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Wyszukujesz frazę "thermal neutron" wg kryterium: Temat

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    Wyświetlanie 1-8 z 8
    Tytuł:
    Analysis of thermal neutron flux measurement in the Cobalt Irradiation Device at ETRR-2
    Autorzy:
    Abou-Zaid, A.
    Powiązania:
    https://bibliotekanauki.pl/articles/148356.pdf
    Data publikacji:
    2003
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    ETRR-2
    CID
    MCNP4B
    thermal neutron flux
    Opis:
    The measurements of geometrical distribution of thermal neutron flux in research reactors are often used in the field of reactor operation and reactor physics. Usually such measurements are carried out by using the gold wire activation method. This method has been used for measuring a thermal neutron flux at the location of a Cobalt Irradiation Device (CID) of ETRR-2. A special device was used for locating samples in an irradiation box and the measurements were performed for seventy-two positions. The Monte Carlo MCNP-4B code has been used for the modeling and simulation of ETRR-2 core with structural materials and surrounding beryllium reflectors. The device used in the flux measurement was also simulated in the MCNP-4B model. The thermal flux has been calculated and compared with the experimental one. The results show good agreement between the measured and calculated flux.
    Źródło:
    Nukleonika; 2003, 48, 4; 211-214
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Anisotropy of the neutron emission from PF-360 facility operated without and with solid-state targets
    Autorzy:
    Czaus, K.
    Baranowski, J.
    Sadowski, M.
    Skladnik-Sadowska, E.
    Zebrowski, J.
    Powiązania:
    https://bibliotekanauki.pl/articles/146908.pdf
    Data publikacji:
    2001
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    anisotropy
    beam-target mechanism
    dense plasma focus (DPF)
    neutron yield
    thermal mechanism
    Opis:
    The paper reports on detailed studies of an anisotropy of the fusion-produced neutrons emitted from the modernized PF-360 facility [10], which has been operated with a pure deuterium-gas filling, without and with some additional solidstate targets containing deuterium atoms. Under standard operational conditions, anisotropy of the neutron yield from the PF-360 facility is similar to that observed in other PF devices. For the first time the neutron emission anisotropy has been measured in the PF experiments performed with a planar cryogenic target covered with a heavy-ice (D2O) layer. Changes in the Yn(Φ)/Yn(90°) ratio, particularly for angles Φ = 0–60°, have been explained by the known features of the angular distribution of fast deuterons.
    Źródło:
    Nukleonika; 2001, 46, suppl. 1; 77-80
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Correction of the electric resistivity distribution of Si wafers using selective neutron transmutation doping (SNTD) in MARIA nuclear research reactor
    Autorzy:
    Tarchalski, M.
    Kordyasz, A. J.
    Pytel, K.
    Dorosz, D.
    Powiązania:
    https://bibliotekanauki.pl/articles/146646.pdf
    Data publikacji:
    2012
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    silicon wafer
    thermal neutron doping
    silicon resistivity homogeneity
    silicon resistivity heterogeneity
    neutron transmutation doping (NTD)
    selective neutron transmutation doping (SNTD)
    MARIA nuclear research reactor
    Opis:
    The result of the electric resistivity distribution modification in silicon wafers, by means of selective neutron transmutation doping (SNTD) method in the MARIA nuclear research reactor at Świerk/Otwock (Poland) is presented. Silicon wafer doping system has been fully designed for the MARIA reactor, where irradiation took place. The silicon wafer resistivity distribution after SNTD has been measured by the capacity voltage (C-V) method. In this article we show first results of this correction technique. The result of the present investigation is that the planar resolution of the correction process is about 4 mm. It is the full width at half maximum (FWHM) of the resistivity distribution produced by thermal neutrons irradiation of Si wafer through a 3 mm hole in the Cd-mask.
    Źródło:
    Nukleonika; 2012, 57, 3; 363-367
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Determination of the mass fraction of 10B in boric acid by the measurement of thermal neutron flux depression
    Autorzy:
    Bolewski Jr, A.
    Ciechanowski, M.
    Kreft, A.
    Powiązania:
    https://bibliotekanauki.pl/articles/146718.pdf
    Data publikacji:
    2012
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    10B
    boric acid
    252Cf neutron source
    Monte Carlo N-particle (MCNP)
    reactor coolant
    thermal neutron absorption
    Opis:
    A thermal neutron absorption technique has been improved with the aid of Monte Carlo N-particle (MCNP) modelling and used for the determination of the mass fraction of 10B in boric acid. A relative standard deviation of that determination has been estimated to be below 0.12%. Owing to the good precision and simplicity, the presented technique could be helpful in nuclear plants with pressurized water reactors, where boric acid is added to the primary circuit coolant to control the chain reaction. Possible applications include the checking of the actual mass fraction of 10B in lots of boric acid delivered to nuclear power plants as well as calibration of instruments used for on-line monitoring the content of 10B in reactor coolants.
    Źródło:
    Nukleonika; 2012, 57, 4; 537-544
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Gamma Induced Positron Annihilation: History, Current, and Future Developments
    Autorzy:
    Selim, F.
    Powiązania:
    https://bibliotekanauki.pl/articles/1030020.pdf
    Data publikacji:
    2017-11
    Wydawca:
    Polska Akademia Nauk. Instytut Fizyki PAN
    Tematy:
    gamma induced positron spectroscopy
    positron transient measurements
    thermal neutron capture
    proton capture
    electron accelerator
    Van de Graaff accelerator
    Opis:
    Positron annihilation spectroscopy is often performed using radioactive sources for bulk measurements or positron beams for depth resolved measurements. Both have many advantages and great capabilities for a variety of applications. In the recent history, we have shown that positron annihilation spectroscopy can be carried out directly using high energy photons without the need for positron source or positron beam. This approach brings unique capabilities for some specific applications and promotes the use of positron annihilation spectroscopy in new areas of materials science and probably in industrial applications. Some of the important applications include developing new nondestructive highly penetrating sensitive probe for structural and engineering materials. It can also greatly advance positron applications in bulk semiconductors, electronic and photonic materials as well as in polymers, ceramics, and liquids. The recently developed γ-induced positron spectroscopy in HZDR in Dresden provides an example of an excellent facility for many of these applications. When incorporated with pulsed accelerators, γ-induced positron annihilation spectroscopy may trigger novel studies of transient states in matter and explore several solid-state processes that take place on short time scale. In this article I will review the history and development of the technique and its incorporation in a wide range of accelerators including table top electron accelerators, pulsed electron accelerators, and Van de Graaff accelerators. Then I will introduce a design for a new γ-induced positron annihilation spectroscopy facility based on using small nuclear research reactors or neutron generators. The paper presents all the possible approaches for γ-induced positron annihilation spectroscopy and discusses its potential and limitations to guide the efforts in further development of the technique and illustrate the unique aspects that the technique can bring to positron science and applications.
    Źródło:
    Acta Physica Polonica A; 2017, 132, 5; 1450-1455
    0587-4246
    1898-794X
    Pojawia się w:
    Acta Physica Polonica A
    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:
    Peculiarities of neutron interaction with boron containing semiconductors
    Autorzy:
    Didyk, A. Y.
    Hofman, A.
    Szteke, W.
    Hajewska, E.
    Vlasukova, L. A.
    Powiązania:
    https://bibliotekanauki.pl/articles/148104.pdf
    Data publikacji:
    2009
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    semiconductors
    thermal neutrons
    point defects
    vacancies
    damage concentration
    thermal neutron fluence
    cross-section of damage creation
    fission fragments
    lithium
    helium
    alfa-particles
    diffusion of impurities
    homogeneity of damage and active impurities
    Opis:
    Abstract. The results of point defect creation calculation in B4C, BN and BP semiconductor single crystals irradiated in the fast neutron reactor IBR-2 are presented. It has been shown that during the thermal neutron interaction with light isotope boron atoms (10B) the damage creation by means of fission nuclear reaction fragments (alfa-particles and 7Li recoil nuclei) exceeds the damage created by fast neutrons (En greater than 0.1 MeV) by more than two orders of value. It has been concluded that such irradiation can create a well developed radiation defect structure in boron-containing crystals with nearly homogeneous vacancy depth distribution. This may be used in technological applications for more effective diffusion of impurities implanted at low energies or deposited onto the semiconductor surface. The developed homogeneous vacancy structure is very suitable for the radiation enhanced diffusion of electrically charged or neutral impurities from the surface into the technological depth of semiconductor devices under post irradiation treatment.
    Źródło:
    Nukleonika; 2009, 54, 3; 163-168
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Thermal neutron radiography studies of drying of rectangular blocks of wet mortar
    Autorzy:
    Fijał-Kirejczyk, I. M.
    Milczarek, J. J.
    de Beer, F. C.
    Radebe, M. J.
    Nothnagel, G.
    Żołądek-Nowak, J.
    Powiązania:
    https://bibliotekanauki.pl/articles/146714.pdf
    Data publikacji:
    2012
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    drying
    capillary-porous media
    mortar
    thermal neutron radiography
    Opis:
    The convectional drying of rectangular block of wet mortar was investigated with thermal neutron radiography technique supplemented with traditional mass and temperature measurements. The time evolution of the drying process was recorded for rectangular sample of aged mortar before and after painting its lateral sides. The receding boundary of the central core wet region was observed in the advanced stage of the process. The size, shape and water content of that region were determined for both cases of non-painted and painted sample. It was shown that in the advanced drying process the receding drying front exists irrespectively of the drying pattern observed at the early period of drying.
    Źródło:
    Nukleonika; 2012, 57, 4; 529-535
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
      Wyświetlanie 1-8 z 8

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