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Wyszukujesz frazę "M. S. R." wg kryterium: Autor


Tytuł:
R&D on divertor plasma facing components at the Institute for Plasma Research
Autorzy:
Patil, Y.
Khirwadkar, S.
Belsare, S. M.
Swamy, R.
Khan, M. S.
Tripathi, S.
Bhope, K.
Powiązania:
https://bibliotekanauki.pl/articles/146770.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
divertor
plasma facing material
high heat fl ux test
transient IR thermography
Opis:
This paper is focused on various aspects of the development and testing of water cooled divertor PFCs. Divertor PFCs are mainly designed to absorb the heat and particle fluxes out flowing from the core plasma of fusion devices like ITER. The Divertor and First Wall Technology Development Division at the Institute for Plasma Research (IPR), India, is extensively working on development and testing of divertor plasma facing components (PFCs). Tungsten and graphite macro-brush type test mock-ups were produced using vacuum brazing furnace technique and tungsten monoblock type of test mock-ups were obtained by hot radial pressing (HRP) technique. Heat transfer performance of the developed test mock-ups was tested using high heat flux tests with different heat load conditions as well as the surface temperature monitoring using transient infrared thermography technique. Recently we have established the High Heat Flux Test Facility (HHFTF) at IPR with an electron gun EH300V (M/s Von Ardenne Anlagentechnik GmbH, Germany) having maximum power 200 kW. Two tungsten monoblock type test mock-ups were probed using HHFTF. Both of the test mock-ups successfully sustained 316 thermal cycles during high heat fl ux (HHF) tests. The test mock-ups were non- -destructively tested using infrared thermography before and after the HHF tests. In this note we describe the detailed procedure used for testing macro-brush and monoblock type test mock-ups using in-house transient infrared thermography set-up. An acceptance criteria limit was defined for small scale macro-brush type of mock-ups using DTrefmax value and the surface temperature measured during the HHF tests. It is concluded that the heat transfer behavior of a plasma facing component was checked by the HHF tests followed by transient IR thermography. The acceptance criteria DTrefmax limit for a graphite macro-brush mock-up was found to be ~3centi grade while for a tungsten macro-brush mock-up it was ~5centi grade.
Źródło:
Nukleonika; 2015, 60, 2; 285-288
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Radionuclides 137Cs and 40K in the soils of the Tatra National Park (TPN, Poland)
Autorzy:
Kubica, B.
Skiba, S.
Drewnik, M.
Stobiński, M.
Kubica, M.
Gołaś, J.
Misiak, R.
Powiązania:
https://bibliotekanauki.pl/articles/148560.pdf
Data publikacji:
2010
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
137Cs
40K
Tatra Mts.
gamma spectrometry
maps of the radioisotopes
Opis:
The paper presents the results of radioactivity determination of artificial 137Cs and natural 40K in soil samples taken from the Tatra Mountains in Poland (Tatra National Park – TPN). Soil samples were collected as the cores of 10 cm in diameter and 10 cm in depth. These cores were divided into 3 slices. It has been found that the content of 137Cs was the highest at the sites of the altitude over 1300 m a.s.l. The values of 137Cs concentration in the soils examined varied – from 55.8 Bqźkg–1 (dry mass) (417.8 Bqźm–2) for the Tomanowa Pass (1685 m a.s.l.) to 5111 Bqźkg–1 (dry mass) (8400 Bqźm–2) for the Krzyzne Pass (2112 m a.s.l.). In most cases, the values were lower than the average radiocaesium concentration established for Poland.
Źródło:
Nukleonika; 2010, 55, 3; 377-386
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Preparation and biodistribution of 99mTc-IgG-HYNIC in normal rats
Autorzy:
Rajabifar, S.
Akhlaghi, M.
Jalilian, A. R.
Bolourinovin, F.
Maashkar, B.
Talebimehrdar, M.
Ghafouri, M.
Powiązania:
https://bibliotekanauki.pl/articles/148161.pdf
Data publikacji:
2009
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
99mTc
HIG
HYNIC
IgG-hynic
infection
inflammation
Opis:
Human gamma globulin can be labeled by a direct or indirect method of radiotracer incorporated in a protein molecule. In this indirect method hydrazinonicotinic acid (HYNIC) is used which saves the structure and biological activity of the protein. Our goal was the efficient labeling of the human gamma globulin and evaluation of its biodistribution in different organs which can be used on experimentally induced infection causing inflammation. Immune globulin is mixed with s-hynic and IgG-hynic is developed using sidle A-lyzer and stored at –20°C which can be used at least for six months and then Sn-tricine kit is prepared which is used for 99mTc labeling. Efficiency of 99mTc-IgG-hynic labeling at pH 6.4 was very much dependent on ligand (hynic) and coligand (tricine) presence in the reaction mixture. Radiochemical purity was more than 90% in the kits prepared. Serum stability study showed no decomposition of 99mTc from the complex. The biodistribution studies showed the highest percentage ID/organ in the blood, liver and kidney, respectively. A human gamma globulin was successfully labeled through hynic to 99mTc by an indirect method with high radiochemical purity.
Źródło:
Nukleonika; 2009, 54, 4; 279-284
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Investigation of thermal neutron detection capability of a CdZnTe detector in a mixed gamma-neutron radiation field
Autorzy:
Yücel, H.
Narttürk, R. B.
Zümrüt, S.
Gedik, G.
Karadag, M.
Powiązania:
https://bibliotekanauki.pl/articles/146914.pdf
Data publikacji:
2018
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
neutron detection
CdZnTe
prompt gamma ray
thermal neutron
cadmium
neutron sensitivity
241Am-Be source
Opis:
The aim of this study was to investigate the thermal neutron measurement capability of a CdZnTe detector irradiated in a mixed gamma-neutron radiation fi eld. A CdZnTe detector was irradiated in one of the irradiation tubes of a 241Am-Be source unit to determine the sensitivity factors of the detector in terms of peak count rate (counts per second [cps]) per neutron flux (in square centimeters per second) [cps/neutron•cm–2•s–1]. The CdZnTe detector was covered in a 1-mm-thick cadmium (Cd) cylindrical box to completely absorb incoming thermal neutrons via 113Cd(n,γ) capture reactions. To achieve, this Cd-covered CdZnTe detector was placed in a well-thermalized neutron fi eld (f-ratio = 50.9 ± 1.3) in the irradiation tube of the 241Am-Be neutron source. The gamma-ray spectra were acquired, and the most intense gamma-ray peak at 558 keV (0.74 γ/n) was evaluated to estimate the thermal neutron fl ux. The epithermal component was also estimated from the bare CdZnTe detector irradiation because the epithermal neutron cutoff energy is about 0.55 eV at the 1-mm-thick Cd filter. A high-density polyethylene moderating cylinder box can also be fi tted into the Cd fi lter box to enhance thermal sensitivity because of moderation of the epithermal neutron component. Neutron detection sensitivity was determined from the measured count rates from the 558 keV photopeak, using the measured neutron fluxes at different irradiation positions. The results indicate that the CdZnTe detector can serve as a neutron detector in mixed gamma-neutron radiation fields, such as reactors, neutron generators, linear accelerators, and isotopic neutron sources. New thermal neutron filters, such as Gd and Tb foils, can be tested instead of the Cd filter due to its serious gamma-shielding effect.
Źródło:
Nukleonika; 2018, 63, 3; 59-64
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Radiation stability of 125I-brachytherapy sources
Autorzy:
Saxena, S.
Ram, R.
Dash, A.
Joshi, P.
Venkatesh, M.
Powiązania:
https://bibliotekanauki.pl/articles/148254.pdf
Data publikacji:
2007
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
retinoblastoma
125 I-brachytherapy sources
radiation stability
SEM
leach rate
Opis:
Low energy 125I-brachytherapy sources are used for the treatment of retinoblastoma and many other forms of eye cancer. Such sources were prepared by adsorption of 125I on palladium coated silver rods and were critically evaluated for safety aspects, as per AERB standards. In order to attain low leachability and to facilitate leak free laser encapsulation of sources within titanium capsules of size 0.8 mm (f) ´ 4.75 mm (l), the radioactive source core was coated with polystyrene. With a view to study the radiation stability of such sources over a period of three weeks, both polymer coated radioactive sources and inactive source cores were separately subjected to an integrated gamma dose of ~(17.85 ´ 104) Gy (17.85 MRad), which is the dose expected to be received in three weeks from a source containing ~ 111 MBq of 125I. This was carried out to test their suitability for reuse within such period. SEM pictures of inactive source cores were taken to observe the effect of gamma radiation on palladium coating. Post-irradiation leachability and uniformity of activity of radioactive sources were evaluated and found to be satisfactory. The sources were found to be reusable safely, for repeated brachytherapy procedures over a practically useful time of at least three weeks.
Źródło:
Nukleonika; 2007, 52, 1; 13-16
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Determination of the emission rate for the 14 MeV neutron generator with the use of radio-yttrium
Autorzy:
Laszynska, E.
Jednorog, S.
Ziolkowski, A.
Gierlik, M.
Rzadkiewicz, R.
Powiązania:
https://bibliotekanauki.pl/articles/146115.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
14 MeV neutron generator
activation method
yttrium activation
Opis:
The neutron emission rate is a crucial parameter for most of the radiation sources that emit neutrons. In the case of large fusion devices the determination of this parameter is necessary for a proper assessment of the power release and the prediction for the neutron budget. The 14 MeV neutron generator will be used for calibration of neutron diagnostics at JET and ITER facilities. The stability of the neutron generator working parameters like emission and angular homogeneity affects the accuracy of calibration other neutron diagnostics. The aim of our experiment was to confi rm the usefulness of yttrium activation method for monitoring of the neutron generator SODERN Model: GENIE 16. The reaction rate induced by neutrons inside the yttrium sample was indirectly measured by activation of the yttrium sample, and then by means of the γ-spectrometry method. The pre-calibrated HPGe detector was used to determine the yttrium radioactivity. The emissivity of neutron generator calculated on the basis of the measured radioactivity was compared with the value resulting from its electrical settings, and both of these values were found to be consistent. This allowed for a positive verifi cation of the reaction cross section that was used to determine the reaction rate (6.45 × 10–21 reactions per second) and the neutron emission rate (1.04 × 108 n·s–1). Our study confi rms usefulness of the yttrium activation method for monitoring of the neutron generator.
Źródło:
Nukleonika; 2015, 60, 2; 319-322
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Recent studies of irradiated mangoes in Brazil : a trend towards commercial approach
Autorzy:
Sabato, S. F.
Silva, J. M.
Cruz, J. N.
Broisler, P. O.
Rela, P. R.
Salmieri, S.
Lacroix, M.
Powiązania:
https://bibliotekanauki.pl/articles/148822.pdf
Data publikacji:
2008
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
gamma radiation
mangoes
physicochemical properties
sensory evaluation
Opis:
Mango is an important commodity to our country as Brazil is a great producer and exporter of tropical fruits. Nowadays, Mexico and India are the main exporters of mango in the world and Brazil occupies the third position in this ranking. As these countries have adopted gamma radiation as a phytosanitary treatment and signed a bilateral agreement with the United States for exporting mango to this country, Brazil has to be up-to-dated with this trend. The Institute of Nuclear and Energy Researches together with field producers in the northeastern region and partners like the International Atomic Energy Agency, the Canadian Irradiation Center and Empresa Brasileira de Agropecuária joined to demonstrate this technology, its application and its commercial feasibility. The whole project was structured in two parts that involved around 1300 mangoes. The first step consisted mainly in studying the quality of irradiated mangoes within our territory, using a multipurpose semi-commercial cobalt facility, and comparing two harvesting points of the fruits. The second one was an international consignment of irradiated fruits from Brazil to Canada, where the control sample consisted of fruits treated with a hot water dip. The financial part of the feasibility study covers the scope of the investment, including the net working capital and production costs. In a summarized way to express, the results from physicochemical analysis and sensory evaluation were favorable, indicating that gamma radiation is a potential quarantine treatment.
Źródło:
Nukleonika; 2008, 53, suppl. 2; 77-79
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Comparison of optical spectra recorded during DPF-1000U plasma experiments with gas-puffing
Autorzy:
Zaloga, D. R.
Skladnik-Sadowska, E.
Kubkowska, M.
Ladygina, M. S.
Malinowski, K.
Kwiatkowski, R.
Sadowski, M. J.
Paduch, M.
Zielinska, E.
Makhlaj, V. A.
Powiązania:
https://bibliotekanauki.pl/articles/147780.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
electron density
gas-puff
optical spectrum
plasma focus
plasma stream
Opis:
The results are presented of the optical spectra measurements for free plasma streams generated with the use of the modifi ed DPF-1000U machine. This facility was recently equipped with a gas injection system (the so-called gas-puff) placed on the symmetry axis behind the central opening in the inner electrode. The DPF-1000U experimental chamber was fi lled up with pure deuterium at the initial pressure of 1.6 or 2.4 mbar. Additionally, when the use was made of the gas-puff system about 1 cm3 of pure deuterium was injected at the pressure of 2 bars. The gas injection was initiated 1.5 or 2 ms before the triggering of the main discharge. The investigated plasma discharges were powered from a condenser bank charged initially to 23 kV (corresponding to the energy of 352 kJ), and the maximum discharge current amounted to about 1.8 MA. In order to investigate properties of a dense plasma column formed during DPF-1000U discharges the use was made of the optical emission spectroscopy. The optical spectra were recorded along the line of sight perpendicular to the vacuum chamber, using a Mechelle®900 spectrometer. The recent analysis of all the recorded spectra made it possible to compare the temporal changes in the electron density of a freely propagating plasma stream for discharges without and with the gas-puffing. Using this data an appropriate mode of operation of the DPF-1000U facility could be determined.
Źródło:
Nukleonika; 2015, 60, 2; 309-314
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Preparation and quality control of lutetium-177 bleomycin as a possible therapeutic agent
Autorzy:
Yousefnia, H.
Jalilian, A. R.
Zolghadri, S.
Bahrami-Samani, A.
Shirvani-Arani, S.
Ghannadi-Maragheh, M.
Powiązania:
https://bibliotekanauki.pl/articles/148628.pdf
Data publikacji:
2010
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
bleomycin
Lu-177
biodistribution
radiolabeling
Opis:
Due to interesting therapeutic properties of 177Lu and antineoblastic antibiotic, bleomycin (BLM), 177Lu-bleomycin (177Lu-BLM) was developed as a possible therapeutic compound. Lu-177 of 2.6-3 GBq/mg specific activity was obtained by irradiation of a natural Lu2O3 sample with a thermal neutron flux of 4 × 1013 nźcm-2źs-1. The product was converted into chloride form which was further used for labeling of BLM. In optimized conditions a radiochemical purity of 98% was obtained for 177Lu-BLM shown by instant thin-layer chromatography (ITLC) (specific activity, 740 GBq/mmole). Biodistribution studies of Lu-177 chloride and 177Lu-BLM were performed in wild-type rats. The accumulation of the radiolabeled compound in lungs, liver and spleen demonstrates a pattern similar to the other radiolabeled bleomycins. Lu-BLM is a possible therapeutic agent in human malignancies and the efficacy of the compound should be tested in various tumor-bearing models.
Źródło:
Nukleonika; 2010, 55, 3; 285-291
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Studies of plasma interactions with tungsten targets in PF-1000U facility
Autorzy:
Ladygina, M. S.
Skladnik-Sadowska, E.
Zaloga, D. R.
Sadowski, M. J.
Kubkowska, M.
Kowalska-Strzeciwilk, E.
Krawczyk, N.
Paduch, M.
Miklaszewski, R.
Garkusha, I. E.
Powiązania:
https://bibliotekanauki.pl/articles/147524.pdf
Data publikacji:
2016
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
plasma-surface interaction
plasma streams
tungsten
plasma focus
PF-1000U
Opis:
This paper presents results of experimental studies of tungsten samples of 99.95% purity, which were irradiated by intense plasma-ion streams. The behaviour of tungsten, and particularly its structural change induced by high plasma loads, is of great importance for fusion technology. The reported measurements were performed within a modifi ed PF-1000U plasma-focus facility operated at the IFPiLM in Warsaw, Poland. The working gas was pure deuterium. In order to determine the main plasma parameters and to study the behaviour of impurities at different instants of the plasma discharge, the optical emission spectroscopy was used. The dependence of plasma parameters on the initial charging voltage (16, 19 and 21 kV) was studied. Detailed optical measurements were performed during interactions of a plasma stream with the tungsten samples placed at the z-axis of the facility, at a distance of 6 cm from the electrode outlets. The recorded spectra showed distinct WI and WII spectral lines. Investigation of a target surface morphology, after its irradiation by intense plasma streams, was performed by means of an optical microscope. The observations revealed that some amounts of the electrodes material (mainly copper) were deposited upon the irradiated sample surface. In all the cases, melted zones were observed upon the irradiated target surface, and in experiments performed at the highest charging voltage there were formed some cracks.
Źródło:
Nukleonika; 2016, 61, 2; 149-153
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
The source of X-rays and high-charged ions based on moderate power vacuum discharge with laser triggering
Autorzy:
Alkhimova, M. A.
Vovchenko, E. V.
Melekhov, A. P.
Ramakoti, R. S.
Savelov, A. S.
Krapiva, P. S.
Moskalenko, I. N.
Powiązania:
https://bibliotekanauki.pl/articles/146864.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
laser-triggered vacuum discharge
sources of X-rays
ion composition of plasma
Opis:
The source of X-ray radiation with the energy of quanta that may vary in the range hv = 1÷12 keV was developed for studies in X-ray interaction with matter and modifi cation of solid surfaces. It was based on a vacuum spark discharge with the laser triggering. It was shown in our experiments that there is a possibility to adjust X-ray radiation spectrum by changing the confi guration of the electrode system when the energy stored in the capacitor is varied within the range of 1÷17 J. A comprehensive study of X-ray imaging and quanta energy was carried out. These experiments were carried out for the case of both direct and reverse polarity of the voltage on the electrodes. Additionally, ion composition of plasma created in a laser-triggered vacuum discharge was analyzed. Highly charged ions Zn(+21), Cu(+20) and Fe(+18) were observed.
Źródło:
Nukleonika; 2015, 60, 2; 221-227
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Preparation, quality control and biodistribution studies of 165Dy-chitosan for radiosynovectomy
Autorzy:
Shirvani-Arani, S.
Mahmoodabadi, A.
Bahrami-Samani, A.
Jalilian, A. R.
Mazidi, M.
Afarideh, H.
Ghannadi-Maragheh, M.
Powiązania:
https://bibliotekanauki.pl/articles/147619.pdf
Data publikacji:
2011
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
radiosynovectomy
Dy-165
chitosan
biodistribution
Opis:
The preparation of 165Dy-labeled chitosan for radiosynovectomy applications is described in this paper. 165Dy (T1/2 = 2.33 h) was prepared by irradiation of natural Dy(NO3)3 at a flux of 3.4 x 1013 neutrons/cm2.s for about 6 h. The irradiation resulted in the production of 11.1 GBq (300 mCi) of 165Dy activity. Emitting gamma ray (94.7 keV) and beta particles (Emax = 1.3 MeV, 83%) 165Dy decays to 165Ho. Eight hours after bombardment, the corresponding specific activity was 703 MBq/mg (19 mCi/mg). The irradiated target was dissolved in 0.1 N HCl solution. Radionuclidic purity was ascertained by high resolution gamma spectrometry. Chitosan solution was prepared in acetic acid solution (pH 3). The chitosan solution was labeled with 165Dy to prepare 165Dy-chitosan (165Dy-Chit) complex (labeling yield, greater than 99% and specific activity small tilde 3.7 TBq/mmol). In optimized conditions (pH 3, 35 mg/4 ml chitosan acidic solution, and 370 MBq of 165Dy) Chit was stable after 48 h. Bioevaluation of the prepared 165Dy-Chit was carried out by injecting 37 MBq (1 mCi, 50.100 mi1) directly into the knee joints of wild rats. Free 165Dy cation was also injected to study the effect of complex formation on the retention of radionuclide in the administered site. To study the consequence of radioactivity leakage from the administration site, a dilute sample of the complex was injected intravenously into the rats followed by biodistribution studies. It was observed that there was no significant extra-articular leakage of the injected activity over the study period of 24 h post-injection.
Źródło:
Nukleonika; 2011, 56, 4; 277-282
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Preparation and biodistribution of [67Ga]-insulin for SPECT purposes
Autorzy:
Jalilian, A. R.
Garousi, J.
Gholami, E.
Akhlaghi, M.
Bolourinovin, F.
Rajabifar, S.
Powiązania:
https://bibliotekanauki.pl/articles/971522.pdf
Data publikacji:
2007
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
radiogallium
insulin
radiolabeling
biodistribution
radiopharmaceutical
cyclotron
Opis:
Human recombinant insulin was successively labeled with [67Ga]-gallium chloride after conjugation with freshly prepared cyclic DTPA-dianhydride (ccDTPA). The best results of the conjugation were obtained by the addition of 0.5 ml of an insulin pharmaceutical solution (5 mg/ml, in phosphate buffer, pH = 8) to a glass tube precoated with DTPA-dianhydride (0.01 mg) at 25°C with continuous mild stirring for 30 min. Radiothin-layer chromatography (RTLC), instant thin-layer chromatography (ITLC) and high-performance liquid chromatography (HPLC) showed overall radiochemical purity higher than 96% in optimized conditions (specific activity = 300 500 MBq/mg, labeling efficiency 77%). Preliminary in vivo studies with normal rats were performed to determine the biodistribution of the radiotracer up to 110 h. They showed a high liver uptake of the tracer which is consistent with other reported radiolabeled insulins.
Źródło:
Nukleonika; 2007, 52, 4; 145-151
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:
Study of tungsten surface interaction with plasma streams at DPF-1000U
Autorzy:
Ladygina, M. S.
Skladnik-Sadowska, E.
Zaloga, D. R.
Malinowski, K.
Sadowski, M. J.
Kubkowska, M.
Kowalska-Strzeciwilk, E.
Paduch, M.
Zielinska, E.
Miklaszewski, R.
Garkusha, I. E.
Gribkov, V. A.
Powiązania:
https://bibliotekanauki.pl/articles/147638.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
DPF-1000U
electron density
gas puffing
plasma stream
tungsten
Opis:
In this note experimental studies of tungsten (W) samples irradiated by intense plasma-ion streams are reported. Measurements were performed using the modified plasma focus device DPF-1000U equipped with an axial gas-puffing system. The main diagnostic tool was a Mechelle®900 optical spectrometer. The electron density of a freely propagating plasma stream (i.e., the plasma stream observed without any target inside the vacuum chamber) was estimated on the basis of the half-width of the Dβ spectral line, taking into account the linear Stark effect. For a freely propagating plasma stream the maximum electron density amounted to about 1.3 × 1017 cm–3 and was reached during the maximum plasma compression. The plasma electron density depends on the initial conditions of the experiments. It was thus important to determine first the plasma flow characteristics before attempting any target irradiation. These data were needed for comparison with plasma characteristics after an irradiation of the investigated target. In fact, spectroscopic measurements performed during interactions of plasma streams with the investigated W samples showed many WI and WII spectral lines. The surface erosion was determined from mass losses of the irradiated samples. Changes on the surfaces of the irradiated samples were also investigated with an optical microscope and some sputtering and melting zones were observed.
Źródło:
Nukleonika; 2015, 60, 2; 293-296
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł

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