1. Nuclear heating at the JSI TRIGA reactor : measurements and simulationsKlemen Ambrožič, Vladimir Radulović, Luka Snoj, Hubert Carcreff, Damien Fourmentel, Christophe Destouches, Nicolas Thiollay, 2026, izvirni znanstveni članek Povzetek: Nuclear heating plays an important aspect in design and deployment of both fission and fusion reactors and experimental devices in terms of cooling requirements. Two experimental campaigns in the framework of a collaboration project between the French Atomic and Alternative Energy Commission (CEA) and Jožef Stefan Institute (JSI), Slovenia, have been performed at the JSI TRIGA reactor for the experimental assessment of nuclear heating in fission and fusion-relevant materials by the differential calorimetry technique, based on the CALMOS and CARMEN differential calorimeters, previously developed at CEA. The results of the first campaign performed at reactor powers between 100 and 250 kW have already been reported, highlighting some measurement difficulties. Therefore, the second campaign was performed at a lower reactor power of 30 kW to overcome these issues. Moreover, a computational analysis of the experiments was performed using the JSIR2S code package to calculate the nuclear heating levels. Both experiments and their reproduction by simulations are described in detail. We present a comparison of the previously reported measured nuclear heating values of the first campaign with the computational results, with consistent underestimation by simulations by 8–35%. We report the experimental and computational results for the second experimental campaign performed at a reactor power of 30 kW. The simulated heating values were in agreement with the measurements within the measured heating uncertainty, with simulated heating 2.7–11.3% lower than the experimental values.
Ključne besede: nuclear heating, differential calorimeter, R2S (rigorous two-step method), MCNP, Eurofer97, Tungsten
Objavljeno v DiRROS: 20.02.2026; Ogledov: 182; Prenosov: 64
 Celotno besedilo (1,63 MB)
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2. Validating a simplified water-activation transport model using time-resolved reactor-pulse neutron measurements at KATANAJulijan Peric, Domen Kotnik, Domen Govekar, Luka Snoj, Vladimir Radulović, 2026, izvirni znanstveni članek Povzetek: KATANA is a water activation facility at the Jožef Stefan Institute TRIGA Mark II reactor in Ljubljana, Slovenia, developed to study water activation processes relevant for future fusion systems such as ITER. In this work, we validated a simplified activation-transport model of the KATANA loop using time-resolved neutron measurements during reactor pulse operation. A finite volume of water in the KATANA loop was irradiated during reactor pulses, and the subsequent decay of Image 1001 was tracked with a He detector. For each reactor pulse two distinct activation peaks were observed, corresponding to successive passages of activated water, and showed excellent agreement with model predictions. The measurements enabled to determine loop parameters in particular the effective loop volume, which gave excellent agreement with the direct measurements. The presented validation provides a solid foundation for future experimental campaigns at the KATANA water activation facility, aimed at performing integral cross-section measurements of the Image 1002 reaction and advancing studies of activation phenomena relevant to fusion applications.
Ključne besede: nuclear reactors, water activation, JSI, KATANA, neutron measurements, ITER
Objavljeno v DiRROS: 12.01.2026; Ogledov: 159; Prenosov: 81
Celotno besedilo (2,42 MB)
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3. Advanced Monte Carlo analysis of ex-vessel neutron dosimetry for cycle 25 of Krško nuclear power plantTanja Goričanec, Benjamin Barbarič, Vladimir Radulović, Dušan Čalič, Luka Snoj, Marjan Kromar, 2026, izvirni znanstveni članek Povzetek: This paper presents the results of Monte Carlo neutron transport calculations performed for the containment building of the Krško Nuclear Power Plant. The calculations were performed using the Monte Carlo N-Particle Transport Code (MCNP) in combination with the ADVANTG hybrid code to speed up the convergence of the results outside the reactor core. The paper focuses on the analysis of the Ex-Vessel Neutron Dosimetry (EVND) program conducted during the 25th fuel cycle at the Krško nuclear power plant with the irradiation of gradient chains and multiple foil sensor sets. The calculated reaction rates at the dosimeter locations are in good agreement with the measured values. However, deviations were observed in the thermal part of the neutron energy spectrum which cannot be neglected, and investigated were some possible reasons for the deviations: nuclear data, concrete material composition, concrete geometry, sensor position and impurities in sample.
Ključne besede: neutron transport, ex-vessel neutron dosimeters, neutron
Objavljeno v DiRROS: 20.10.2025; Ogledov: 329; Prenosov: 138
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4. A half-century of nuclear research, education and training : Story of the JSI TRIGA reactorLuka Snoj, Klemen Ambrožič, L. Barbot, Ljudmila Benedik, Arne Bratkič, Ivana Capan, C. Reynard-Carette, Vladimir Cindro, Dušan Čalič, Christophe Destouches, B. Geslot, Alireza Haghighat, Romain Henry, Milena Horvat, Elchin Huseynov, Gregoire De Izzara, Radojko Jaćimović, Anže Jazbec, Igor Jenčič, Robert Jeraj, Malcolm Joyce, Domen Kotnik, Gregor Kramberger, Igor Lengar, Jan Malec, Igor Mandić, Valerio Mascolino, Vid Merljak, Marko Mikuž, Gilles Noguere, Julijan Peric, Anže Pungerčič, Vladimir Radulović, Sebastjan Rupnik, Borut Smodiš, Zdenka Šlejkovec, Marko Štrok, Žiga Štancar, Ingrid Švajger, N. Thiollay, Iztok Tiselj, Andrej Trkov, Bojan Žefran, Gašper Žerovnik, Ylenia Žiber, Tanja Goričanec, 2025, pregledni znanstveni članek Povzetek: The TRIGA Mark II research reactor at the Jožef Stefan Institute is a key facility in the field of nuclear research, characterized by its versatility and applicability in a wide range of scientific disciplines. This document highlights its operational history, contributions to nuclear safety, education and various scientific applications, including advances in reactor and radiation physics, neutron activation analysis, environmental science and even contributions to the fight against the COVID-19 pandemic. It highlights the reactor’s significant role in fostering international collaborations, improving computer modeling techniques for nuclear research, and providing invaluable educational experiences. The great versatility and applicability of the JSI TRIGA reactor is emphasized by its adaptability to various research needs and its ability to enable groundbreaking studies in both fundamental and applied sciences
Objavljeno v DiRROS: 11.04.2025; Ogledov: 933; Prenosov: 242
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