يعرض 1 - 10 نتائج من 19 نتيجة بحث عن '"radiation damage"', وقت الاستعلام: 1.45s تنقيح النتائج
  1. 1

    المصدر: Physics of Metals and Metallography. 121:508-519

    الوصف: The nuclear transmutation effects in zirconium alloys are analyzed in this work. The molybdenum content in zirconium alloys of various compositions are numerically estimated under irradiation in research (SM-3) and power (WWER-1000) nuclear reactors. The dynamics of molybdenum accumulation under irradiation in the SM-3 reactor and subsequent one-year aging of samples is estimated in the Zr–1% Nb and Zr–2.5% Nb standard zirconium alloys and the proposed Zr–1% Nb–0.5% Mo and Zr–2.5% Nb–0.5% Mo starting compositions.

  2. 2

    المؤلفون: R. E. Voskoboinikov

    المصدر: Physics of Metals and Metallography. 121:14-20

    الوصف: The process of radiation damage formation in collision cascades initiated by primary knock-on atoms (PKAs) with energy EPKA = 5, 10, 15, and 20 keV in nickel at temperatures T = 100, 300, 600, 900, and 1200 K was studied using the molecular dynamics method. To ensure the statistical validity of the results, a series of 24 cascades was modeled for each pair of (EPKA, T) parameters. The simulation results were analyzed to determine the number NFP of Frenkel pairs, fractions of vacancies σvac and interstitial atoms σSIA in clusters of point defects, average sizes of vacancy 〈Nvac〉 and interstitial 〈NSIA〉 clusters, and average numbers of vacancy 〈Yvac〉 and interstitial 〈YSIA〉 clusters produced in collision cascades as functions of the PKA energy and simulation temperature. It was found that the relation 〈NFP〉 = 2 ± 0.9 × $$E_{\text{PKA}}^{{1.1 \pm 0.1}}$$ holds true at all the examined values of (EPKA, T). The functional dependences of 〈σvac〉 and 〈σSIA〉 on EPKA were identical. The dependence of 〈σvac〉 follows that of 〈Yvac〉, while 〈σSIA〉 is governed by 〈NSIA〉 and the mobility of interstitials. The value of 〈Nvac〉 depends on the irradiation temperature and the thermal stability of vacancy clusters. These clusters are stable at T ≤ 300 K, and 〈Nvac〉 ∝ EPKA; at 600 ≤ T ≤ 900 K, 〈Nvac〉 ≈ 6 and 10, which corresponds to the sizes of regular stacking fault tetrahedra. The value of 〈YSIA〉 is proportional to 〈NFP〉 and, consequently, to EPKA in the entire range of PKA energies.

  3. 3

    المصدر: Journal of Surface Investigation: X-ray, Synchrotron and Neutron Techniques. 14:24-30

    الوصف: Metal hydrides and their alloys are widely used in nuclear power engineering and are regarded as promising hydrogen accumulators. Due to the nature of materials used in reactors, nondestructive methods are required to determine the concentration of hydrogen and its content in hydrides under the influence of a harsh environment. In this paper, a technique based on nuclear backscattering spectrometry is proposed, which allows determination of the hydrogen content in a sample at a depth of up to 100 μm. The profiles of the hydrogen distribution in Al, Mg, Ti, Zr, and their hydrides are measured. Estimation of the radiation damage to the sample is performed using the example of polymer impregnation of the protective coating.

  4. 4

    المصدر: Biology Bulletin. 46:1619-1624

    الوصف: A correlation between the effectiveness of the radioprotective action of cysteamine with the radiosensitivity of cells and their ability to recover from radiation damage was demonstrated for diploid yeast cells of S. cerevisiae. To demonstrate the involvement of the recovery processes in the mechanism for radioprotective action of the T1023 compound in animals, data on the survival of clonogenic bone marrow cells of mice exposed to ionizing radiation are presented. It is shown that the radioprotective effect of this compound can be realized not only at the physicochemical stage of formation of radiation damage due to a decrease in the oxygen content in tissues but also due to the post-radiation cell recovery at the biochemical stage. This is confirmed by the presence of the sigmoid part of the dose-response curve in the region of low doses of ionizing radiation.

  5. 5

    المصدر: Physics of Atomic Nuclei. 82:1252-1262

    الوصف: The new results of cathode surface degradation in muon proportional chambers of CMS after a long-term irradiation with a 90Sr β-source are presented. The data of the complex analysis of the copper foil samples from the cathode are shown. The AFM method revealed the general radiation damage of the copper surface and the dynamics of its change. It is clearly demonstrated that the revealed development of the radiation erosion on the cathode is a result of electron irradiation. Moreover, the nature of erosion and level of the destruction of copper are associated with irradiation intensity. The study of the elemental and phase composition together with the data of structural analysis allowed us to single out the stages of the radiation aging of the copper surface on the cathodes and consider the processes which are at the basis of them.

  6. 6

    المصدر: Journal of Surface Investigation: X-ray, Synchrotron and Neutron Techniques. 13:802-808

    الوصف: The results of a comparative experimental study of the structure and morphology of high-temperature glassy carbon of brand SU-2500 after high-fluence (1018 cm–2 and higher) irradiation with 30-keV Ar+ ions in the temperature range of 60–600°С and glassy carbon samples after treatment at temperatures of 850, 1300, 2000, and 2500°С are reported and discussed. The Raman spectra of irradiated glassy carbon SU-2500 show the amorphous state of the surface layer after irradiation at temperatures below that of dynamic annealing of radiation damage, which is determined from the temperature dependence of the ion-induced electron emission yield, a graphite-like state after irradiation at temperatures of 150–250°С, and a structure typical of glassy carbon samples treated at elevated temperatures after irradiation at temperatures in the range of 250 < T ≤ 600°С. Ion irradiation under conditions of the dynamic annealing of radiation damage leads to a сellular topography, i.e., nanowalls connected by nodes. The sizes of the structure cells are about 150 and 300 nm after irradiation at temperatures of 250 and 600°С, respectively.

  7. 7

    المصدر: Physical Mesomechanics. 22:355-364

    الوصف: Molecular dynamics simulations have been performed to investigate the defect structure evolution at different development stages of atomic displacement cascades with energies up to 50 keV in iron crystallites in the temperature range from 300 to 900 K. The number of surviving radiation defects in iron crystallites increases according to a power law with increasing energy of the primary knocked-on atom. An increase in the crystallite temperature slightly increases the number of surviving defects. It is found that atomic displacement cascades can lead to radiation-induced grain boundary migration due to the melting and crystallization of the radiation-damaged region. The crystallographic orientation of the irradiated free surface strongly affects the radiation damage behavior. Craters with adatom islands are formed on the (111) free surface, and vacancy loops are nucleated in the (110) near-surface region. Point defects aggregate into clusters of various types during the evolution of atomic displacement cascades. It is shown that the number of surviving point defect clusters can significantly decrease under uniaxial elastic compression.

  8. 8

    المؤلفون: Y. N. Kharzheev

    المصدر: Physics of Particles and Nuclei. 50:42-76

    الوصف: Scintillation detectors (SD) based on organic plastic scintillators and optical fibers are basic detectors at all modern accelerators and in astrophysics and neutrino physics experiments. In recent years, interest in SD has significantly increased due to the upcoming major upgrade of the LHC and the construction of new accelerators NICA, FAIR, FCC, etc. At the same time, requirements on the stability and reliability of SD operation under new conditions have become stricter, and their fulfillment largely depends on radiation hardness of scintillators, optical fibers, and photodetectors. The review presents the results of the radiation hardness investigations of various scintillators, optical fibers (scintillating, as well as wavelength-shifting and clear), and optical glues used to increase light collection from scintillators by fibers. The influence of various factors (dose, dose rate, type of radiation, scintillator materials, and fluors) on light output, light collection, and transmittance of the irradiated materials and their recovery is considered. Aging of scintillators caused by environmental effects (temperature, humidity) irrespective of radiation is also briefly considered.

  9. 9

    المصدر: Physics of Atomic Nuclei. 81:1580-1585

    الوصف: Stable configurations of point radiation defects of tungsten near the surface were investigated within the density functional theory. The emergence of an self-interstitial atom leads to formation of a crowdion. The transformation of this configuration into a configuration with an adsorbed W atom is a thermally activated process with the energy barrier of 1.38 eV. When a single vacancy emerges near the crowdion close to the surface, a recombination occurs. Impurity atoms in the vacancy near the surface are capable of blocking the recombination process, acting as a factor that increases the radiation damage of tungsten.

  10. 10

    المصدر: Physics of Atomic Nuclei. 81:1015-1023

    الوصف: The effect of deuterium plasma on tungsten with high levels of radiation damage was studied experimentally. Tungsten was examined as a candidate plasma-facing material for a fusion reactor. The effect of damage accumulation in a material irradiated with fusion neutrons was simulated using high-energy ions. Primary radiation defects of 1–100 dpa were produced in tungsten irradiated with He2+ and C3+ ions accelerated to 3–10 MeV in the cyclotron at the Kurchatov Institute with a fluence of 1017–1019 ion/cm2. The irradiated material was exposed to deuterium plasma at the LENTA linear plasma facility operated in the continuous regime and providing a plasma flux of 1021–1022 D/cm2. The erosion dynamics, the development of surface microstructure, and the accumulation of deuterium in tungsten were studied. Enhanced retention of deuterium was observed in the samples damaged both by helium and carbon ions at room temperature (ERDA). The effect of deuterium retention was suppressed in the damaged tungsten samples processed at a temperature of 500°C.