A5077710501- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Graphite, nuclear technology, radiation studies
- Nuclear Materials and Properties
- Molten salt chemistry and electrochemical processes
- Radiation Detection and Scintillator Technologies
- Radiation Therapy and Dosimetry
- Nuclear and radioactivity studies
- Perovskite Materials and Applications
- Grouting, Rheology, and Soil Mechanics
- Seismic Waves and Analysis
- Geotechnical Engineering and Soil Stabilization
- Radiation Effects and Dosimetry
- Advancements in Solid Oxide Fuel Cells
- Photonic Crystal and Fiber Optics
- Advanced Radiotherapy Techniques
- Geographic Information Systems Studies
- Advanced Fiber Optic Sensors
Research Centre Rez
2020-2024
University of West Bohemia
2021-2023
Czech Technical University in Prague
2019
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Energy harvesting is a versatile approach that holds promise for generating clean energy and enhancing the sustainability of infrastructure. Given challenges associated with nuclear waste, such as radiation levels long-term storage requirements, developing suitable materials crucial. These must be capable withstanding harsh conditions present in waste facilities while efficiently capturing converting energy. The objective this work was to study lead halide perovskites ( MAPbCl3 MAPbI3) terms...
The measured and evaluated excitation functions are fundamental quantities that affect the accuracy of all calculations in nuclear applications. Some cross sections, such as 14N(n,p)14C, have added value for special applications, these reactions may be responsible possible contamination industrial processes spent fuel reprocessing. For validation we can rely on comparison calculated spectrum averaged sections (SACS) given neutron with SACS value. benchmark reference field has been...
This paper is focused on validation of graphite cross section. Graphite an important material for a wide range reactors such as HTR, RBMK or VHTR and MSR belonging to the generation IV, which are now under development. However, there still uncertainties in its sections. For purposes mentioned validation, set measurements LR-0 core with insertion cube external neutron source center was carried out. Other types cores larger sensitivity investigation The cross-section by integral experiments...
Several concepts of new reactors use graphite. Some them graphite as a moderator, some reflector. There are at least two these graphitetype under development in the Czech Republic. Both An in-core measurement might be impossible to because various reasons, for instance, high temperature or aggressive environment. Therefore, this article focuses on ex-core neutron flux system placed reflector and optimization detector position. A set experiments were performed LR-0 reactor. The is light water...
Dosimetry cross sections are fundamental quantities necessary for neutron dosimetry using the activation method. It is worth noting that uncertainty in major source of calculational predictions nuclear data simulations. Thus, section validation a key issue any aims refinement predictions. A small compact generator promising tool performing integral experiments and even differential experiments. This paper deals with measurement D-T 14.05 ± 0.08 MeV emission (1×108 n/s into 4π). Achieving...
Dosimetry cross sections are fundamental quantities necessary for neutron dosimetry using the activation method. It is worth noting that uncertainty in major source of calculational predictions nuclear data simulations thus, section validation a key issue any aims refinement predictions. A small compact generator promising tool performing integral experiments and even differential experiments. This paper deals with measurement D-T 14.05 MeV emission (10E8 n/s into 4pi). Achieving measurable...
Graphite is important reactor material used as a neutron moderator in various designs. It not only structural previous reactors design but even to which attention focused due the very high-temperature design, uses graphite and reflector. Due well-characterised cross-section of graphite, it also good candidate for shaping experiments. In this kind experiment, spectra are modified unconventional shape can be validate cross-section. This paper deals with validation field block surrounded by...
This paper is focused on the development of experimental environment connected to reactor graphite. Regarding its very good neutronic and mechanical properties, graphite will be important in some new designs, such as high-temperature or molten salt SMR reactors. These concepts require a support for further research. In laboratories Research Centre Řež at LR-0 reactor, experimentally validated was created. large insertion largest mono-block, which possible assemble reactor. Sets experiments...
Abstract Nowadays, there is an increasing demand for new small modular reactors (SMR) with a wide range of applications, often classified as Generation-IV reactors. Unfortunately, no commercially operating nuclear reactor meeting the characteristics in its technical design and features. However, are intensively developed worldwide, including Czech Republic. To support research activities linked development these reactors, appropriate experimental environment resources simulating conditions...
Abstract Silicon dioxide is a common material in nature and also often used the nuclear industry (concrete, radioactive waste repositories bedrocks), therefore, properly characterizing neutronic properties very important for energy criticality safety applications. The worth was measured several core arrangements containing silica sand both inside and/or as reflector by measuring moderator level. lateral central reflectors different combinations. results showed that new thermal scattering law...