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Search Results - Pabarčius, Raimondas
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The impact of fuel depletion scheme within SCALE code on the criticality of spent fuel pool with RBMK fuel assemblies
by
Slavickas, Andrius
,
Kaliatka, Tadas
,
Pabarčius, Raimondas
,
Rimkevičius, Sigitas
Published in
Nuclear engineering and technology
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Uncertainty and Sensitivity Analysis of Void Reactivity Feedback for 3D BWR Assembly Model
by
Uspuras, Eugenijus
,
Tonkūnas, Aurimas
,
Pabarčius, Raimondas
,
Slavickas, Andrius
Published in
Science and technology of nuclear installations
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Neutron Transport Simulations of RBMK Fuel Assembly Using Multigroup and Continuous Energy Data Libraries within the SCALE Code
by
Slavickas, Andrius
,
Pabarčius, Raimondas
,
Tonkūnas, Aurimas
,
Rimkevičius, Sigitas
Published in
Science and technology of nuclear installations
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Innovative technologies for spent fuel safe management at Ignalina channel-type reactors
by
Babilas, Egidijus
,
Dokucajev, Pavel
,
Janulevičius, Darius
,
Markelov, Aleksej
,
Pabarčius, Raimondas
,
Rimkevičius, Sigitas
,
Ušpuras, Eugenijus
,
Vaišnoras, Mindaugas
Published in
Nuclear engineering and technology
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Analysis of Void Reactivity Coefficient for 3D BWR Assembly Model
by
Uspuras, Eugenijus
,
Tonkūnas, Aurimas
,
Pabarčius, Raimondas
,
Slavickas, Andrius
Published in
Science and technology of nuclear installations
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Void Reactivity Coefficient Analysis during Void Fraction Changes in Innovative BWR Assemblies
by
Stankūnas, Gediminas
,
Tonkūnas, Aurimas
,
Pabarčius, Raimondas
,
Slavickas, Andrius
,
Uspuras, Eugenijus
Published in
Science and technology of nuclear installations
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Decomposition Analysis of Void Reactivity Coefficient for Innovative and Modified BWR Assemblies
by
Stankūnas, Gediminas
,
Tonkūnas, Aurimas
,
Pabarčius, Raimondas
,
Slavickas, Andrius
Published in
Science and technology of nuclear installations
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The Concept and RELAP5 Model of Thermal-Hydraulic System, Employing a Rapid Condensation for Coolant Circulation
by
Valinčius, Mindaugas
,
Šeporaitis, Marijus
,
Kaliatka, Algirdas
,
Pabarčius, Raimondas
,
Gasiūnas, Stasys
,
Laurinavičius, Darius
Published in
Heat transfer engineering
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Nuclear process heat application options: Highlights from the European GEMINI+ project
by
Fütterer, Michael A.
,
Pabarcius, Raimondas
,
Hübner, Sebastian
,
Pieńkowski, Ludwik
,
Brudek, Wojtek
,
Darnowski, Piotr
,
Pawluczyk, Michał
,
Chmielarz, Błażej
,
Šilhan, Martin
Published in
Nuclear engineering and design
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Evaluation of coolant density history effect in RBMK type fuel modelling
by
Tonkunas, Aurimas
,
Pabarcius, Raimоndas
,
Slavickas, Andrius
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Nuclear engineering and technology
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The impact of fuel depletion scheme within SCALE code on the criticality of spent fuel pool with RBMK fuel assemblies
by
Andrius Slavickas
,
Tadas Kaliatka
,
Raimondas Pabarcius
,
Sigitas Rimkevicius
Published in
Nuclear engineering and technology
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Assessment and benchmarking of the impact to gamma dose rate employing different photon-to-dose conversion factors using MCNPX code at the decommissioning stage of Ignalina Nuclear...
by
Stankunas, Gediminas
,
Pabarcius, Raimondas
,
Tonkunas, Aurimas
Published in
Radiation protection dosimetry
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Innovative technologies for spent fuel safe management at Ignalina channel-type reactors
by
Babilas, Egidijus
,
Dokucajev, Pavel
,
Janulevicius, Darius
,
Markelov, Aleksej
,
Pabarcius, Raimondas
,
Rimkevicius, Sigitas
,
Uspuras, Eugenijus
,
Vaisnoras, Mindaugas
Published in
Nuclear engineering and technology
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