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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">10.52676/1729-7885-2025-4-5-11</article-id><article-id custom-type="elpub" pub-id-type="custom">nuc-874</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>РАЗРАБОТКА И ВЕРИФИКАЦИЯ НЕЙТРОННО-ФИЗИЧЕСКОЙ МОДЕЛИ РЕАКТОРА APR-1400</article-title><trans-title-group xml:lang="en"><trans-title>DEVELOPMENT AND VERIFICATION OF THE NEUTRON-PHYSICS MODEL  OF THE APR-1400 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>Какимова</surname><given-names>Г. Г.</given-names></name><name name-style="western" xml:lang="en"><surname>Kakimova</surname><given-names>G. G.</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">kakimova@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>Иркимбеков</surname><given-names>Р. А.</given-names></name><name name-style="western" xml:lang="en"><surname>Irkimbekov</surname><given-names>R. 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">Irkimbekov@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>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-group><aff-alternatives id="aff-1"><aff xml:lang="ru">Филиал «Институт атомной энергии» РГП НЯЦ РК<country>Казахстан</country></aff><aff xml:lang="en">Branch “Institute of Atomic Energy” RSE NNC RK<country>Kazakhstan</country></aff></aff-alternatives><pub-date pub-type="collection"><year>2025</year></pub-date><pub-date pub-type="epub"><day>08</day><month>12</month><year>2025</year></pub-date><volume>0</volume><issue>4</issue><fpage>5</fpage><lpage>11</lpage><permissions><copyright-statement>Copyright &amp;#x00A9; Какимова Г.Г., Иркимбеков Р.А., Сураев А.С., 2025</copyright-statement><copyright-year>2025</copyright-year><copyright-holder xml:lang="ru">Какимова Г.Г., Иркимбеков Р.А., Сураев А.С.</copyright-holder><copyright-holder xml:lang="en">Kakimova G.G., Irkimbekov R.A., Surayev A.S.</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/874">https://journals.nnc.kz/jour/article/view/874</self-uri><abstract><p>В данной работе представлена разработка и верификация нейтронно-физической модели водо-водяного энергетического реактора APR-1400 с использованием кода MCNP6. Разработана модель активной зоны с детализированным описанием конструктивных элементов. Верификация модели свидетельствует о её достоверности и позволяет использовать её для надёжного прогнозирования нейтронно-физических характеристик реактора в процессе эксплуатации. Результаты могут быть использованы для оптимизации топливных циклов и оценки воздействия новых конструктивных решений. </p></abstract><trans-abstract xml:lang="en"><p>In this work, a neutron-physical model of the APR-1400 water-moderated power reactor was developed and verified using the MCNP6 code. An active zone with a detailed description of the design elements was developed. The verification of the model will provide a reliable basis for strategic planning of further support for the operation of the reactor. The results can be used to optimize fuel cycles and assess the impact of new design solutions. </p></trans-abstract><kwd-group xml:lang="ru"><kwd>нейтронно-физический расчет</kwd><kwd>активная зона</kwd><kwd>реактивность</kwd><kwd>APR</kwd><kwd>нейтронно-физическая модель</kwd></kwd-group><kwd-group xml:lang="en"><kwd>neutron-physical calculation</kwd><kwd>active zone</kwd><kwd>reactivity</kwd><kwd>APR</kwd><kwd>neutron physics model</kwd></kwd-group><funding-group xml:lang="ru"><funding-statement>Работа выполнена при финансовой поддержке Агентства Республики Казахстан по атомной энергии по научно-технической программе BR24792713 «Развитие атомной энергетики в Республике Казахстан».</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">KEPCO E&amp;C. APR1400 Design Overview. – Yongin: Korea Electric Power Corporation Engineering &amp; Construction Company, 2002. – 40 p.</mixed-citation><mixed-citation xml:lang="en">KEPCO E&amp;C. APR1400 Design Overview. – Yongin: Korea Electric Power Corporation Engineering &amp; Construction Company, 2002. – 40 p.</mixed-citation></citation-alternatives></ref><ref id="cit2"><label>2</label><citation-alternatives><mixed-citation xml:lang="ru">KAERI. Development of Advanced Power Reactor (APR1400) / Korea Atomic Energy Research Institute // Nuclear Engineering and Technology. – 2004. – Vol. 36, No. 1. – P. 1–14. – ISSN 1738-5733.</mixed-citation><mixed-citation xml:lang="en">KAERI. Development of Advanced Power Reactor (APR1400) / Korea Atomic Energy Research Institute // Nuclear Engineering and Technology. – 2004. – Vol. 36, No. 1. – P. 1–14. – ISSN 1738-5733.</mixed-citation></citation-alternatives></ref><ref id="cit3"><label>3</label><citation-alternatives><mixed-citation xml:lang="ru">World Nuclear Association. Nuclear Power in South Korea – 2024. https://world-nuclear.org/informationlibrary/country-profiles/countries-o-s/south-korea.aspx</mixed-citation><mixed-citation xml:lang="en">World Nuclear Association. Nuclear Power in South Korea – 2024. https://world-nuclear.org/informationlibrary/country-profiles/countries-o-s/south-korea.aspx</mixed-citation></citation-alternatives></ref><ref id="cit4"><label>4</label><citation-alternatives><mixed-citation xml:lang="ru">Alrwashdeh М., Alameri S. A. Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly // Nuclear Engineering and Design. – 2021. – Vol. 384. – P. 111486.</mixed-citation><mixed-citation xml:lang="en">Alrwashdeh М., Alameri S. A. Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly // Nuclear Engineering and Design. – 2021. – Vol. 384. – P. 111486.</mixed-citation></citation-alternatives></ref><ref id="cit5"><label>5</label><citation-alternatives><mixed-citation xml:lang="ru">Alrwashdeh M., Alameri S. A. A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors // Arabian Journal for Science and Engineering. – 2023.</mixed-citation><mixed-citation xml:lang="en">Alrwashdeh M., Alameri S. A. A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors // Arabian Journal for Science and Engineering. – 2023.</mixed-citation></citation-alternatives></ref><ref id="cit6"><label>6</label><citation-alternatives><mixed-citation xml:lang="ru">Kang D. G. et al. Assessment of APR-1400 Emergency Core Cooling System performance for design basis LOCA redefinition // Nuclear Engineering and Design. – 2013.</mixed-citation><mixed-citation xml:lang="en">Kang D. G. et al. Assessment of APR-1400 Emergency Core Cooling System performance for design basis LOCA redefinition // Nuclear Engineering and Design. – 2013.</mixed-citation></citation-alternatives></ref><ref id="cit7"><label>7</label><citation-alternatives><mixed-citation xml:lang="ru">Advanced Power Reactor 1400 MWe (APR1400) [Status report 83]. – KEPCO E&amp;C/KHNP, 2011. – 37 p.</mixed-citation><mixed-citation xml:lang="en">Advanced Power Reactor 1400 MWe (APR1400) [Status report 83]. – KEPCO E&amp;C/KHNP, 2011. – 37 p.</mixed-citation></citation-alternatives></ref><ref id="cit8"><label>8</label><citation-alternatives><mixed-citation xml:lang="ru">IAEA. Action Plan on Nuclear Safety – Vienna: International Atomic Energy Agency, 2011. – 19 p. https://www.iaea.org/sites/default/files/actionplanns.pdf</mixed-citation><mixed-citation xml:lang="en">IAEA. Action Plan on Nuclear Safety – Vienna: International Atomic Energy Agency, 2011. – 19 p. https://www.iaea.org/sites/default/files/actionplanns.pdf</mixed-citation></citation-alternatives></ref><ref id="cit9"><label>9</label><citation-alternatives><mixed-citation xml:lang="ru">OECD/NEA. The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt. – NEA No. 7161. – Paris: Nuclear Energy Agency, 2013. – 136 p. – ISBN 978-92-64-99155-7.</mixed-citation><mixed-citation xml:lang="en">OECD/NEA. The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt. – NEA No. 7161. – Paris: Nuclear Energy Agency, 2013. – 136 p. – ISBN 978-92-64-99155-7.</mixed-citation></citation-alternatives></ref><ref id="cit10"><label>10</label><citation-alternatives><mixed-citation xml:lang="ru">U.S. NRC. Enhancing Reactor Safety in the 21st Century: The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. – Washington, D.C.: U.S. Nuclear Regulatory Commission, July 2011. – 96 p. https://www.nrc.gov/docs/ML1118/ML111861807.pdf</mixed-citation><mixed-citation xml:lang="en">U.S. NRC. Enhancing Reactor Safety in the 21st Century: The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. – Washington, D.C.: U.S. Nuclear Regulatory Commission, July 2011. – 96 p. https://www.nrc.gov/docs/ML1118/ML111861807.pdf</mixed-citation></citation-alternatives></ref><ref id="cit11"><label>11</label><citation-alternatives><mixed-citation xml:lang="ru">Goorley, T., James, M., Booth, T., Brown, F., Bull, J., Cox, L.J., Durkee, J., Elson, J., Fensin, M., Forster, R.A. and Hendricks, J. (2012). Initial MCNP6 release overview. Nuclear Technology, 180(3), pp.298-315. https://doi.org/10.13182/NT11-135.</mixed-citation><mixed-citation xml:lang="en">Goorley, T., James, M., Booth, T., Brown, F., Bull, J., Cox, L.J., Durkee, J., Elson, J., Fensin, M., Forster, R.A. and Hendricks, J. (2012). Initial MCNP6 release overview. Nuclear Technology, 180(3), pp.298-315. https://doi.org/10.13182/NT11-135.</mixed-citation></citation-alternatives></ref><ref id="cit12"><label>12</label><citation-alternatives><mixed-citation xml:lang="ru">Alrwashdeh, M.; Alameri, S.A. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core. Energies. – 2022. – Vol. 15(21). – P. 8008. https://doi.org/10.3390/en15218008</mixed-citation><mixed-citation xml:lang="en">Alrwashdeh, M.; Alameri, S.A. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core. Energies. – 2022. – Vol. 15(21). – P. 8008. https://doi.org/10.3390/en15218008</mixed-citation></citation-alternatives></ref><ref id="cit13"><label>13</label><citation-alternatives><mixed-citation xml:lang="ru">Yuk, S. APR1400 Reactor Core Benchmark Problem Book; Technical Report RPL-INERICA-004; Korea Atomic Energy Research Institute: Daejeon, Korea, 2019.</mixed-citation><mixed-citation xml:lang="en">Yuk, S. APR1400 Reactor Core Benchmark Problem Book; Technical Report RPL-INERICA-004; Korea Atomic Energy Research Institute: Daejeon, Korea, 2019.</mixed-citation></citation-alternatives></ref><ref id="cit14"><label>14</label><citation-alternatives><mixed-citation xml:lang="ru">Reactivity – Definition &amp; Calculation // Nuclearpower.com. https://www.nuclear-power.com/nuclearpower/reactor-physics/nuclear-fission-chainreaction/reactivity/?utm_source</mixed-citation><mixed-citation xml:lang="en">Reactivity – Definition &amp; Calculation // Nuclearpower.com. https://www.nuclear-power.com/nuclearpower/reactor-physics/nuclear-fission-chainreaction/reactivity/?utm_source</mixed-citation></citation-alternatives></ref><ref id="cit15"><label>15</label><citation-alternatives><mixed-citation xml:lang="ru">Introduction to Water Cooled Reactor Theory with the Micro-Physics. – Vienna: IAEA, 2014. – (Training Course Series No. 70). https://wwwpub.iaea.org/MTCD/Publications/PDF/TCS-70web.pdf?utm_source</mixed-citation><mixed-citation xml:lang="en">Introduction to Water Cooled Reactor Theory with the Micro-Physics. – Vienna: IAEA, 2014. – (Training Course Series No. 70). https://wwwpub.iaea.org/MTCD/Publications/PDF/TCS-70web.pdf?utm_source</mixed-citation></citation-alternatives></ref><ref id="cit16"><label>16</label><citation-alternatives><mixed-citation xml:lang="ru">K.E. Barr, S. Choi, J. Kang, B. Kochunas. Verification of MPACT for the APR1400 Benchmark // Energies. – 2021. – Vol. 14. – P. 3831. https://doi.org/10.3390/en14133831</mixed-citation><mixed-citation xml:lang="en">K.E. Barr, S. Choi, J. Kang, B. Kochunas. Verification of MPACT for the APR1400 Benchmark // Energies. – 2021. – Vol. 14. – P. 3831. https://doi.org/10.3390/en14133831</mixed-citation></citation-alternatives></ref><ref id="cit17"><label>17</label><citation-alternatives><mixed-citation xml:lang="ru">Z. Alnoamani, S. A. Alameri, M. Elsawi. Neutronic and Fuel Performance Evaluation of Accident Fuel Concepts in APR1400 Reactor. – Conference: Proceedings of the American Nuclear Society Annual Meeting, June 17–21, 2018, Philadelphia, PA, USA. https://www.researchgate.net/profile/ZainabAlnoamani2/publication/329357617_Neutronic_and_Fuel_Performance_Evaluation_of_Accident_Tolerant_Fuel_Concepts_in_APR1400_Reactor/links/64acc65bb9ed6874a50b9b8c/Neutronic-andFuel-Performance-Evaluation-of-Acciden-Tolerant-Fuel-Concepts-in-APR1400-Reactor.pdf</mixed-citation><mixed-citation xml:lang="en">Z. Alnoamani, S. A. Alameri, M. Elsawi. Neutronic and Fuel Performance Evaluation of Accident Fuel Concepts in APR1400 Reactor. – Conference: Proceedings of the American Nuclear Society Annual Meeting, June 17–21, 2018, Philadelphia, PA, USA. https://www.researchgate.net/profile/ZainabAlnoamani2/publication/329357617_Neutronic_and_Fuel_Performance_Evaluation_of_Accident_Tolerant_Fuel_Concepts_in_APR1400_Reactor/links/64acc65bb9ed6874a50b9b8c/Neutronic-andFuel-Performance-Evaluation-of-Acciden-Tolerant-Fuel-Concepts-in-APR1400-Reactor.pdf</mixed-citation></citation-alternatives></ref><ref id="cit18"><label>18</label><citation-alternatives><mixed-citation xml:lang="ru">Joint International Topical Meeting on Mathematics &amp; Computation and Supercomputing in Nuclear Applications (M&amp;C + SNA 2007) Monterey, California, April 15-19, 2007, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2007) “Doppler coefficient of reactivity – benchmark calculations for different enrichments of UO2” L. Thilagam, C. Sunil Sunny and K.V. Subbaiah; K. Devan; Lee, Young-Seok; V. Jagannathan.</mixed-citation><mixed-citation xml:lang="en">Joint International Topical Meeting on Mathematics &amp; Computation and Supercomputing in Nuclear Applications (M&amp;C + SNA 2007) Monterey, California, April 15-19, 2007, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2007) “Doppler coefficient of reactivity – benchmark calculations for different enrichments of UO2” L. Thilagam, C. Sunil Sunny and K.V. Subbaiah; K. Devan; Lee, Young-Seok; V. Jagannathan.</mixed-citation></citation-alternatives></ref><ref id="cit19"><label>19</label><citation-alternatives><mixed-citation xml:lang="ru">Risk Engineering LTD., Belene ISAR – Training course provided for Vietnam Atomic Energy Institute VINATOM, Sofia, Bungari, 15 Jan – 9 March 2012.</mixed-citation><mixed-citation xml:lang="en">Risk Engineering LTD., Belene ISAR – Training course provided for Vietnam Atomic Energy Institute VINATOM, Sofia, Bungari, 15 Jan – 9 March 2012.</mixed-citation></citation-alternatives></ref><ref id="cit20"><label>20</label><citation-alternatives><mixed-citation xml:lang="ru">В.А. Горбунов, С.С. Теплякова, Н.Е. Лоншаков, С.Г. Андриянов, П.А. Минеев. Исследование влияния конструктивного параметра тепловыделяющего элемента на коэффициент неравномерности теплового выделения по высоте реактора ВВЭР-100. – 2023. https://static.nuclear-powerengineering.ru/articles/2023/02/03.pdf</mixed-citation><mixed-citation xml:lang="en">V.A. Gorbunov, S.S. Teplyakova, N.E. Lonshakov, S.G. Andriyanov, P.A. Mineev. Issledovanie vliyaniya konstruktivnogo parametra teplovydelyayushchego elementa na koeffitsient neravnomernosti teplovogo vydeleniya po vysote reaktora VVER-100. – 2023. (In Russ.)] https://static.nuclear-powerengineering.ru/articles/2023/02/03.pdf</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>
