments of nuclear power plants using lumped-parameter code von Povilaitis, M., Urbonavičius, E., Rimkevičius, S.

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Safety analysis of beyond design basis accidents in RBMK-1500 reactors von Ušpuras, E., Kaliatka, A., Augutis, J., Rimkevičius, S., Urbonavičius, E., Kopustinskas, V.

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Experimental investigation of pebble beds thermal hydraulic characteristics von Rimkevičius, S., Uspuras, E.

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Scientific inheritance of Eugenijus Ušpuras von Augutis, J., Babilas, E., Dundulis, G., Kaliatka, A., Kaliatka, T., Krikštolaitis, R., Martišauskas, L., Rimkevičius, S., Pabarčius, R., Povilaitis, M., Stankūnas, G., Urbonas, R., Urbonavičius, E.

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Scientific inheritance of Eugenijus Ušpuras von Augutis, J., Babilas, E., Dundulis, G., Kaliatka, A., Kaliatka, T., Krikštolaitis, R., Martišauskas, L., Rimkevičius, S., Pabarčius, R., Povilaitis, M., Stankūnas, G., Urbonas, R., Urbonavičius, E.

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Safety analysis of irradiated RBMK-1500 nuclear fuel transportation in newly developed container von Rimkevičius, S., Ušpuras, E., Dundulis, G., Laurinavičius, D.

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Simulation of Ignalina NPP accident localisation system behaviour employing the RALOC4 code in the case of group distribution header rupture von RIMKEVICIUS, S, URBONAVICIUS, E, CESNA, B

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Integrated failure probability estimation based on structural integrity analysis and failure data: Natural gas pipeline case von Dundulis, Gintautas, Žutautaitė, Inga, Janulionis, Remigijus, Ušpuras, Eugenijus, Rimkevičius, Sigitas, Eid, Mohamed

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Degradation mechanisms and evaluation of failure of gas pipelines von Dundulis, G, Grybenas, A, Janulionis, R, Kriukiene, R, Rimkevicius, S

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Heat transfer to the building structures of the Ignalina NPP accident localisation system von Babilas, E., Rimkevičius, S., Urbonavičius, E.

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COCOSYS code validation against measured data during unintended single main safety valve opening at Ignalina NPP von Urbonavicius, E., Rimkevicius, S.

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Hazard analysis and consequences assessment of gas pipeline rupture and natural gas explosion von USPURAS, E, RIMKEVICIUS, S, POVILAITIS, M, IESMANTAS, T, ALZBUTAS, R

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Reactor cavity and ALS thermal-hydraulic evaluation in the case of fuel channels ruptures at Ignalina NPP von Cesna, B, Rimkevicius, S, Urbonavicius, E, Babilas, E

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Energy production from high level radioactive waste at the Ignalina NPP von Rada, E C, Ragazzi, M, Apostol, T

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RALOC4 code validation against measured data at Ignalina NPP during single Main Safety Valve opening von Urbonavicius, E., Rimkevicius, S.

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Analysis of the hydrogen behaviour in compartments of the Ignalina nuclear power plant von Babilas, E., Urbonavicius, E., Rimkevicius, S., Kaliatka, A.

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Modeling of the TOSQAN test facility with the lumped parameter code COCOSYS von Babilas, E., Urbonavicius, E., Rimkevicius, S.

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Analyses of severe accident scenarios in RBMK-1500 von Kaliatka, A., Rimkevicius, S., Uspuras, E., Urbonavicius, E.

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Simulation of the hydrogen distribution in the confinement of the Ignalina nuclear power plant von Babilas, E., Urbonavicius, E., Rimkevicius, S.

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