Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Dušan Ćalić"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 9, Pp 3668-3685 (2024)
The operation of a nuclear power plant relies on precalculated nuclear design predictions based on core calculations of various reactor states. The fuel temperature is a crucial factor in determining the reactor fuel behavior, but assessing the tempe
Externí odkaz:
https://doaj.org/article/8f0914191b3d4efbad3663067f82ab56
Autor:
Dušan Ćalić, Andrej Trkov, Matjaž Ravnik, Tomaž Žagar, Andreja Peršič, Luka Snoj, Slavko Slavic, Bojan Žefran, Anže Jazbec, Gašper Žerovnik
Publikováno v:
Nuclear Engineering and Design. 318:24-34
An overview of the TRIGLAV package, a tool for the computational analysis of TRIGA Mark II reactors based on lattice transport code WIMSD for unit cell cross section homogenization and four-group diffusion theory in 2D cylindrical coordinates, is pre
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8616659943e2ad68adc64cabbed65a5d
https://doi.org/10.1016/j.nucengdes.2017.04.010
https://doi.org/10.1016/j.nucengdes.2017.04.010
Autor:
Peter Schillebeeckx, Klemen Ambrožič, A. Stankovskiy, L. Fiorito, Gašper Žerovnik, Marjan Kromar, B. Kos, Dušan Ćalić, Augusto Hernández-Solís
Publikováno v:
EPJ Web of Conferences
EPJ Web of Conferences, Vol 247, p 12008 (2021)
EPJ Web of Conferences, Vol 247, p 12008 (2021)
In this paper, two main exercises have been carried out to describe the effect that varying an albedo boundary condition has in the computation of observables such as decay heat, neutron emission rate and nuclide inventory from a PWR fuel assembly (o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::749c03397880fc26b40ee0051831faba
https://doi.org/10.1051/epjconf/202124712008
https://doi.org/10.1051/epjconf/202124712008
Publikováno v:
EPJ Web of Conferences, Vol 247, p 05001 (2021)
The ADVANTG code was used to analyze dose rates from the proposed Slovenian silo-type low and intermediate level waste (LILW) repository. Detailed calculations of dose rates are challenging as gamma-sources are located in thick concrete containers an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8e9366ecff66589168b26c659f6f763a
https://doi.org/10.1051/epjconf/202124705001
https://doi.org/10.1051/epjconf/202124705001
Publikováno v:
Progress in Nuclear Energy. 130:103536
In this study, analysis of the complete operational history of the “Jožef Stefan” Institute (JSI) TRIGA reactor was performed. Reactor power changes, core configurations and weekly excess reactivity measurements were analysed to obtain the neede
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3c57494887811719b97e7939e305c1b2
https://doi.org/10.1016/j.pnucene.2020.103536
https://doi.org/10.1016/j.pnucene.2020.103536
Publikováno v:
Annals of Nuclear Energy. 94:392-398
The use of Monte Carlo transport method with the Serpent code for generating unit cell cross sections of a light-water reactor is investigated. The geometry is a 3 × 3 array of cells, where homogenization is performed over the central cell, while th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f14d08bfd08cc35f2b9e10fec21ee96b
https://doi.org/10.1016/j.anucene.2016.04.008
https://doi.org/10.1016/j.anucene.2016.04.008
Autor:
Dušan Čalič, Marjan Kromar
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 9, Pp 3260-3271 (2022)
Experience shows that the solution to waste management in any national programme is lengthy and burdened with uncertainties. There are several uncertainties that contribute to the costs associated with spent fuel management. In this work, we have ana
Externí odkaz:
https://doaj.org/article/a063ef410b8f4aaebf9e26c40e46203b
Autor:
Dušan Ćalić, Matjaž Ravnik
Publikováno v:
Nuclear Engineering and Design. 240:668-671
Criticality calculations have been performed for a typical spent fuel disposal canister model filled with PWR fuel elements. Geometric and material properties of the disposal canister and disposal holes were modeled based on the Swedish preliminary d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f8a83e832a2a98d4063dda9bade0d4a2
https://doi.org/10.1016/j.nucengdes.2009.10.021
https://doi.org/10.1016/j.nucengdes.2009.10.021
Publikováno v:
Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine. 107
The main aim of this paper is the development and validation of a 3D computational model of TRIGA research reactor using Serpent 2 code. The calculated parameters were compared to the experimental results and to calculations performed with the MCNP c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a53588c6f6ef1fd2147f1f05426e3122
https://pubmed.ncbi.nlm.nih.gov/26516989
https://pubmed.ncbi.nlm.nih.gov/26516989
Autor:
Gašper Žerovnik, Dušan Čalič, Samo Gerkšič, Marjan Kromar, Jan Malec, Anže Mihelčič, Andrej Trkov, Luka Snoj
Publikováno v:
Frontiers in Energy Research, Vol 11 (2023)
Previous work done on reactor kinetics and control in load-following operation modes available in open literature is reviewed. The analysis is focused on, however not limited to pressurized water reactors. Different approximations of the time-depende
Externí odkaz:
https://doaj.org/article/4a3f4dc9cb204a60ad814b8d8ceaffae