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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">10.52676/1729-7885-2025-1-46-52</article-id><article-id custom-type="elpub" pub-id-type="custom">nuc-759</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>ОПТИМИЗАЦИЯ ЗАДАНИЯ МНОГОМЕРНОГО РАСПРЕДЕЛЕНИЯ ЭНЕРГОВЫДЕЛЕНИЯ  В ОБЪЕКТЕ ИСПЫТАНИЯ ДЛЯ CFD МОДЕЛИРОВАНИЯ</article-title><trans-title-group xml:lang="en"><trans-title>OPTIMIZATION OF MULTIDIMENSIONAL ENERGY DISTRIBUTION  IN TEST DEVICE FOR CFD MODELING</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>Сураев</surname><given-names>А. С.</given-names></name><name name-style="western" xml:lang="en"><surname>Surayev</surname><given-names>A. S.</given-names></name></name-alternatives><bio xml:lang="ru"><p>Курчатов</p></bio><bio xml:lang="en"><p>Kurchatov</p></bio><email xlink:type="simple">suraev@nnc.kz</email><xref ref-type="aff" rid="aff-1"/></contrib><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Қабдылқақов</surname><given-names>Е. А.</given-names></name><name name-style="western" xml:lang="en"><surname>Kabdylkakov</surname><given-names>Ye. A.</given-names></name></name-alternatives><bio xml:lang="ru"><p>Курчатов</p></bio><bio xml:lang="en"><p>Kurchatov</p></bio><email xlink:type="simple">kabdylkakov@nnc.kz</email><xref ref-type="aff" rid="aff-1"/></contrib><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Жанболатов</surname><given-names>О. М.</given-names></name><name name-style="western" xml:lang="en"><surname>Zhanbolatov</surname><given-names>O. M.</given-names></name></name-alternatives><bio xml:lang="ru"><p>Курчатов</p></bio><bio xml:lang="en"><p>Kurchatov</p></bio><email xlink:type="simple">zhanbolatov@nnc.kz</email><xref ref-type="aff" rid="aff-1"/></contrib><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Витюк</surname><given-names>Г. А.</given-names></name><name name-style="western" xml:lang="en"><surname>Vityuk</surname><given-names>G. A.</given-names></name></name-alternatives><bio xml:lang="ru"><p>Курчатов</p></bio><bio xml:lang="en"><p>Kurchatov</p></bio><email xlink:type="simple">Shmeleova@nnc.kz</email><xref ref-type="aff" rid="aff-1"/></contrib><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Секен</surname><given-names>Д. М.</given-names></name><name name-style="western" xml:lang="en"><surname>Seken</surname><given-names>D. M.</given-names></name></name-alternatives><bio xml:lang="ru"><p>Курчатов</p><p>Семей</p></bio><bio xml:lang="en"><p>Kurchatov</p><p>Semey</p></bio><email xlink:type="simple">seken@nnc.kz</email><xref ref-type="aff" rid="aff-2"/></contrib></contrib-group><aff-alternatives id="aff-1"><aff xml:lang="ru">Филиал «Институт атомной энергии» РГП НЯЦ РК</aff><aff xml:lang="en">Branch “Institute of Atomic Energy” RSE NNC RK</aff></aff-alternatives><aff-alternatives id="aff-2"><aff xml:lang="ru">Филиал «Институт атомной энергии» РГП НЯЦ РК; Университет имени Шакарима города Семей<country>Казахстан</country></aff><aff xml:lang="en">Branch “Institute of Atomic Energy” RSE NNC RK; Shakharim University of Semey<country>Kazakhstan</country></aff></aff-alternatives><pub-date pub-type="collection"><year>2025</year></pub-date><pub-date pub-type="epub"><day>01</day><month>04</month><year>2025</year></pub-date><volume>0</volume><issue>1</issue><fpage>46</fpage><lpage>52</lpage><permissions><copyright-statement>Copyright &amp;#x00A9; Сураев А.С., Қабдылқақов Е.А., Жанболатов О.М., Витюк Г.А., Секен Д.М., 2025</copyright-statement><copyright-year>2025</copyright-year><copyright-holder xml:lang="ru">Сураев А.С., Қабдылқақов Е.А., Жанболатов О.М., Витюк Г.А., Секен Д.М.</copyright-holder><copyright-holder xml:lang="en">Surayev A.S., Kabdylkakov Y.A., Zhanbolatov O.M., Vityuk G.A., Seken D.M.</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/759">https://journals.nnc.kz/jour/article/view/759</self-uri><abstract><p>CFD моделирование – широко распространенный инструмент, применяемый для компьютерного анализа в различных сферах, в том числе и в реакторной теплофизике. Так, в стенах Национального ядерного центра Республики Казахстан, с целью выполнения расчетного анализа безопасности облучательных ампульных устройств перед их внутриреакторными испытаниями применяется программа ANSYS FLUENT. Помимо анализа безопасности проводимых реакторных испытаний, данная программа используется для подбора режимов испытаний, выбора и обоснования диаграммы изменения мощности реактора, оценки теплового состояния отдельных элементов конструкции и т.д. Особенность программного комплекса Ansys Fluent заключается в ограниченности функционала графического пользовательского интерфейса (GUI), который используется большинством пользователей программы на всех этапах выполнения расчетного анализа от подготовки расчетной модели и до обработки результатов. С другой стороны, текстовый пользовательский интерфейс (TUI) и пользовательские функции (UDF) применяются реже, при том, что их совместное использование предоставляет широкие возможности по оптимизации расчетного процесса, повышения качества результатов и экономии времени и вычислительных ресурсов. В этой связи актуальной стала задача разработки специализированного программного обеспечения (программы), которое способствует легкому внедрению UDF файлов в расчетный анализ.  В работе представлена компьютерная программа консольного типа, разработанная в среде Visual Basic для автоматического формирования UDF файлов на основе входных данных. Входными данными являются файлы с временным и высотным (радиальным) профилем энерговыделения. Преимущества программы: простота использования (не требует навыков программирования), скорость создания UDF файлов, точность написания функции (исключение ошибок, связанных с ручным вводом большого количества информации). </p></abstract><trans-abstract xml:lang="en"><p>CFD modelling is a widely used tool for computer analysis in various fields, including reactor thermophysics. Thus, in the walls of the National Nuclear Center of the Republic of Kazakhstan, for the purpose of carrying out safety analysis of irradiated devices before their in-pile tests, the program ANSYS FLUENT is used. In addition to the safety analysis of reactor tests being conducted, this program is used for the selection of test modes, selection and justification of the diagram of the change of the power of the reactor, evaluation of the thermal state of individual structural elements, etc. The special feature of the Ansys Fluent software complex is the limited functionality of the graphical user interface (GUI), which is used by most users of the program at all stages of calculation analysis from preparation of the calculation model to processing of results. On the other hand, the text-based user interface (TUI) and user-defined functions (UDF) are used less frequently, although their combined use provides extensive opportunities for optimizing the computational process, improving result quality, and saving time and computing resources. In this regard, the task of developing a specialized software (program) that facilitates easy implementation of UDF files into calculation analysis has become urgent. The article presents a console-type computer program developed in Visual Basic environment for automatic generation of UDF files based on input data. Input data are files contain time and height (radial) energy distribution profiles. Advantages of the program: easy to use (no programming skills required), speed of creation of UDF files, accuracy of writing function (elimination of errors related to manual input of a large amount of data). </p></trans-abstract><kwd-group xml:lang="ru"><kwd>Ansys Fluent</kwd><kwd>UDF</kwd><kwd>профиль энерговыделения</kwd><kwd>массив данных</kwd><kwd>программа</kwd><kwd>оптимизация расчетов</kwd></kwd-group><kwd-group xml:lang="en"><kwd>Ansys Fluent</kwd><kwd>UDF</kwd><kwd>energy profile</kwd><kwd>data array</kwd><kwd>program</kwd><kwd>calculation optimization</kwd></kwd-group><funding-group xml:lang="ru"><funding-statement>Работа выполнена при финансовой поддержке Комитета науки Министерства науки и высшего образования в рамках проекта грантового финансирования АР19577709 «Развитие методов CFD моделирования для описания процессов, сопровождающих развитие тяжелой аварии ядерного энергетического реактора».</funding-statement></funding-group></article-meta></front><back><ref-list><title>References</title><ref id="cit1"><label>1</label><citation-alternatives><mixed-citation xml:lang="ru">ANSYS, Inc. Products Release 2021 R1. Academic research Mechanical and CFD.</mixed-citation><mixed-citation xml:lang="en">ANSYS, Inc. Products Release 2021 R1. Academic research Mechanical and CFD.</mixed-citation></citation-alternatives></ref><ref id="cit2"><label>2</label><citation-alternatives><mixed-citation xml:lang="ru">Vityuk V., Vityuk G., Vurim A., Irkimbekov R., Kukushkin I., Surayev A., Mukhamedov N. Testing of a heterogeneous fuel rod in the research Impulse graphite reactor // Progress in Nuclear Energy. – 2023. – Vol. 164. – P. 104889. ISSN 0149-1970. https://doi.org/10.1016/j.pnucene.2023.104889</mixed-citation><mixed-citation xml:lang="en">Vityuk V., Vityuk G., Vurim A., Irkimbekov R., Kukushkin I., Surayev A., Mukhamedov N. Testing of a heterogeneous fuel rod in the research Impulse graphite reactor // Progress in Nuclear Energy. – 2023. – Vol. 164. – P. 104889. ISSN 0149-1970. https://doi.org/10.1016/j.pnucene.2023.104889</mixed-citation></citation-alternatives></ref><ref id="cit3"><label>3</label><citation-alternatives><mixed-citation xml:lang="ru">Surayev A. S. et al. Impact assessment of the IGR graphite block uneven impregnation with uranium on thermal strength properties // Вестник. Серия Физическая (ВКФ). – 2022. – Т. 82. – № 3. – С. 52–59. [Surayev A. S. et al. Impact assessment of the IGR graphite block uneven impregnation with uranium on thermal strength properties // Vestnik. Seriya Fizicheskaya (VKF). – 2022. – Vol. 82. – Issue 3. – P. 52–59.]</mixed-citation><mixed-citation xml:lang="en">Surayev A. S. et al. Impact assessment of the IGR graphite block uneven impregnation with uranium on thermal strength properties // Вестник. Серия Физическая (ВКФ). – 2022. – Т. 82. – № 3. – С. 52–59. [Surayev A. S. et al. Impact assessment of the IGR graphite block uneven impregnation with uranium on thermal strength properties // Vestnik. Seriya Fizicheskaya (VKF). – 2022. – Vol. 82. – Issue 3. – P. 52–59.]</mixed-citation></citation-alternatives></ref><ref id="cit4"><label>4</label><citation-alternatives><mixed-citation xml:lang="ru">Eickhoff M., Rückert A., Pfeifer H. Solidification modeling with User defined function in Ansys Fluent // Progress in Applied CFD – CFD2017 Selected papers from 12th International Conference on Computational Fluid Dynamics in the Oil &amp; Gas, Metallurgical and Process Industries. – SINTEF Academic Press, 2017.</mixed-citation><mixed-citation xml:lang="en">Eickhoff M., Rückert A., Pfeifer H. Solidification modeling with User defined function in Ansys Fluent // Progress in Applied CFD – CFD2017 Selected papers from 12th International Conference on Computational Fluid Dynamics in the Oil &amp; Gas, Metallurgical and Process Industries. – SINTEF Academic Press, 2017.</mixed-citation></citation-alternatives></ref><ref id="cit5"><label>5</label><citation-alternatives><mixed-citation xml:lang="ru">Manual U.D.F. ANSYS FLUENT 12.0 // Theory Guide. – 2021.</mixed-citation><mixed-citation xml:lang="en">Manual U.D.F. ANSYS FLUENT 12.0 // Theory Guide. – 2021.</mixed-citation></citation-alternatives></ref><ref id="cit6"><label>6</label><citation-alternatives><mixed-citation xml:lang="ru">Yerzhan Kabdylkakov, Artur Surayev, Ruslan Irkimbekov (2022) New approaches to CFD analysis of experimental devices in the Ansys Fluent // AIP conference proceedings, 3020, 040008 (2024). https://doi.org/10.1063/5.0194184</mixed-citation><mixed-citation xml:lang="en">Yerzhan Kabdylkakov, Artur Surayev, Ruslan Irkimbekov (2022) New approaches to CFD analysis of experimental devices in the Ansys Fluent // AIP conference proceedings, 3020, 040008 (2024). https://doi.org/10.1063/5.0194184</mixed-citation></citation-alternatives></ref><ref id="cit7"><label>7</label><citation-alternatives><mixed-citation xml:lang="ru">ANSYS FLUENT Text Command List Release 2021// Command List. – 2020</mixed-citation><mixed-citation xml:lang="en">ANSYS FLUENT Text Command List Release 2021// Command List. – 2020</mixed-citation></citation-alternatives></ref><ref id="cit8"><label>8</label><citation-alternatives><mixed-citation xml:lang="ru">Kabdylkakov Y.A., Suraev A.S. Application of the volume of fluid method to simulate the process of melting and movement of fuel // NNC RK Bulletin. – 2021. Issue 3(87). – P. 3–8. (In Russ.). https://doi.org/10.52676/1729-7885-2021-3-3-8</mixed-citation><mixed-citation xml:lang="en">Kabdylkakov Y.A., Suraev A.S. Application of the volume of fluid method to simulate the process of melting and movement of fuel // NNC RK Bulletin. – 2021. Issue 3(87). – P. 3–8. (In Russ.). https://doi.org/10.52676/1729-7885-2021-3-3-8</mixed-citation></citation-alternatives></ref><ref id="cit9"><label>9</label><citation-alternatives><mixed-citation xml:lang="ru">Kabdylkakov Y.A., Suraev A.S. Modeling of heat-strength interaction of fuel and structural materials of an irradiating device in the ANSYS software // NNC RK Bulletin. – 2023. – Issue 3(95). – P. 63–71. (In Russ.) https://doi.org/10.52676/1729-7885-2023-3-63-71</mixed-citation><mixed-citation xml:lang="en">Kabdylkakov Y.A., Suraev A.S. Modeling of heat-strength interaction of fuel and structural materials of an irradiating device in the ANSYS software // NNC RK Bulletin. – 2023. – Issue 3(95). – P. 63–71. (In Russ.) https://doi.org/10.52676/1729-7885-2023-3-63-71</mixed-citation></citation-alternatives></ref><ref id="cit10"><label>10</label><citation-alternatives><mixed-citation xml:lang="ru">Surayev A.S., Irkimbekov R.A., Stepanova O.A. Simulation of interaction between material and melt of nuclear fuel // Book of Abstracts of International online conference “Advanced manufacturing materials and research: New technologies and techniques AMM&amp;R2021”. – Ust-Kamenogorsk, D. Serikbayev EKTU, 2021. – P.42.</mixed-citation><mixed-citation xml:lang="en">Surayev A.S., Irkimbekov R.A., Stepanova O.A. Simulation of interaction between material and melt of nuclear fuel // Book of Abstracts of International online conference “Advanced manufacturing materials and research: New technologies and techniques AMM&amp;R2021”. – Ust-Kamenogorsk, D. Serikbayev EKTU, 2021. – P.42.</mixed-citation></citation-alternatives></ref><ref id="cit11"><label>11</label><citation-alternatives><mixed-citation xml:lang="ru">Жанболатов О.М., Сураев А.С. Программа управления для моделирования динамических параметров импульсного графитового реактора // Сборник трудов XX Международной конференции студентов, аспирантов и молодых ученых «Перспективы развития фундаментальных наук», 25–28 апреля 2023 г., Томск.</mixed-citation><mixed-citation xml:lang="en">Zhanbolatov О.М., Surayev А.S. Program for control of modeling the dynamic parameters of a pulse graphite reactor // Collection of works of XX International conference of students, graduate and young scientists «Perspectives of development of fundamental sciences», April, 25–28, 2023, Tomsk. (In Russ.)]</mixed-citation></citation-alternatives></ref><ref id="cit12"><label>12</label><citation-alternatives><mixed-citation xml:lang="ru">ANSYS Fluent Customization Manual. Ansys Inc. Products Release 2021 R1, January 2021.</mixed-citation><mixed-citation xml:lang="en">ANSYS Fluent Customization Manual. Ansys Inc. Products Release 2021 R1, January 2021.</mixed-citation></citation-alternatives></ref><ref id="cit13"><label>13</label><citation-alternatives><mixed-citation xml:lang="ru">Vick, Paul. The Visual Basic.Net Programming Language // Addison-Wesley Professional. – 2004.</mixed-citation><mixed-citation xml:lang="en">Vick, Paul. The Visual Basic.Net Programming Language // Addison-Wesley Professional. – 2004.</mixed-citation></citation-alternatives></ref><ref id="cit14"><label>14</label><citation-alternatives><mixed-citation xml:lang="ru"></mixed-citation><mixed-citation xml:lang="en"></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>
