Zobrazeno 1 - 10
of 16
pro vyhledávání: '"Dušan Ćalić"'
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
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
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
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
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
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
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
Publikováno v:
Annals of Nuclear Energy
MCNP and the ADVANTG code were used to analyse γ-dose rates for the future Slovenian LILW repository. Using ADVANTG’s variance reduction technique, different detailed calculations of γ-dose rates were achievable in a reasonable time, whereby the
This book presents state-of-the-art discussions around the concentration camp Jasenovac. Initially one of the largest camps of the Second World War, Jasenovac became a symbol of supra-national unity during the Yugoslav period and in the 1990s re-emer