vestifmИзвестия Национальной академии наук Беларуси. Серия физико-математических наукProceedings of the National Academy of Sciences of Belarus. Physics and Mathematics Series1561-24302524-2415The Republican Unitary Enterprise Publishing House "Belaruskaya Navuka"10.29235/1561-2430-2026-62-2-125-135vestifm-902Research ArticleФИЗИКАPHYSICSГенерация малогрупповой библиотеки для активной зоны ВВЭР-1200 с использованием Монте-Карло кода SerpentThe few-group data library generation for a VVER-1200 core using the Monte Carlo code SerpentБабичевЛ. Ф.BabichevL. F.

Бабичев Леонид Филиппович – кандидат физи коматематических наук, заведующий лабораторией моделирования и суперкомпьютерных технологий в ядерной физике и энергетике

ул. Академика Красина, 99, 220109, Минск

Leonid F. Babichev – Ph. D. (Physics and Mathematics), Head of the Laboratory of Simulations and Supercomputing Technologies in Nuclear Physics and Power Engineering

 

babichev@sosny.bas-net.byРуденковИ. В.RudziankouI. V.

Руденков Ивантон Владимирович – научный сотрудник лаборатории моделирования и суперкомпьютерных технологий в ядерной физике и энергетике

ул. Академика Красина, 99, 220109, Минск

Ivanton V. Rudziankou – Researcher of the Laboratory of Simulations and Supercomputing Technologies in Nuclear Physics and Power Engineering

 

ivanton.rudziankou@gmail.comОбъединенный институт энергетических и ядерных исследований – Сосны Национальной академии наук БеларусиБеларусьJoint Institute for Power and Nuclear Research – Sosny of the National Academy of Sciences of BelarusBelarus202610072026622125135Copyright © Бабичев Л.Ф., Руденков И.В., 20262026Бабичев Л.Ф., Руденков И.В.Babichev L.F., Rudziankou I.V.Данная работа распространяется под лицензией Creative Commons Attribution 4.0.This work is licensed under a Creative Commons Attribution 4.0 License.https://vestifm.belnauka.by/jour/article/view/902

Представлены результаты комплексного исследования, направленного на разработку и валидацию методологии создания двухгрупповых библиотек сечений для реакторного кода DYN3D в формульном формате (IWQS = 2) с использованием прецизионного Монте-Карло кода Serpent. Исследование ориентировано на ядерный реактор ВВЭР-1200 Белорусской АЭС. Методика предполагает расчет двухгрупповых сечений и других констант для различных состояний реактора. Показано, что наибольшее отклонение для k∞ у всех типов тепловыделяющих сборок (ТВС) при расчете по коду DYN3D с полученной библиотекой отличается от прецизионного расчета по Монте-Карло коду Serpent на величину порядка 1000 ppm. Этот уровень точности является достаточным для проведения расчетов с данной библиотекой по анализу безопасности работы реактора ВВЭР-1200 в различных условиях эксплуатации. Проведен расчет концентраций борной кислоты в процессе кампании для первой и стационарной топливных загрузок реактора и распределения энерговыделения в начале кампании. Полученные результаты подчеркивают надежность и эффективность разработанной методики.

This article presents the results of a comprehensive investigation focused on developing and validating a methodology for creating two-group cross-section libraries for the DYN3D reactor code in the formula format (IWQS = 2), utilizing the high-precision Monte Carlo code Serpent. The study specifically targets the VVER-1200 nuclear reactor at the Belarusian Nuclear Power Plant. The methodology involves calculating two-group cross-sections and other constants for various reactor states. It is demonstrated that the largest deviation for k∞ for all types of fuel assemblies when calculated using the DYN3D code with the obtained library differs from precise Monte Carlo Serpent calculations by approximately 1000 ppm. This level of precision is deemed sufficient for safety analysis calculations using this library for the VVER-1200 reactor. Calculations of boric acid concentrations during the reactor’s first and stationary fuel cycles were performed, along with the distribution of energy release at the beginning of the campaign. The obtained results underscore the reliability and effectiveness of the developed methodology.

анализ безопасности реактораанализ аварийкритерии приемкикомпьютерное моделированиедиффузионное приближениедвухгрупповые сеченияМонте-Карло моделированиеreactor safety analysisaccident analysisacceptance criteriacomputer simulationdiffusion approximationtwo-group cross sectionsMonte Carlo simulationАвторы выражают благодарность Е. С. Горохову за техническую поддержку в расчетах и разработку компьютерных программ для этого исследования.Authors express their gratitude to Ya. S. Harokhau for the technical support in calculations and the development of computer programs for this research.ReferencesGrundmann U., Rohde U., Mittag S., Kliem S. DYN3D version 3.2 code for calculation of transients in light water reactors (LWR) with hexagonal or quadratic fuel elements. Dresden, Forschungszentrum Rossendorf Publ., 2005. 146 p. Available at: https://www.hzdr.de/publications/PublDoc-750.pdf (accessed 10 January 2023).Grundmann U., Rohde U., Mittag S., Kliem S. 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The authors declare that there are no conflicts of interest present.