A5059471557- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Radiation Detection and Scintillator Technologies
- Particle Detector Development and Performance
- Fusion materials and technologies
- Boron Compounds in Chemistry
- Silicon Carbide Semiconductor Technologies
- Radiation Therapy and Dosimetry
- Nuclear physics research studies
Jožef Stefan Institute
2020-2024
University of Ljubljana
2020-2024
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2024
The Real-time Analysis for Particle-transport and In-situ Detection (RAPID) Code System, developed based on the Multi-stage Response-function Transport (MRT) methodology, enables real-time simulation of nuclear systems such as reactor cores, spent fuel pools casks, sub-critical facilities. This paper presents application a novel fission matrix-based burnup methodology to well-characterized JSI TRIGA Mark II research reactor. allows calculation depletion by combination interpolation RAPID's...
In this study, analysis of the complete operational history "Jožef Stefan" Institute (JSI) TRIGA reactor was performed. Reactor power changes, core configurations and weekly excess reactivity measurements were analysed to obtain needed data for fuel burnup calculations. More than 50 years operation simulated using deterministic code TRIGLAV stochastic Serpent-2. The calculated reactivities are in good agreement compared with measurements. Code-to-code comparison is presented. Clear observed...
In the paper we validate theoretical models of pulse against experimental data from Jozef Stefan Institute TRIGA Mark II research reactor. Data all experiments since 1991 have been collected, analysed and are publicly available. This summarizes validation study, which is focused on comparison between values, predictions (Fuchs-Hansen Nordheim-Fuchs models) calculation using computational program Improved Pulse Model. The results show that predicts higher maximum power but lower total...
Reactivity worth of fuel rods at the JSI TRIGA research reactor was measured. Differently burned were chosen to validate burnup calculations. Two methods measuring reactivity are used, traditional method is compared newly introduced using swapping. Connection between both described theoretically and theory validated experimentally. Fuel rod calculated swap within 1σ measured method. In addition recently performed experiments, weekly measurements core throughout operational history used for...
A pulse experiment model was validated in order to support future experimental campaigns. All experiments data collected and are publicly available at http://trigapulse.ijs.si/. comparison of the measured physical parameters (maximal power, total released energy full width half maximum) theoretical predictions (Fuchs-Hansen Nordheim-Fuchs models) made.
The JSI TRIGA reactor features several in-core and ex-core irradiation facilities, each having different properties, such as neutron/gamma flux intensity, spectra volume. A series of experiments calculations was performed in order to characterise radiation fields channel thus allowing users perform irradiations a well characterised environment. Since 2001 the has been heavily used for hardness studies components at accelerators Large Hadron Collider (LHC) CERN. 2010 it extensively testing...
This paper discusses the current status of European research reactor (RR) fleet and identified opportunities for its utilization. The data this analysis was collected through a specific questionnaire from which database RR created. designed to assess degree exploitation different applications identify gaps future results indicate that is older compared world average, with no new reactors built in Europe since 1992. majority RRs reported low levels across all applications, desire expand...
Activated cooling water in nuclear facilities can present a significant radiation source around primary system causing damage to electrical components, increasing doses personnel and the case of fusion additional heating superconducting coils. As there are only few sources gamma rays with energies range 6 MeV 7 an irradiation using activated as energetic is proposed at Jožef Stefan Institute (JSI) TRIGA Mark II research reactor. Two different conceptual designs, one utilizing central channel...
<title>Abstract</title> Neutron activation dosimetry is the primary method for determination of neutron flux or fluence, and in general, it sensitive to thermal resonance energy ranges (radiative capture reactions - (n,g) reactions) fast range (threshold reactions). However, there are very few nuclear which specifically neutrons intermediate epithermal region. This region, along with range, will become particularly important development deployment new reactor technologies (Generation IV...
Abstract The TRIGA Mark II research reactor at the Jožef Stefan Institute in Slovenia achieved first criticality 1966. Since then, has been playing an important role developing nuclear technology. mainly used for research, education of university students, training operators Krško power plant (start operation 1983) and other specialists, isotope production beam applications. is experiencing a high level activity today, engaging diverse range experiments studies across physics, environmental...
Neutron activation dosimetry is the primary method for determination of neutron flux or fluence, and in general, it sensitive to thermal resonance energy ranges (radiative capture reactions– $$(n,\gamma )$$ reactions) fast range (threshold reactions). However, there are very few nuclear reactions which specifically neutrons intermediate–epithermal–energy region. This region, along with range, will become particularly important development deployment new reactor technologies (Generation IV...
Constant improvements of the computational power and methods as well demands accurate reliable measurements for reactor operation safety require a continuous upgrade instrumentation. In particular, nuclear sensors used in fission reactors (research or reactors) fusion facilities are operated under intense mixed neutron gamma-ray fields, need to be calibrated modeled provide selective measurements. The French Atomic Energy Alternative Energies Commission (CEA) Jožef Stefan Institute (JSI)...
Neutron detection is a relevant topic in the field of nuclear instrumentation. It at heart concerns for fusion applications (neutron diagnostics, measurements inside Test Blanket Modules TBM) as well fission (in-core and ex-core monitoring, neutron mapping or safety research reactors). Moreover, due to even more harsh conditions future experimental reactors such Jules Horowitz Reactor (JHR) International Thermonuclear Experimental (ITER), detectors need be adapted high γ fluxes, heating...
Fuel burnup of the JSI TRIGA was calculated by simulating complete operational history consisting 240 different core configurations from 1966 to 2020. At moment we are unable perform measurements, e.g. gamma spectroscopy on burned fuel elements, hence used weekly measured excess reactivity as a reference point verify reactivity. Changes in due were assumed be linear and this assumption verified for intervals smaller than 3 MWd / kg(HM) . The comparison performed 46 with type elements....