Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Radomir Ječmenica"'
Publikováno v:
Energies, Vol 14, Iss 23, p 8022 (2021)
Nuclear energy is an option that enables a significant reduction of greenhouse gases emissions at the national and European Union (EU) level. However, it is also an option that is mostly influenced by public opinion and an option that has strong cros
Externí odkaz:
https://doaj.org/article/0d6128a515354f42bfd214402b48cede
Full Core Criticality Modeling of Gas-Cooled Fast Reactor using the SCALE6.0 and MCNP5 Code Packages
Publikováno v:
Journal of Energy : Energija
Volume 62
Issue 1-4
Volume 62
Issue 1-4
The Gas-Cooled Fast Reactor (GFR) is one of the reactor concepts selected by the Generation IV International Forum (GIF) for the next generation of innovative nuclear energy systems. It was selected among a group of more than 100 prototypes and his c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::26ed48b256b0efdd54d586d127004e5a
https://doi.org/10.37798/2013621-4229
https://doi.org/10.37798/2013621-4229
Publikováno v:
Journal of Energy : Energija
Volume 65
Issue 1-2
Volume 65
Issue 1-2
This paper presents comparison of the Krško Power Plant simplified Spent Fuel Pool (SFP) dose rates using different computational shielding methodologies. The analysis was performed to estimate limiting gamma dose rates on wall mounted level instrum
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::80c2cd72e80ff939ca84c4bd247b1580
https://doi.org/10.37798/2016651-2138
https://doi.org/10.37798/2016651-2138
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 8
In this paper, shielding analysis was performed to determine neutron and gamma dose rates around the transfer cask HI-TRAC VW (Holtec International Transfer Cask Variable Weight) loaded with spent fuel assemblies (SFA) from nuclear power plant (NPP)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::875e406087173a2dcc2c66d4442145a5
https://doi.org/10.1115/1.4051447
https://doi.org/10.1115/1.4051447
Autor:
Dubravko Horvat, Radomir Ječmenica
Publikováno v:
Resonance. 21:259-275
A simple apparatus for an experiment often performed during introductory lectures on free fall is described. Collected data of the free fall times are given and the standard calculation of the acceleration of free fall g including error evaluation is
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::34130d964ecfed75506d4ee893d14803
https://doi.org/10.1007/s12045-016-0321-9
https://doi.org/10.1007/s12045-016-0321-9
Publikováno v:
Journal of Energy : Energija
Volume 65
Issue 1-2
Volume 65
Issue 1-2
The Integral Inherently Safe Light Water Reactor (I2S-LWR) concept developed by Georgia Tech is a novel PWR reactor delivering electric power of 1000 MWe while implementing inherent safety features typical for Generation III+ small modular reactors.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::030d1b8209e645382d01cd98f4089628
https://www.bib.irb.hr/1110783
https://www.bib.irb.hr/1110783
Publikováno v:
Journal of Energy : Energija
Volume 65
Issue 1-2
Volume 65
Issue 1-2
The Integral Inherently Safe Light Water Reactor (I2S-LWR) concept developed by a team lead by Georgia Tech is a novel PWR reactor delivering electric power of 1000 MWe while implementing inherent safety features typically reserved for Generation III
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5c594d476b7b5e962a4dc27cffe81eeb
https://www.bib.irb.hr/826756
https://www.bib.irb.hr/826756
Publikováno v:
Nuclear Engineering and Design. 246:27-40
Lattice codes are able to produce burnup dependent fuel assembly homogenized neutron cross sections and pin power form factors. These data are used by diffusion nodal codes to produce fuel assembly powers and intra assembly power distributions. 2D tr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cba21b99aaed1feabfe21f6effb1cbf0
https://doi.org/10.1016/j.nucengdes.2011.11.032
https://doi.org/10.1016/j.nucengdes.2011.11.032
The calculations were performed at different power levels for selected IFBA and non-IFBA NPP Krsko fuel assemblies using 2D lattice codes (DRAGON, NEWT and FA2D) to show quantitative influence of xenon concentration on homogenized cross sections. In
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c5af3bfd4b04d2f66e2414a08b5f9f63
https://www.bib.irb.hr/591215
https://www.bib.irb.hr/591215