30 research outputs found

    Evolution of microstructure in stainless martensitic steel for seamless tubing

    Full text link
    Scanning electron microscopy with orientation analysis by the electron backscatter diffraction (EBSD) method is used to study microstructures and textures formed in the 0.08C-13Cr-3Ni-Mo-V-Nb steel through seamless tube production route: after hot deformation by extrusion; after quenching from various temperatures and subsequent high tempering. It is shown that the martensitic microstructure formed both after hot deformation and after quenching is characterized by the presence of deformation crystallographic texture, which is predetermined by the texture of austenite. The effect of heat treatment on texture, packet refinement, lath width, precipitation of carbides and Charpy impact energy is analyzed. © 2017 Author(s).The work was done using the equipment of the laboratory of Structural Methods of Analysis and Properties of materials and nanomaterials of the Collective Use Center affiliated to Ural Federal University. The study was supported by the program of increasing the competitiveness of the leading Russian universities, RF Government resolution No. 211, contract No. 02.А03.21.0006. We are grateful to the TMK company for their support and assistance in organizing the study

    ОБРАЩЕНИЕ С ОСОБЫМИ РАДИОАКТИВНЫМИ ОТХОДАМИ: ПРОГРЕСС ПРАКТИЧЕСКОЙ ДЕЯТЕЛЬНОСТИ И АКТУАЛЬНЫЕ ЗАДАЧИ

    Get PDF
    The article covers methodological approaches for substantiating the assignment of radioactive wastes (RAO) to special radioactive wastes, as well as the results of its practical application within initial registration of RAO.Обсуждаются методологические подходы к обоснованию отнесения радиоактивных отходов к особым радиоактивным отходам и результаты их практического применения в ходе первичной регистрации РАО

    Using the questionnaire (ohip-49) for life quality estimation in patients with hard tissue and dentition lesions treated by ceramic restorations

    Get PDF
    Questionnaire OHIP used for estimation of life quality in 40 somatic intact patients (mean age 45.9) before and after treatment by zirconia dioxide supported ceramic restorations, feldspar ceramic and «Е-max» pressed ceramic restorations.У 40 соматически сохранных пациентов (средний возраст 45,9 лет) с помощью опросника 0HIP-49 проведено изучение показателей качества жизни до и после протезирования безметалловыми керамическими реставрациями на каркасе из диоксида циркония, либо цельнокерамическими из полевошпатной керамики или литьевой керамики по технологии «Е-тах»

    Дозы облучения персонала и населения при нормальной эксплуатации пунктов захоронения радиоактивных отходов

    Get PDF
    This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on data collected during operation of near-surface disposal facilities for short-lived intermediate-, lowand very low-level waste in France, as well as nearsurface disposal facilities for long-lived waste in Russia. Further analysis of occupational and public doses calculated at the design stage was completed covering a near-surface disposal facility in Belgium and deep disposal facilities in the United Kingdom and the Nizhne-Kansk rock massive (Russia). The results show that engineering and technical solutions enable almost complete elimination of internal occupational exposure, whereas external exposure doses would fall within the range of values typical for a basic nuclear facility. Conclusion: radioactive waste disposal facilities being developed, constructed and operated meet the safety requirements effective in the Russian Federation and consistent with relevant international recommendations. It has been found that individual occupational exposure doses commensurate with those received by personnel of similar facilities abroad. Furthermore, according to the forecasts, mean individual doses for personnel during radioactive waste disposal would be an order of magnitude lower than the dose limit of 20 mSv/year. As for the public exposure, during normal operation, potential impact is virtually impossible by delaminating boundaries of a nuclear facility sanitary protection zone inside which the disposal facility is located and can be solely attributed to the use of public roads during radioactive waste transportation to the disposal facility site. Цель работы – сравнительный анализ фактических и оцениваемых на этапе проектирования доз облучения персонала и населения при захоронении жидких радиоактивных отходов и твердых радиоактивных отходов различных классов. В рамках настоящей статьи рассматривается вариант облучения персонала и населения при нормальной эксплуатации пункта захоронения радиоактивных отходов в режиме размещения отходов. Результаты: выполнен анализ индивидуальных и коллективных доз облучения персонала при приповерхностном захоронении короткоживущих среднеактивных, низкоактивных и очень низкоактивных радиоактивных отходов во Франции, а также при приповерхностном захоронении долгоживущих радиоактивных отходов в России. Проведен анализ проектных оценок доз облучения персонала и населения для объекта приповерхностной изоляции радиоактивных отходов, планируемого к сооружению в Бельгии, а также проектируемых объектов глубинного захоронения в Великобритании и Нижнеканском массиве (Российская Федерация). Техническими и технологическими решениями удается практически полностью исключить внутреннее облучение персонала, а дозы внешнего облучения ограничить диапазоном, характерным и для базовых ядерных технологий. Заключение: планируемые к сооружению, сооружаемые и эксплуатируемые пункты захоронения удаляемых радиоактивных отходов соответствуют действующим в России требованиям безопасности, согласующимся с международными рекомендациями. Оценено, что индивидуальные дозы облучения персонала сопоставимы с данными контроля персонала аналогичных объектов в других странах. Средние индивидуальные дозы облучения персонала при захоронении радиоактивных отходов прогнозируются на порядок ниже установленного предела дозы – 20 мЗв/год. Воздействие на население при нормальной эксплуатации практически исключено установлением санитарно-защитной зоны объекта использования атомной энергии, на которой размещена установка по захоронению отходов, и возможно только при транспортировке радиоактивных отходов по дорогам общего пользования к месту расположения пункта захоронения радиоактивных отходов.

    Ramsay-Hunt syndrome: case report

    Get PDF
    The aim of the study- to share the experience of treating a patient with Ramsey-Hunt syndrome, to pay attention to the interdisciplinary manifestations of this syndrome.Цель исследования - поделиться опытом лечения больной с синдромом Рамсея-Ханта, обратить внимание на междисциплинарные проявления данного синдрома

    THE EFFECT OF LITHIUM CHLORIDE ADDITIVE ON THE PHYSICO-CHEMICAL PROPERTIES OF BOROPHOSPHATE GLASS

    Full text link
    Studies of the effect of lithium chloride additives on the physicochemical properties of borophosphate glass. Structural studies have been carried out, thermal effects of the material and electrical conductivity have been described

    PENTAFLUOROPHENYL-2H-IMIDAZOLE DERIVATIVES OF CARBAZOLE BASED MOLECULARLY IMPRINTED POLYMER FOR CHLORAMPHENICOL DETECTION: CREATION AND PROPERTIES

    Full text link
    In this work the creation and characterization of molecularly imprinted polymer based on pentafluorophenyl-2H-imidazole derivatives of carbazole for chloramphenicol detection have been investigated. The increased direct electrochemical response of chloramphenicol on modified electrodes was shown.Работа выполнена при финансовой поддержке гранта РНФ № 20-73-10077

    Orientational Effects and Random Mixing in 1‑Alkanol + Nitrile Mixtures

    Get PDF
    1-Alkanol + alkanenitrile or + benzonitrile systems have been investigated by means of the molar excess functionsenthalpies (Hm E ), isobaric heat capacities (Cp,m E ), volumes (Vm E ), and entropiesand using the Flory model and the concentration−concentration structure factor (SCC(0)) formalism. From the analysis of the experimental data available in the literature, it is concluded that interactions are mainly of dipolar type. In addition, large Hm E values contrast with rather low Vm E values, indicating the existence of strong structural effects. Hm E measurements have been used to evaluate the enthalpy of the hydroxyl−nitrile interactions (ΔHOH−CN). They are stronger in methanol systems and become weaker when the alcohol size increases. In solutions with a given short chain 1-alkanol (up to 1-butanol), the replacement of ethanenitrile by butanenitrile weakens the mentioned interactions. Application of the Flory model shows that orientational effects exist in methanol or 1- nonanol, or 1-decanol + ethanenitrile mixtures. In the former solution, this is due to the existence of interactions between unlike molecules. For mixtures including 1-nonanol or 1-decanol, the systems at 298.15 K are close to their UCST (upper critical solution temperature), and interactions between like molecules are dominant. Orientational effects also are encountered in methanol or ethanol + butanenitrile mixtures because self-association of the alcohol plays a more important role. Aromaticity effect seems to enhance orientational effects. For the remainder of the systems under consideration, the random mixing hypothesis is attained to a rather large extent. Results from the application of the SCC(0) formalism show that homocoordination is the dominant trend in the investigated solutions, and are consistent with those obtained from the Flory model

    MANAGEMENT OF SPECIAL RADIOACTIVE WASTES: PRACTICAL ADVANCES AND CURRENT CHALLENGES

    No full text
    The article covers methodological approaches for substantiating the assignment of radioactive wastes (RAO) to special radioactive wastes, as well as the results of its practical application within initial registration of RAO
    corecore