Zobrazeno 1 - 10
of 42
pro vyhledávání: '"Tadas KALIATKA"'
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 12, Pp 4731-4742 (2022)
RBMK fuel assemblies differ from other LWR FA due to a specific arrangement of the fuel rods, the low enrichment, and the used burnable absorber – erbium. Therefore, there is a challenge to adapt modeling tools, developed for other LWR types, to so
Externí odkaz:
https://doaj.org/article/9786fef4e04e4b6f896c9e4c57a79e8f
Publikováno v:
International Journal of Thermofluids, Vol 14, Iss , Pp 100154- (2022)
The water hammer phenomenon investigations employing RELAP5 code with one-dimensional two-fluid six-equation models of water and steam flow were performed and the main results shared in this paper. The capability of RELAP5 code to simulate transients
Externí odkaz:
https://doaj.org/article/96fd7e46de0641199902c528af4998a6
Autor:
Noura Elsalamouny, Tadas Kaliatka
Publikováno v:
Energies, Vol 14, Iss 21, p 7320 (2021)
One of the biggest experimental programs helping to improve nuclear installation safety is PHEBUS, an international cooperative research program that provides data for validating computer codes dedicated to the analysis of severe accidents and their
Externí odkaz:
https://doaj.org/article/89aaaf08fc26416c9c3199c1b2552b87
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 2, Pp 419-433 (2016)
One of the important severe accident management measures in the Light Water Reactors is water injection to the reactor core. The related phenomena are investigated by performing experiments and computer simulations. One of the most widely known is th
Externí odkaz:
https://doaj.org/article/10235b8053c34125a3d13ed2c218b182
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:
Medžiagotyra, Vol 20, Iss 4, Pp 403-408 (2014)
Goal of this research was to find out if reorientation can influence cladding failure and determine conditions and possible mechanism of failure. Reorientation tests were done on zircaloy nuclear fuel cladding specimens. Specimens were made having tw
Externí odkaz:
https://doaj.org/article/4bf9dcafb8c542f6a7b77a8698838b96
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
Autor:
Juozas Augutis, Rolandas Urbonas, Egidijus Urbonavicius, Linas Martišauskas, Algirdas Kaliatka, G. Dundulis, Tadas Kaliatka, G. Stankūnas, Sigitas Rimkevicius, Mantas Povilaitis, R. Krikštolaitis, Raimondas Pabarčius, Egidijus Babilas
Publikováno v:
Kerntechnik. 85:72-81
This article is written to honour the scientific achievements of prof. Eugenijus Ušpuras, who passed away in 2019. Therefore, his colleagues summarized retrospectively main research topics like safety studies for Ignalina NPP, research in nuclear fu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::149d17e106f9708095d17de464205d63
https://doi.org/10.1515/kern-2020-850203
https://doi.org/10.1515/kern-2020-850203
Publikováno v:
SSRN Electronic Journal.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2a1bcb8125c8c9e7c6c68c4c15852baa
https://doi.org/10.2139/ssrn.4055236
https://doi.org/10.2139/ssrn.4055236
Autor:
Nicholas Terranova, Simona Breidokaité, Gian Marco Contessa, Luigi Di Pace, Claudia Gasparrini, Tadas Kaliatka, Giovanni Mariano
Publikováno v:
Environments; Volume 9; Issue 7; Pages: 76
Activated corrosion products generation in primary heat transfer systems of nuclear fusion facilities is a relevant radiological source term for occupation dose assessments. The formation of the Chalk River Undefined Deposit, already well known in nu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::787016a51c7fb0d401699d0f2e1eb6e0
https://www.mdpi.com/2076-3298/9/7/76
https://www.mdpi.com/2076-3298/9/7/76
