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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">glonucsec</journal-id><journal-title-group><journal-title xml:lang="ru">Глобальная ядерная безопасность</journal-title><trans-title-group xml:lang="en"><trans-title>Global Nuclear Safety</trans-title></trans-title-group></journal-title-group><issn pub-type="ppub">2305-414X</issn><issn pub-type="epub">2499-9733</issn><publisher><publisher-name>National Research Nuclear University "MEPhI"</publisher-name></publisher></journal-meta><article-meta><article-id pub-id-type="doi">10.26583/gns-2025-02-06</article-id><article-id custom-type="edn" pub-id-type="custom">IQZVFW</article-id><article-id custom-type="elpub" pub-id-type="custom">glonucsec-324</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>ЭКСПЛУАТАЦИЯ ОБЪЕКТОВ АТОМНОЙ ОТРАСЛИ</subject></subj-group><subj-group subj-group-type="section-heading" xml:lang="en"><subject>OPERATION OF FACILITIES NUCLEAR INDUSTRY</subject></subj-group></article-categories><title-group><article-title>Об учете влияния гетерогенного эффекта в парообразовании на нейтронно-физические характеристики ТВС реактора BWR</article-title><trans-title-group xml:lang="en"><trans-title>The influence of the heterogeneous effect in vaporization on the neutron-physical characteristics of BWR fuel assembly</trans-title></trans-title-group></title-group><contrib-group><contrib contrib-type="author" corresp="yes"><contrib-id contrib-id-type="orcid">https://orcid.org/0000-0002-2048-0828</contrib-id><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Внуков</surname><given-names>Р. А.</given-names></name><name name-style="western" xml:lang="en"><surname>Vnukov</surname><given-names>R. A.</given-names></name></name-alternatives><bio xml:lang="ru"><p>аспирант, старший преподаватель</p></bio><bio xml:lang="en"><p>Postgraduate, Senior lecturer</p></bio><email xlink:type="simple">levz555@mail.ru</email><xref ref-type="aff" rid="aff-1"/></contrib><contrib contrib-type="author" corresp="yes"><contrib-id contrib-id-type="orcid">https://orcid.org/0000-0001-8905-1995</contrib-id><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Колесов</surname><given-names>В. В.</given-names></name><name name-style="western" xml:lang="en"><surname>Kolesov</surname><given-names>V. V.</given-names></name></name-alternatives><bio xml:lang="ru"><p>кандидат физико-математических наук, доцент</p></bio><bio xml:lang="en"><p>Cand. Sci (Phys. Math.), Associate Professor</p></bio><email xlink:type="simple">valeri-kolesov@yandex.ru</email><xref ref-type="aff" rid="aff-1"/></contrib></contrib-group><aff-alternatives id="aff-1"><aff xml:lang="ru"><institution>Обнинский институт атомной энергетики – филиал Национального исследовательского ядерного университета «МИФИ»</institution></aff><aff xml:lang="en"><institution>Obninsk Institute for Nuclear Power Engineering</institution></aff></aff-alternatives><pub-date pub-type="collection"><year>2025</year></pub-date><pub-date pub-type="epub"><day>26</day><month>06</month><year>2025</year></pub-date><volume>15</volume><issue>2</issue><fpage>56</fpage><lpage>63</lpage><permissions><copyright-statement>Copyright &amp;#x00A9; Внуков Р.А., Колесов В.В., 2025</copyright-statement><copyright-year>2025</copyright-year><copyright-holder xml:lang="ru">Внуков Р.А., Колесов В.В.</copyright-holder><copyright-holder xml:lang="en">Vnukov R.A., Kolesov V.V.</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://glonucsec.elpub.ru/jour/article/view/324">https://glonucsec.elpub.ru/jour/article/view/324</self-uri><abstract><p>Традиционно при проведении нейтронно-физических расчетов в случае, когда замедлитель представляет собой систему пар + вода, эффект парообразования, например, в кипящих реакторах типа BWR учитывается гомогенно уменьшением плотности воды в соответствии с долей пара. В работе сделана попытка исследовать влияние гетерогенной структуры вода + пузырьки пара на нейтронно-физические характеристики ТВС реактора BWR. Для создания модели использовались данные бенчмарка OECD/NEA Burnup Credit Criticality Benchmark Phase IIIB. Исследования проводились с использованием программного комплекса SERPENT-2, позволяющего случайным образом разбрасывать сферы различного радиуса, заполненные различным материалом в различных областях активной зоны реактора. Расчеты проводились с использованием библиотеки JEFF-3.1.1. Исследовалась зависимость наблюдаемого эффекта от радиусов пузырьков пара и от доли пара в теплоносителе. Обнаружено, что различия для гомогенной и гетерогенной моделей ТВС могут составлять до 0.3% в величине Кinf, что значительно больше точности, с которой проводились расчеты (~0.01%). Показано, что α уменьшается с ростом размера пузырьков пара при сравнении с гомогенной моделью. Таким образом, обосновывается изменение спектра нейтронов, которое влияет на изменение коэффициента размножения. При расчетном исследовании пустотного эффекта выявлено, что расхождения достигают 8% при рассмотрении моделей с различным паросодержанием и идентичных размерах пузырьков пара. Данная величина важна для корректной интерпретации мощностного эффекта реактивности в задачах оптимизации топливоиспользования. В частности, актуально для обоснования внедрения новых видов топлива.</p></abstract><trans-abstract xml:lang="en"><p>Traditionally, when conducting neutron physics calculations in cases where the moderator is a steam + water system, the effect of vaporization, for example, in boiling reactors of the BWR type, is taken into account homogeneously by reducing the density of water in accordance with the proportion of steam. The paper attempts to investigate the effect of the heterogenic structure of water + vapor bubbles on the neutron-physical characteristics of the fuel assemblies of the BWR reactor. To create the model, data from the OECD/NEA Burnup Credit Criticality Benchmark Phase IIIB are used. The research is carried out using the SERPENT-2 software package which allows randomly scattering spheres of various radii filled with various materials in different areas of the reactor core. The calculations are performed using the JEFF-3.1.1 library. The dependence of the observed effect on the radii of steam bubbles and on the proportion of steam in the coolant is investigated. It is found that the differences for homogeneous and heterogeneous fuel assembly models can be up to 0.3% in the value of Kinf, which is significantly higher than the accuracy with which calculations are performed (~0.01%). It is shown that α decreases with increasing vapor bubble size when compared with the homogeneous model. Thus, a change in the neutron spectrum is justified, which affects the change in the multiplication coefficient. A calculating study of the void effect revealed that discrepancies reach 8% when considering models with different vapor contents and identical vapor bubble sizes. This value is important for the correct interpretation of the reactivity power effect in fuel optimization problems. In particular, it is relevant to justify the introduction of new fuels.</p></trans-abstract><kwd-group xml:lang="ru"><kwd>кипящий реактор</kwd><kwd>двухфазная среда</kwd><kwd>теплоноситель</kwd><kwd>пузырьки пара</kwd><kwd>BWR</kwd><kwd>гетерогенная модель</kwd><kwd>гомогенная модель</kwd></kwd-group><kwd-group xml:lang="en"><kwd>boiling reactor</kwd><kwd>two-phase flow</kwd><kwd>coolant</kwd><kwd>vapor bubbles</kwd><kwd>BWR</kwd><kwd>heterogeneous model</kwd><kwd>homogeneous model</kwd></kwd-group></article-meta></front><back><ref-list><title>References</title><ref id="cit1"><label>1</label><citation-alternatives><mixed-citation xml:lang="ru">Santamarina A. Advanced neutronics tools for BWR design calculations. Nuclear Engineering and Design. 2008. https://doi.org/10.1016/J.NUCENGDES.2007.12.012</mixed-citation><mixed-citation xml:lang="en">Santamarina A. Advanced neutronics tools for BWR design calculations. 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