Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Anže Pungerčič"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 8, Pp 3405-3424 (2024)
Reactivity worth of fuel rods at the JSI TRIGA research reactor was measured. Differently burned fuel rods were chosen to validate fuel burnup calculations. Two methods of measuring reactivity worth of fuel rods are used, traditional method is compar
Externí odkaz:
https://doaj.org/article/764a264ddf494b7da5be2499d821602e
Publikováno v:
EPJ Web of Conferences, Vol 247, p 08009 (2021)
Fuel burnup of the JSI TRIGA was calculated by simulating complete operational history consisting of 240 different core configurations from 1966 to 2020. At the moment we are unable to perform burnup measurements, e.g. gamma spectroscopy on burned fu
Externí odkaz:
https://doaj.org/article/509811e8d5344be284000528b72fc2d2
Autor:
Abdallah Lyoussi, Laurent Ottaviani, V. Valero, M. Carette, A. Volte, Luka Snoj, C. Reynard-Carette, H. Ghninou, Anže Pungerčič, Vladimir Radulović
Publikováno v:
EPJ Web of Conferences, Vol 253, p 04009 (2021)
Neutron detection is a relevant topic in the field of nuclear instrumentation. It is at the heart of the concerns for fusion applications (neutron diagnostics, measurements inside the Test Blanket Modules TBM) as well as for fission applications (in-
Publikováno v:
EPJ Web of Conferences, Vol 225, p 04027 (2020)
A pulse experiment model was validated in order to support future pulse experimental campaigns. All pulse experiments data was collected and are publicly available at http://trigapulse.ijs.si/. A comparison of the measured pulse physical parameters (
Autor:
Hubert Carcreff, Luka Snoj, Vladimir Cindro, Marko Mikuž, Anže Pungerčič, Igor Lengar, Aljaž Čufar, Loïc Barbot, J. F. Villard, Gregor Kramberger, Damien Fourmentel, Tanja Goričanec, A. Gruel, Anže Jazbec, Žiga Štancar, Christophe Destouches, Vladimir Radulović, Klemen Ambrožič, Sebastjan Rupnik, Igor Mandić, Gašper Žerovnik, Andrej Žohar
Publikováno v:
EPJ Web of Conferences, Vol 225, p 04031 (2020)
The JSI TRIGA reactor features several in-core and ex-core irradiation facilities, each having different properties, such as neutron/gamma flux intensity, spectra and irradiation volume. A series of experiments and calculations was performed in order
Publikováno v:
Nuclear Engineering and Design. 378:111170
Monte Carlo N-Particle (MCNP) transport code accelerated by AutomateD VAriaNce reducTion Generator (ADVANTG) code was used to simulate the transport of delayed gamma particles emitted from irradiated TRIGA fuel. At the first step, this method was ver
Publikováno v:
EPJ Web of Conferences; 2021, Vol. 247, p1-9, 9p
Autor:
Gašper Žerovnik, Damien Fourmentel, Andrej Trkov, Žiga Štancar, Clément Fausser, Vladimir Radulović, Anže Pungerčič, Nicolas Thiollay, A. Gruel, G. Gregoire, Christophe Destouches, Luka Snoj, Tanja Goričanec, Christophe Domergue, Grégoire De Izarra, Igor Lengar, Loïc Barbot, Klemen Ambrožič, Benoit Geslot
Publikováno v:
EPJ Web of Conferences, Vol 253, p 04018 (2021)
Constant improvements of the computational power and methods as well as demands of accurate and reliable measurements for reactor operation and safety require a continuous upgrade of the instrumentation. In particular, nuclear sensors used in nuclear
Publikováno v:
Fusion Engineering and Design
Activated cooling water in nuclear facilities can present a significant radiation source around primary cooling system causing radiation damage to electrical components, increasing doses to personnel and in the case of fusion facilities additional he
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