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Wyszukujesz frazę "L. A. S." wg kryterium: Autor


Tytuł:
Investigation of low temperature diffusion of carbon in martensite by Mössbauer spectroscopy and X-ray diffraction
Autorzy:
Jabłońska, A.
Dąbrowski, L.
Suwalski, J.
Neov, S.
Powiązania:
https://bibliotekanauki.pl/articles/147492.pdf
Data publikacji:
2006
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
martensite
diffusion coefficients
Mössbauer specroscopy
X-ray studies
Opis:
Martensite containing 0.87 wt.% carbon was studied by Mössbauer spectroscopy at temperatures, T = 10, 15, 25, 40 and 78 K and by X-ray diffraction at T = 78 K in the course of 35 days. Samples in the form of 30 mm thick foil of pure carbon martensite with enhanced tetragonality were synthesized applying non-standard technology. The measured by X-rays (c/a - 1) ratio varies within the limits 0.044-0.055 by pulsations with a period of few hours. According to Kurdimov’s model any changes in tetragonality of martensite are fully related to the passage of carbon atoms from Oc to Oa and Ob octahedral sites or vice versa. Pulsations of the central and satellite sextets were observed by Mössbauer spectroscopy. In accordance with the conventional interpretation of satellites, these pulsations result from different spatial distribution of carbon around the Fe atoms in the diffusion process. The data of (c/a - 1) pulsations were used to determine the diffusion coefficient below 78 K. The measured diffusion coefficient of carbon in a-iron below 78 K contradicts the classical approach to the observed temperature dependence. As the temperature is lowered below 78 K, the diffusion constant approaches the nearly temperature-independent value. The low temperature branch is apparently characteristic of a quantum mechanical process dominated by tunnelling in the ground state.
Źródło:
Nukleonika; 2006, 51, 2; 101-104
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Study of some physicochemical and rheological properties of irradiated honey
Autorzy:
Bera, A
Almeida-Muradian, L. G.
Sabato, S. F.
Powiązania:
https://bibliotekanauki.pl/articles/147025.pdf
Data publikacji:
2008
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
gamma radiation
honey
rheology
physicochemical properties
Opis:
Honey is a sweet substance produced by bees, well appreciated in many places and its consumption has been increased either as raw material or as a food ingredient. Its use as food by the consumer, or even for exportation, implies safety inherent in its quality and processing control. Gamma radiation can be applied in food or ingredients for many objectives like pathogens microorganisms’ reduction, disinfestations, and sterilization. The aim of this work was to verify some physicochemical modifications, as well as rheological evaluation of honey submitted to irradiation at 10 kGy. The physicochemical parameters analyzed were: moisture, HMF, free acidity, pH, sugars and ash. The rheological behavior was measured at different temperatures. The results indicated that few changes occurred; the rheological behavior was not impaired and did not present any significant physicochemical alteration.
Źródło:
Nukleonika; 2008, 53, suppl. 2; 85-87
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Vitamin E content and sensory qualities of γ-irradiated sunflower whole grain cookies
Autorzy:
Taipina, M. S.
Lamardo, L. C. A.
Rodas, M. A. B.
del Mastro, N. L.
Powiązania:
https://bibliotekanauki.pl/articles/147792.pdf
Data publikacji:
2008
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
ionization radiation
cookies
vitamin E
sensory evaluation
Opis:
The sources of vitamin E in the diet are oils, margarines, seeds, nuts and cereal grains. Industrialized sunflower whole grain cookies were treated with gamma irradiation and evaluated for changes in vitamin E content and sensory properties. Radiation doses were 0.0, 1.0 and 3.0 kGy, the dose rate was 3.5 kGy/h. Irradiation at 1 and 3 kGy resulted in no changes in vitamin E content measured as α-tocopherol equivalents by a colorimetric measurement based method. A sensory panel composed of 22 trained members found that irradiation even at 1 kGy induced certain small, but statistically significant differences in sensory characteristics for appearance, aroma, texture and flavor attributes. From the obtained results, it is possible to conclude that there was a notorious stability of the vitamin content of the product submitted to γ-irradiation at the assayed doses. Meanwhile, irradiation at room temperature of this ready to eat food item caused small but statistically significant effects on sensory (marketing) attributes.
Źródło:
Nukleonika; 2008, 53, suppl. 2; 81-84
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Freeze-out process with in-medium nucleon mass
Autorzy:
Zschocke, S.
Csernai, L.
Molnar, E.
Manninen, J.
Nyiri, A.
Powiązania:
https://bibliotekanauki.pl/articles/148362.pdf
Data publikacji:
2006
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
freeze-out
nucleon mass shift
chiral condensate
heavy-ion collision
Opis:
We investigate the kinetic freeze-out scenario of a nucleon gas through a finite layer. The in-medium mass modification of nucleons and its impact on the freeze-out process is studied. A considerable modification of the thermodynamical parameters temperature, flow-velocity, energy density and particle density has been found in comparison with evaluations which use a constant vacuum nucleon mass.
Źródło:
Nukleonika; 2006, 51,suppl.3; 43-46
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Reprocessability of molybdenum and magnesia based inert matrix fuels
Autorzy:
Ebert, E. L.
Bukaemskiy, A.
Sadowski, F.
Lange, S
Wilden, A.
Modolo, G.
Powiązania:
https://bibliotekanauki.pl/articles/148138.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
CERCER
CERMET
dissolution
inert matrix fuels (IMF)
liquid-liquid extraction
minor actinides
reprocessing
Opis:
This work focuses on the reprocessability of metallic 92Mo and ceramic MgO, which is under investigation for (Pu,MA)-oxide (MA = minor actinide) fuel within a metallic 92Mo matrix (CERMET) and a ceramic MgO matrix (CERCER). Magnesium oxide and molybdenum reference samples have been fabricated by powder metallurgy. The dissolution of the matrices was studied as a function of HNO3 concentration (1–7 mol/L) and temperature (25–90°C). The rate of dissolution of magnesium oxide and metallic molybdenum increased with temperature. While the MgO rate was independent of the acid concentration (1–7 mol/L), the rate of dissolution of Mo increased with acid concentration. However, the dissolution of Mo at high temperatures and nitric acid concentrations was accompanied by precipitation of MoO3. The extraction of uranium, americium, and europium in the presence of macro amounts of Mo and Mg was studied by three different extraction agents: tri-n-butylphosphate (TBP), N,N'-dimethyl-N,N'-dioctylhexylethoxymalonamide (DMDOHEMA), and N,N,N’,N’- -tetraoctyldiglycolamide (TODGA). With TBP no extraction of Mo and Mg occurred. Both matrix materials are partly extracted by DMDOHEMA. Magnesium is not extracted by TODGA (D < 0.1), but a weak extraction of Mo is observed at low Mo concentration.
Źródło:
Nukleonika; 2015, 60, No. 4, part 2; 871-878
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Cyclotron production of 68Ga via proton-induced reaction on 68Zn target
Autorzy:
Sadeghi, M.
Kakavand, T.
Rajabifar, S.
Mokhtari, L.
Rahimi-Nezhad, A.
Powiązania:
https://bibliotekanauki.pl/articles/146448.pdf
Data publikacji:
2009
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
production
gallium-68
zinc-68
PET
cyclotron
Opis:
68Ga is an important positron-emitting radionuclide for positron emission tomography. In this work 68Ga was produced via the 68Zn(p,n)68Ga nuclear reaction. 68Zn electrodeposition on a copper substrate was carried out by alkaline cyanide baths. 68Zn target was irradiated with a 15 MeV proton beam and a 150 mi A current. The production yield achieved was 136 mCi/ mi Aźh (5.032 GBq/mi Aźh). 68Ga was separated from zinc and copper by a combination of cation exchange chromatography and liquid-liquid extraction methods.
Źródło:
Nukleonika; 2009, 54, 1; 25-28
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Uranium and neodymium partitioning in alkali chloride melts using low-melting gallium-based alloys
Autorzy:
Melchakov, S. Y.
Maltsev, D. S.
Volkovich, V. A.
Yamshchikov, L. F.
Lisienko, D. G.
Osipenko, A. G.
Rusakov, M. A.
Powiązania:
https://bibliotekanauki.pl/articles/146407.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
neodymium
uranium
gallium
separation factor
reductive extraction
pyrochemical reprocessing
Opis:
Partitioning of uranium and neodymium was studied in a ‘molten chloride salt – liquid Ga-X (X = In or Sn) alloy’ system. Chloride melts were based on the low-melting ternary LiCl-KCl-CsCl eutectic. Nd/U separation factors were calculated from the thermodynamic data as well as determined experimentally. Separation of uranium and neodymium was studied using reductive extraction with neodymium acting as a reducing agent. Efficient partitioning of lanthanides (Nd) and actinides (U), simulating fission products and fissile materials in irradiated nuclear fuels, was achieved in a single stage process. The experimentally observed Nd/U separation factor valued up to 106, depending on the conditions.
Źródło:
Nukleonika; 2015, 60, No. 4, part 2; 915-920
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
PF-6 an effective plasma focus as a source of ionizing radiation and plasma streams for application in material technology, biology and medicine
Autorzy:
Gribkov, V.
Dubrovsky, A.
Scholz, M.
Jednorog, S.
Karpiński, L.
Tomaszewski, K.
Paduch, M.
Miklaszewski, R.
Pimenov, V.
Ivanov, L. I.
Dyomina, E. V.
Maslyaev, S. A.
Orlova, M. A.
Powiązania:
https://bibliotekanauki.pl/articles/147424.pdf
Data publikacji:
2006
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
dense plasma focus (DPF)
ion beam
plasma beam
X-ray beams
surface damage
microlithography
radioenzymology
positron emission tomography (PET)
Opis:
A review of results on the design and operation of the new efficient Dense Plasma Focus device PF-6 of medium size (transportable) having bank energy of ca. 7 kJ and possessing a long lifetime is presented. New data on the interaction of the pulsed fast ion beams and dense plasma streams generated at this apparatus with various materials are given. These results are compared with the analogous information received at the biggest facility PF-1000. It is shown that it is possible to have about the same power flux density (in the range of 105 109 W/cm2) in both devices however in different areas. Doses of soft X-rays produced by the device within the resists for the goals of microlithography and micromachining appear to be several times less that it is with the conventional X-ray tube. In biological application of this device, medium- and hard-energy X-rays are exploited in the field of radioenzymology. It was found that the necessary dose producing activation/inactivation of enzymes can be by several orders of magnitude lower if used at a high-power flux density in comparison with those received with isotope sources. In medicine, short-life isotope production for the goals of the positron emission tomography (medicine diagnostics) is possible by means of the fast ions generated within DPF. All these experiments are discussed in the framework of pulsed radiation physics and chemistry in its perfect sense thereto the criteria are formulated.
Źródło:
Nukleonika; 2006, 51, 1; 55-62
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Badania chemiczne w Instytucie Chemii i Techniki Jądrowej nad projektowaniem i syntezą nowych radiofarmaceutyków
Autorzy:
Bilewicz, A.
Fuks, L.
Gniazdowska, E.
Kasperek, A.
Koźmiński, P.
Krajewski, S.
Leszczuk, E.
Łyczko, M.
Powiązania:
https://bibliotekanauki.pl/articles/214209.pdf
Data publikacji:
2012
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
Instytut Chemii i Techniki Jądrowej
radiofarmaceutyki
radiobiokoniugat
znakowanie biomolekuł
Źródło:
Postępy Techniki Jądrowej; 2012, 2; 2-13
0551-6846
Pojawia się w:
Postępy Techniki Jądrowej
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
On the nature of changes in the optical characterization produced in sapphire on its irradiation with a pulsed powerful stream of hydrogen ions
Autorzy:
Gribkov, V.
Ivanov, L.
Maslyaev, S.
Pimenov, V.
Sadowski, M.
Skladnik-Sadowska, E.
Banaszak, A.
Kopeć, G.
Cheblukov, Y.
Kozodaev, M. A.
Suvorov, A. L.
Smirnov, I. S.
Powiązania:
https://bibliotekanauki.pl/articles/147991.pdf
Data publikacji:
2004
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
optical characteristics
irradiation
fast ion stream
morphology
Opis:
Changes in the optical characteristics in synthetic sapphire specimens produced by microsecond pulse irradiation with a stream of hydrogen ions of energies ranging up to tens keV have been observed. Data on decrease in the optical reflection, measured within the wavelength range of 200 900 nm, are presented. This characterization is compared with the data received by optical and atomic force microscopy as well as by lattice structure analysis performed with X-rays. The measurements indicate that the changes of optical parameters are not a consequence of absorption increase and/or sapphire decomposition. They result from modifications of the morphology and structure of surface layer of the sapphire samples, induced by irradiation.
Źródło:
Nukleonika; 2004, 49, 2; 43-49
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Neutron emission parameters from the collapse of the condensed Z-pinch
Autorzy:
Anan'ev, S. S.
Bakshaev, Y. L.
Bryzgunov, V. A.
Chernenko, A. S.
Dan'ko, S. A.
Kazakov, E. D.
Klír, D.
Korolev, V. D.
Smirnova, E. A.
Ustroev, G. I.
Vikhrev, V. V.
Powiązania:
https://bibliotekanauki.pl/articles/146662.pdf
Data publikacji:
2012
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
neutrons
energy distribution
fast Z-pinch
Opis:
The parameters of neutron emission from the neck of the condensed Z-pinch, were measured at an S-300 installation (2 MA, 100 ns). Profiled loads with central parts made from microporous deuterated polyethylene (with a density of 100 mg/cm3) were used in the experiments. Neutron emission parameters were measured by the time-of-flight (TOF) method. Neutrons were registered using four flight bases with 10 scintillation detectors which were placed at two axial and two radial directions. It was found that the mean neutron energy, determined by the TOF method, turned out to be anisotropic. The average energy of neutrons emitted along the axis towards the cathode, was shifted to higher energy (2.6-2.8 MeV) and the average energy of neutrons emitted towards the anode, was shifted to lower energy (2.1-2.3 MeV) compared to the d-d reaction neutron energy 2.45 MeV. The average energy of neutrons, emitted in two opposite radial directions, was close to 2.45 MeV. The half-width of the energy distributions reconstructed for all directions was 400-500 keV. The analysis of the experimental results demonstrated that the found phenomena could be explained by a slowly decaying high energy tail in the energy distribution of colliding deuterons. The maximal neutron yield was of 6 x 109.
Źródło:
Nukleonika; 2012, 57, 3; 333-336
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
A study about the measurement method of the homogeneity of radioactivity along an iridium-192 wire used in brachytherapy
Autorzy:
Costa, O. L.
Calvo, W. A. P.
Zeituni, C. A.
Rostelato, M. E. C. M.
Moura, J. A.
Feher, A.
Souza, C. D.
Somessari, S. L.
Powiązania:
https://bibliotekanauki.pl/articles/148238.pdf
Data publikacji:
2014
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
iridium-192
iridium wire
low dose rate brachytherapy
quality control
cancer treatment
radioactive sources production
Opis:
The Nuclear and Energy Research Institute has produced, since 1998, iridium-192 wires used in low dose rate brachytherapy. In the paper the authors studied the influence of wire profile on the homogeneity distribution of radioactivity of iridium-192 along the wire. The authors propose the improvements in the quality control procedure that will provide more accurate measurement data and suggest changes in control devices.
Źródło:
Nukleonika; 2014, 59, 1; 37-39
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Burn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code
Autorzy:
Gholamzadeh, Z.
Feghhi, S. A. H.
Soltani, L.
Rezazadeh, M
Tenreiro, C.
Joharifard, M.
Powiązania:
https://bibliotekanauki.pl/articles/148179.pdf
Data publikacji:
2014
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
ThO2
neutronic parameters
fuel burn-up
233U
235U
239Pu fissile material
Opis:
Decrease of the economically accessible uranium resources and the inherent proliferation resistance of thorium fuel motivate its application in nuclear power systems. Estimation of the nuclear reactor’s neutronic parameters during different operational situations is of key importance for the safe operation of nuclear reactors. In the present research, thorium oxide fuel burn-up calculations for a demonstrative model of a heavy water- -cooled reactor have been performed using MCNPX 2.6 code. Neutronic parameters for three different thorium fuel matrices loaded separately in the modelled thermal core have been investigated. 233U, 235U and 239Pu isotopes have been used as fi ssile element in the thorium oxide fuel, separately. Burn-up of three different fuels has been calculated at 1 MW constant power. 135X and 149Sm concentration variations have been studied in the modelled core during 165 days burn-up. Burn-up of thorium oxide enriched with 233U resulted in the least 149Sm and 135Xe productions and net fi ssile production of 233U after 165 days. The negative fuel, coolant and void reactivity of the used fuel assures safe operation of the modelled thermal core containing (233U-Th) O2 matrix. Furthermore, utilisation of thorium breeder fuel demonstrates several advantages, such as good neutronic economy, 233U production and less production of long-lived α emitter high radiotoxic wastes in biological internal exposure point of view.
Źródło:
Nukleonika; 2014, 59, 4; 129-136
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Characterization of some modern scintillators recommended for use on large fusion facilities in γ-ray spectroscopy and tomographic measurements of γ-emission profiles
Autorzy:
Sibczynski, P.
Broslawski, A.
Gojska, A.
Kiptily, V.
Korolczuk, S.
Kwiatkowski, R.
Mianowski, S.
Moszyński, M.
Rzadkiewicz, J.
Swiderski, L.
Szydlowski, A.
Zychor, I.
Powiązania:
https://bibliotekanauki.pl/articles/146137.pdf
Data publikacji:
2017
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
gamma spectrometry
scintillators
decay time
non-proportionality
energy resolution
detection efficiency
fusion plasma
Opis:
LaBr3:Ce,CeBr3 and GAGG:Ce scintillators were investigated and the determined characteristics were compared with those obtained for the well-known and widely used CsI:Tl and NaI:Tl crystals. All the detectors were of the same size of 10 × 10 × 5 mm3. The aim of this test study was to single out scintillation detectors most suitable for γ-ray spectrometry and γ -ray emission radial profile measurements in high-temperature plasma experiments. Decay time, energy resolution, non-proportionality and full energy peak detection efficiency were measured for γ -ray energies up to 1770 keV. Due to their good energy resolution, short decay time and high detection efficiency for MeV gamma rays, LaBr3:Ce and CeBr3 scintillators are proposed as the best candidates for use especially under conditions of high count rates, which are expected in the forthcoming DT experiments.
Źródło:
Nukleonika; 2017, 62, 3; 223-228
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Leakage test evaluation used for qualification of iodine-125 seeds sealing
Autorzy:
Feher, A.
Rostelato, M. E. C. M.
Zeituni, C. A.
Calvo, W. A. P.
Somessari, S. L.
Moura, J. A.
Moura, E. S.
Souza, C. D.
Rela, P. R.
Powiązania:
https://bibliotekanauki.pl/articles/147662.pdf
Data publikacji:
2011
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
leakage test
iodine-125 seeds
prostate cancer
brachytherapy
titanium tube
standard ISO-9978
Opis:
Brachytherapy is one of the possible treatments with ionizing radiation available for prostate cancer, in which small seeds containing iodine-125 radioisotope are implanted directly into the prostate. The seed consists of a sealed titanium tube containing a central silver wire with adsorbed iodine-125. The tube sealing is made with titanium at the ends, using plasma arc-welding (PAW) or laser process. This sealing must be leakage-resistant and free of cracks, therefore avoiding iodine-125 to deposit in the silver wire to escape and spread into the human body. To ensure that this problem is not occurring, rigorous leakage tests in accordance with the standard ISO-9978 should be applied. The aim of this study is to determine, implement and evaluate the leakage test to be used in the iodine-125 seeds production, in order to qualify the sealing procedure. The standard ISO-9978 presents a list of tests to be carried out according to the type of source. The preferential methods for brachytherapy sources are soaking and helium. To assess the seeds leakage, the method of immersion test at room temperature was applied. The seeds are considered leakage-free if the detected activity does not exceed 185 Bq (5 nCi). An iodine standard was prepared and its value determined in a sodium iodide detector. A liquid scintillation counter was calibrated with the standard for seed leakage tests. Forty-eight seeds were plasma arc-welded for these tests.
Źródło:
Nukleonika; 2011, 56, 4; 375-379
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł

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