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<article article-type="research-article" dtd-version="1.3" xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xml:lang="ru"><front><journal-meta><journal-id journal-id-type="publisher-id">nuc</journal-id><journal-title-group><journal-title xml:lang="ru">Вестник НЯЦ РК</journal-title><trans-title-group xml:lang="en"><trans-title>NNC RK Bulletin</trans-title></trans-title-group></journal-title-group><issn pub-type="ppub">1729-7516</issn><issn pub-type="epub">1729-7885</issn><publisher><publisher-name>Национальный ядерный центр Республики Казахстан</publisher-name></publisher></journal-meta><article-meta><article-id pub-id-type="doi">10.52676/1729-7885-2019-1-129-132</article-id><article-id custom-type="elpub" pub-id-type="custom">nuc-54</article-id><article-categories><subj-group subj-group-type="heading"><subject>Research Article</subject></subj-group><subj-group subj-group-type="section-heading" xml:lang="ru"><subject>Статьи</subject></subj-group></article-categories><title-group><article-title>СВОЙСТВА РАСПЛАВА МАТЕРИАЛОВ АКТИВНОЙ ЗОНЫ ЯДЕРНОГО РЕАКТОРА, ПОЛУЧЕННОГО НА ИССЛЕДОВАТЕЛЬСКОМ РЕАКТОРЕ ИГР</article-title><trans-title-group xml:lang="en"><trans-title>NUCLEAR REACTOR CORIUM PROPERTIES OBTAINED AT IGR RESEARCH REACTOR</trans-title></trans-title-group></title-group><contrib-group><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Скаков</surname><given-names>М. К.</given-names></name><name name-style="western" xml:lang="en"><surname>Skakov</surname><given-names>M. K.</given-names></name></name-alternatives><bio xml:lang="ru"><p>Курчатов</p></bio><bio xml:lang="en"><p>Kurchatov</p></bio><xref ref-type="aff" rid="aff-1"/></contrib><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Мухамедов</surname><given-names>Н. Е.</given-names></name><name name-style="western" xml:lang="en"><surname>Mukhamedov</surname><given-names>N. Ye.</given-names></name></name-alternatives><bio xml:lang="ru"><p>Курчатов</p></bio><bio xml:lang="en"><p>Kurchatov</p></bio><xref ref-type="aff" rid="aff-1"/></contrib><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Пахниц</surname><given-names>А. В.</given-names></name><name name-style="western" xml:lang="en"><surname>Pakhnits</surname><given-names>A. V.</given-names></name></name-alternatives><bio xml:lang="ru"><p>Курчатов</p></bio><bio xml:lang="en"><p>Kurchatov</p></bio><xref ref-type="aff" rid="aff-1"/></contrib><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Дерявко</surname><given-names>И. И.</given-names></name><name name-style="western" xml:lang="en"><surname>Deryavko</surname><given-names>I. I.</given-names></name></name-alternatives><bio xml:lang="ru"><p>Курчатов</p></bio><bio xml:lang="en"><p>Kurchatov</p></bio><xref ref-type="aff" rid="aff-1"/></contrib></contrib-group><aff-alternatives id="aff-1"><aff xml:lang="ru">Филиал «Институт атомный энергии» РГП НЯЦ РК<country>Казахстан</country></aff><aff xml:lang="en">RSE NNC RK Branch “Institute of Atomic Energy”<country>Kazakhstan</country></aff></aff-alternatives><pub-date pub-type="collection"><year>2019</year></pub-date><pub-date pub-type="epub"><day>30</day><month>03</month><year>2019</year></pub-date><volume>0</volume><issue>1</issue><fpage>129</fpage><lpage>132</lpage><permissions><copyright-statement>Copyright &amp;#x00A9; Скаков М.К., Мухамедов Н.Е., Пахниц А.В., Дерявко И.И., 2019</copyright-statement><copyright-year>2019</copyright-year><copyright-holder xml:lang="ru">Скаков М.К., Мухамедов Н.Е., Пахниц А.В., Дерявко И.И.</copyright-holder><copyright-holder xml:lang="en">Skakov M.K., Mukhamedov N.Y., Pakhnits A.V., Deryavko I.I.</copyright-holder><license xml:lang="ru" license-type="creative-commons-attribution" xlink:href="https://creativecommons.org/licenses/by/4.0/" xlink:type="simple"><license-p>Данная работа распространяется под лицензией Creative Commons Attribution 4.0.</license-p></license><license xml:lang="en" license-type="creative-commons-attribution" xlink:href="https://creativecommons.org/licenses/by/4.0/" xlink:type="simple"><license-p>This work is licensed under a Creative Commons Attribution 4.0 License.</license-p></license></permissions><self-uri xlink:href="https://journals.nnc.kz/jour/article/view/54">https://journals.nnc.kz/jour/article/view/54</self-uri><abstract><p>В работе впервые определены теплофизические свойства (удельная теплоемкость, температуропроводность и теплопроводность) натурного кориума быстрого энергетического ядерного реактора в диапазоне температур от комнатной до ~400 °С. Полученные данные предназначены к использованию в расчетах температурных полей при моделировании процессов по удержанию расплава кориума в корпусе ядерного реактора на быстрых нейтронах.</p></abstract><trans-abstract xml:lang="en"><p>In the paper for the first time thermophysical properties (specific heat capacity, thermal diffusivity and thermal conductivity) of natural corium of a fast nuclear power reactor were determined in the temperature range from room one up to ~400 °С. The obtained data is oriented at use in temperature field calculations when modeling the processes of corium melt retention in fast nuclear reactor vessel.</p></trans-abstract></article-meta></front><back><ref-list><title>References</title><ref id="cit1"><label>1</label><citation-alternatives><mixed-citation xml:lang="ru">J.K. Fink. Thermophysical properties of uranium dioxide // Journal of Nuclear Materials. – 2000. vol. 279. – pp. 1–18.</mixed-citation><mixed-citation xml:lang="en">J.K. Fink. Thermophysical properties of uranium dioxide // Journal of Nuclear Materials. – 2000. vol. 279. – pp. 1–18.</mixed-citation></citation-alternatives></ref><ref id="cit2"><label>2</label><citation-alternatives><mixed-citation xml:lang="ru">M. Skakov, N. Mukhamedov, I. Deryavko, et al. Temperature dependence of thermophysical properties of light-water reactor prototype corium // Proceedings of Inter. conf. “Materials and Engineering and Industrial Applications (MEIA)” September 20– 21, 2015. – Hong Kong. – pp. 75–79.</mixed-citation><mixed-citation xml:lang="en">M. Skakov, N. Mukhamedov, I. Deryavko, et al. Temperature dependence of thermophysical properties of light-water reactor prototype corium // Proceedings of Inter. conf. “Materials and Engineering and Industrial Applications (MEIA)” September 20– 21, 2015. – Hong Kong. – pp. 75–79.</mixed-citation></citation-alternatives></ref><ref id="cit3"><label>3</label><citation-alternatives><mixed-citation xml:lang="ru">D.E. Burkes, C.A. Papesch, A.P. Maddison, T. Hartmann, F.J. Rice. Thermophysical properties of DU-10wt.% Mo alloys // Journal of Nuclear Materials. – 2010. – vol. 403. – pp. 160–166.</mixed-citation><mixed-citation xml:lang="en">D.E. Burkes, C.A. Papesch, A.P. Maddison, T. Hartmann, F.J. Rice. Thermophysical properties of DU-10wt.% Mo alloys // Journal of Nuclear Materials. – 2010. – vol. 403. – pp. 160–166.</mixed-citation></citation-alternatives></ref><ref id="cit4"><label>4</label><citation-alternatives><mixed-citation xml:lang="ru">M. Skakov, N. Mukhamedov, W. Wieleba, I. Deryavko, Study of corium thermophysical properties of light water reactor with different oxidation degrees of zirconium // Research Journal of Pharmaceutical, Biological and Chemical Sciences. – 2016. – vol. 7(4). – pp. 2018–2024.</mixed-citation><mixed-citation xml:lang="en">M. Skakov, N. Mukhamedov, W. Wieleba, I. Deryavko, Study of corium thermophysical properties of light water reactor with different oxidation degrees of zirconium // Research Journal of Pharmaceutical, Biological and Chemical Sciences. – 2016. – vol. 7(4). – pp. 2018–2024.</mixed-citation></citation-alternatives></ref><ref id="cit5"><label>5</label><citation-alternatives><mixed-citation xml:lang="ru">V. Zhdanov, V. Baklanov et al. The Methodology of Determining Heat-Transfer Properties of the Samples of Promising Fuel for Water-Moderated Water-Cooled Power Reactor // Proceedings of Intern. conf. “Nuclear Power of the Republic of Kazakhstan” June 11–13, 2008, Kurchatov, IAE NNC RK. – 2009. – pp. 150–156.</mixed-citation><mixed-citation xml:lang="en">V. Zhdanov, V. Baklanov et al. The Methodology of Determining Heat-Transfer Properties of the Samples of Promising Fuel for Water-Moderated Water-Cooled Power Reactor // Proceedings of Intern. conf. “Nuclear Power of the Republic of Kazakhstan” June 11–13, 2008, Kurchatov, IAE NNC RK. – 2009. – pp. 150–156.</mixed-citation></citation-alternatives></ref></ref-list><fn-group><fn fn-type="conflict"><p>The authors declare that there are no conflicts of interest present.</p></fn></fn-group></back></article>
