nucВестник НЯЦ РКNNC RK Bulletin1729-75161729-7885Национальный ядерный центр Республики Казахстан10.52676/1729-7885-2025-4-79-87nuc-901Research ArticleСтатьиОЦЕНКА ВЫДЕЛЕНИЯ ИОНОВ ТРИТИЯ, ОБРАЗУЮЩИХСЯ В ЯДЕРНОЙ РЕАКЦИИ 6Li(n, α)T ИЗ ПРИПОВЕРХНОСТНОГО СЛОЯ ЛИТИЕВОЙ КЕРАМИКИ В УСЛОВИЯХ РЕАКТОРНОГО ОБЛУЧЕНИЯEVALUATION OF THE RELEASE OF TRITIUM IONS FORMED IN THE NUCLEAR REACTION 6Li(n, α)T FROM THE SURFACE LAYER OF LITHIUM CERAMICS UNDER REACTOR IRRADIATION CONDITIONShttps://orcid.org/0000-0003-3890-8172КульсартовТ. В.KulsartovT. V.

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Almaty

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tima@physics.kzhttps://orcid.org/0000-0001-7587-3461СайранбаевД. С.SairanbaevD. S.

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d.sairanbayev@inp.kzhttps://orcid.org/0000-0002-9089-3409АйткуловМ. Т.AitkulovM. T.

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maitkulov@inp.kzhttps://orcid.org/0000-0001-7204-4887ӘскербековС. К.AskerbekovS. K.

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askerbekov@physics.kzhttps://orcid.org/0000-0001-5704-1514АхановА. М.AkhanovA. M.

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aakhanov@inp.kzhttps://orcid.org/0009-0005-0406-1374ЕлишенковА. Б.ElishenkovА. B.

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aleksandrelisenkov282@gmail.comhttps://orcid.org/0000-0001-6642-8980ЗаурбековаЖ. А.ZaurbekovaZh. A.

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zzha@physics.kzhttps://orcid.org/0000-0003-0304-2049ШаймерденовА. А.ShaimerdenovA. A.

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aashaimerdenov@gmail.comРГП «Институт ядерной физики» Агентства РК по атомной энергии; «Институт экспериментальной и теоретической физики» Казахского национального университета им. аль-Фараби; филиал «Институт атомной энергии» РГП НЯЦ РККазахстанRSE “Institute of Nuclear Physics” of the Agency of the Republic of Kazakhstan for Atomic Energy; Institute of Experimental and Theoretical Physics, Kazakh National University named after Al-Farabi; Branch “Institute of Atomic Energy” RSE NNC RKKazakhstanРГП «Институт ядерной физики» Агентства РК по атомной энергииКазахстанRSE “Institute of Nuclear Physics” of the Agency of the Republic of Kazakhstan for Atomic EnergyKazakhstanРГП «Институт ядерной физики» Агентства РК по атомной энергии; «Институт экспериментальной и теоретической физики» Казахского национального университета им. аль-ФарабиКазахстанRSE “Institute of Nuclear Physics” of the Agency of the Republic of Kazakhstan for Atomic Energy; Institute of Experimental and Theoretical Physics, Kazakh National University named after Al-FarabiKazakhstanРГП «Институт ядерной физики» Агентства РК по атомной энергии; «Институт экспериментальной и теоретической физики» Казахского национального университета им. аль-ФарабиКазахстанRSE “Institute of Nuclear Physics” of the Agency of the Republic of Kazakhstan for Atomic Energy; Institute of Experimental and Theoretical Physics, Kazakh National University named after Al-FarabiKazakhstan202508122025047987Copyright © Кульсартов Т.В., Сайранбаев Д.С., Айткулов М.Т., Әскербеков С.К., Аханов А.М., Елишенков А.Б., Заурбекова Ж.А., Шаймерденов А.А., 20252025Кульсартов Т.В., Сайранбаев Д.С., Айткулов М.Т., Әскербеков С.К., Аханов А.М., Елишенков А.Б., Заурбекова Ж.А., Шаймерденов А.А.Kulsartov T.V., Sairanbaev D.S., Aitkulov M.T., Askerbekov S.K., Akhanov A.M., Elishenkov А.B., Zaurbekova Z.A., Shaimerdenov A.A.Данная работа распространяется под лицензией Creative Commons Attribution 4.0.This work is licensed under a Creative Commons Attribution 4.0 License.https://journals.nnc.kz/jour/article/view/901

Представлены аналитические результаты по оценке стационарного потока ионов трития, выделяющихся из керамик на основе лития Li2TiO3 различного обогащения в условиях реакторного облучения на реакторе ВВР-К. Нейтронно-транспортные расчёты выполнены в MCNP6 с использованием библиотеки ENDF/B-VII.1 и сопоставлены с in-situ газовыделением, зарегистрированным при температуре керамик 650 ℃ и потоке тепловых нейтронов 5·1013 н/(см² с). Разработанная расчетная модель не содержит подгоночных коэффициентов и учитывает длину пробега ионов, эффект самоэкранирования в керамике (δ = 0,32) и потери на рекомбинацию. Полученные значения потока T⁺ из керамик различного изотопного состава составляют 3,07·10−13 до 1,96·10−12 моль/с. Максимальное снижение потока за счёт самоэкранирования в керамике не превышает 32%. Расхождение между расчётом и экспериментом по компоненте HT не превышает 15%, что подтверждает адекватность подхода. Результаты имеют практическую значимость при оценке баланса трития в бланкетах термоядерных реакторов (ТЯР) и позволяют оптимизировать состав и размер керамических пэбблов с учётом безактивационного газовыделения трития. 

The article presents analytical results on the estimation of the steady-state flux of tritium ions released from lithium-based ceramics Li2TiO3 under reactor irradiation conditions at the WWR-K reactor. Neutron transport calculations were performed in MCNP6 using the ENDF/B-VII.1 library and compared with in-situ gas release recorded at a ceramic temperature of 650 ℃ and a thermal neutron flux of 5·1013 n/(cm2·s). The developed calculation model does not contain fitting coefficients and takes into account the ion mean free path, the self-shielding effect in ceramics (δ = 0.32) and recombination losses. The obtained values of T⁺ flux from ceramics of different isotopic composition are 3.07·10−13 to 1.96·10−12 mol/s. The maximum decrease in the flux due to self-shielding in ceramics does not exceed 32%. The discrepancy between the calculation and the experiment for the HT component does not exceed 15%, which confirms the adequacy of the approach. The results are of practical importance in assessing the tritium balance in fusion reactor blankets and allow optimizing the composition and size of ceramic pebbles taking into account the activation-free gas evolution of tritium.

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The authors declare that there are no conflicts of interest present.