Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Eugenijus Ušpuras"'
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 1, Pp 27-36 (2020)
Natural convection and thermal stratification phenomena are found in large water pools that are being used as heat sinks for decay heat removal from the reactor core using passive heat removal systems. In this study, the two-phase (water and air) nat
Externí odkaz:
https://doaj.org/article/86ad3703c73a45209bde8430b7eff685
Autor:
Egidijus Babilas, Pavel Dokucajev, Darius Janulevičius, Aleksej Markelov, Raimondas Pabarčius, Sigitas Rimkevičius, Eugenijus Ušpuras, Mindaugas Vaišnoras
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 3, Pp 504-511 (2018)
In Lithuania, all spent nuclear fuel (SNF) resulted from the operation of the Ignalina Nuclear Power Plant (INPP), which had two Russian Acronym for “Channelized Large Power Reactor”-type reactors. After the final shutdown, the total amount of SN
Externí odkaz:
https://doaj.org/article/fb99953dcf7b423bbb04c2af97e9df5d
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2018 (2018)
One of the severe accident management strategies for nuclear reactors is the melted corium retention inside the reactor pressure vessel. The work presented in this article investigates the application of in-vessel retention (IVR) severe accident mana
Externí odkaz:
https://doaj.org/article/040a97069f274dab8bb2dccdf350704a
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2017 (2017)
Uncertainty and sensitivity analysis of void reactivity feedback for 3D BWR fuel assembly model is presented in this paper. Uncertainties in basic input data, such as the selection of different cross section library, manufacturing uncertainties in ma
Externí odkaz:
https://doaj.org/article/cd6af145fbdd4a748b25bc19f4bb6d4a
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2016 (2016)
The effect of BWR fuel assembly 3D model on void reactivity coefficient (VRC) estimation is investigated. VRC values were calculated for different BWR assembly models applying deterministic T-NEWT and Monte Carlo KENO-VI functional modules of SCALE 6
Externí odkaz:
https://doaj.org/article/48b064d888254864863d18046554c55a
Autor:
Egidijus Babilas, Eugenijus Ušpuras, Sigitas Rimkevičius, Gintautas Dundulis, Mindaugas Vaišnoras
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2015 (2015)
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 su
Externí odkaz:
https://doaj.org/article/92a502baf9214fdcb399c7331399e269
Autor:
Andrius Slavickas, Raimondas Pabarčius, Aurimas Tonkūnas, Gediminas Stankūnas, Eugenijus Ušpuras
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2015 (2015)
The study of the void reactivity variation in innovative BWR fuel assemblies is presented in this paper. The innovative assemblies are loaded with high enrichment fresh UO2 and MOX fuels. UO2 fuel enrichment is increased above existing design limitat
Externí odkaz:
https://doaj.org/article/ac0d44748f2e4332ab4cae43ed98fb8e
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2014 (2014)
To prevent total meltdown of the uncovered and overheated core, the reflooding with water is a necessary accident management measure. Because these actions lead to the generation of hydrogen, which can cause further problems, the related phenomena ar
Externí odkaz:
https://doaj.org/article/ca332a7e6b0a47879d495e1f4716c938
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2013 (2013)
The safe storage of spent fuel assemblies in the spent fuel pools is very important. These facilities are not covered by leaktight containment; thus, the consequences of overheating and melting of fuel in the spent fuel pools can be very severe. On t
Externí odkaz:
https://doaj.org/article/367d376b4780468ead3ced7dd86d4519
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2008 (2008)
Eight main circulation pumps (MCPs) are employed for the cooling of water forced circulation through the RBMK-1500 reactor at the Ignalina nuclear power plant (NPP). These pumps are joined into groups of four pumps each (three for normal operation an
Externí odkaz:
https://doaj.org/article/2e40fb695df84cfc8a9ccac2719dc935