A5073992124- Nuclear Physics and Applications
- Radiation Detection and Scintillator Technologies
- Nuclear reactor physics and engineering
- Radiation Therapy and Dosimetry
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Radiation Shielding Materials Analysis
- Radiation Effects in Electronics
- Particle accelerators and beam dynamics
- Atomic and Subatomic Physics Research
- Nuclear Materials and Properties
- Advanced Radiotherapy Techniques
- Quantum, superfluid, helium dynamics
- Radiation Effects and Dosimetry
National Centre for Nuclear Research
2013-2024
Centrum Badań Jakości
2016
Aircraft crew are one of the groups radiation workers which receive highest annual exposure to ionizing radiation. Validation computer codes used routinely for calculation due cosmic and observation nonpredictable changes in level solar energetic particles, requires continuous measurements onboard aircraft. Appropriate calibration suitable instruments is crucial, however, very complex atmospheric field there no single reference covering all particles energies involved. Further...
This study aims to characterize the neutron radiation field inside a scanning proton therapy treatment room including impact of different pediatric patient sizes. Working Group 9 European Radiation Dosimetry (EURADOS) has performed comprehensive measurement campaign measure ambient dose equivalent, H*(10), at eight positions around 1-, 5-, and 10-year-old anthropomorphic phantoms irradiated with simulated brain tumor treatment. Several active detector systems were used. The mapping within...
The MARIA research reactor is designed and operated as a multipurpose nuclear installation, combining material testing, neutron beam experiments, medical industrial radionuclide production, including molybdenum-99 (99Mo). Recently, after fuel conversion to LEU rejuvenation of the staff while maintaining their experience, has been used respond increased interest scientific community in advanced power studies, both fission fusion. In this work, we would like introduce MARIA’ s capabilities...
Abstract This paper presents the set of procedures developed in Radiation Protection Measurements Laboratory at National Centre for Nuclear Research evaluation shielding properties high performance concrete. The purpose such procedure is to characterize material behaviour against gamma and neutron radiation. range densities concrete specimens was from 2300 3900 kg/m 3 . photons were evaluated using 137 Cs 60 Co sources. radiation measurements have been performed by measuring transmitted 239...
This paper presents the results on radiation shielding of special types concrete, designed for nuclear reactor containments. The research focused study properties against neutron component ionizing radiation. For this purpose, two source were used: isotopic reference field 239Pu-Be in calibration laboratory and MARIA Research Reactor.
The long-lived xenon isomers 129mXe and 131mXe are of interest for the GAMMA-MRI project, which aims at developing a novel imaging modality based on magnetic resonance polarized unstable tracers. Here, we present steps leading to following production these two via neutron irradiation highly-enriched 128Xe 130Xe gas samples high-flux reactors, High-Flux Reactor (Réacteur à haut flux, RHF) Institut Laue-Langevin (ILL) MARIA reactor National Centre Nuclear Research (NCBJ). We describe...
W artykule przedstawiono wyniki badań właściwości osłonnych betonów eksperymentalnych przed promieniowaniem gamma, z wykorzystaniem zamkniętego źródła promieniotwórczego 137 Cs.Do analiz sporządzono i opisano specjalne stanowisko badawcze o określonej geometrii.Do wykorzystano odpowiednio przygotowane próbki ciężkich zróżnicowanym składzie.W ramach prac przebadano piętnaście rodzajów różniących się przede wszystkim zawartością kruszyw oraz gęstością objętościową.Na podstawie uzyskanych...
A micro-gap air-filled ionisation chamber was designed for criticality dosimetry. The special feature of the is its very small gap between electrodes only 0.3 mm. This prevents ion recombination at high dose rates and minimises influence gas on secondary particles spectrum. are made polypropylene because higher content hydrogen in this material, when compared with soft tissue. difference neutron gamma sensitivity such becomes practically negligible. chamber's envelope contains two specially...
The long-lived xenon isomers 129mXe and 131mXe are of interest for the GAMMA-MRI project, which aims at developing a novel imaging modality based on magnetic resonance polarised unstable tracers. Here, we present steps leading to following production these two via neutron irradiation highly-enriched 128Xe 130Xe gas samples high-flux reactors, High-Flux Reactor (R´eacteur `a haut flux, RHF) Institut Laue-Langevin (ILL) MARIA reactor National Centre Nuclear Research (NCBJ). We describe...