R. P. Karagergi, A. V. Konovalov , A. V. Kozlov
A COMBINED METHOD FOR THE MECHANICAL TESTING OF RING SPECIMENS FROM THE FUEL ELEMENT CLADDING OF A FAST NEUTRON REACTOR
DOI: 10.17804/2410-9908.2026.3.116-139 To assess the condition the fuel element cladding of a nuclear reactor after operation, mechanical tensile testing of ring specimens is performed as part of post-irradiation studies. The specimen shapes and loading methods used in domestic studies differ significantly from those used in studies abroad. When irradiated specimens with low material ductility are tested, premature specimen failure results in a loss of information about the cladding properties, this being a common problem for testing ring specimens. The fuel rod cladding of the BN-600 reactor is used as an example to present a combined method including preliminary ring ovalization and subsequent stretching on semi-cylindrical supports. It is shown that the ovalization procedure allows one to prepare the gauge parts of the ring specimen prior to subsequent tensile testing. Furthermore, the stress-strain state of the specimen in its gauge part promotes a symmetric distribution of plastic strain across the specimen wall thickness. This leads to a more correct evaluation of the ductility and strength characteristics of fuel element cladding materials.
Acknowledgement: The research was performed under Rosatom’s program on increasing maximum fuel burnup in the fuel assemblies of fast neutron reactors, the state assignment from the Russian Ministry of Science and Higher Education for the IES UB RAS (R&D No. 124020600042-9), and the state assignment from the Russian Ministry of Science and Higher Education for the IMP UB RAS. Keywords: fuel element cladding, ring specimen, plastic deformation, mechanical properties, stress-strain state, combined method References:
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Р. П. Карагерги, А. В. Коновалов , А. В. Козлов
КОМБИНИРОВАННЫЙ СПОСОБ МЕХАНИЧЕСКИХ ИСПЫТАНИЙ КОЛЬЦЕВЫХ ОБРАЗЦОВ ИЗ ОБОЛОЧКИ ТВЭЛА РЕАКТОРА НА БЫСТРЫХ НЕЙТРОНАХ
Для оценки состояния оболочек твэлов ядерных реакторов после эксплуатации в рамках послереакторных исследований проводят механические испытания кольцевых образцов на растяжение. В зарубежной и отечественной практике подобных исследований формы образцов и способы их нагружения значительно отличаются. При испытании облученных образцов с низкой пластичностью материала из-за разрушения образца на начальной стадии опыта происходит потеря информации о свойствах оболочки, что является общей проблемой при испытании кольцевых образцов. На примере оболочки твэла реактора БН-600 представлен комбинированный способ, включающий в себя процедуру предварительной овализации кольца и его последующее растяжение на полуцилиндрических опорах. Показано, что процедура овализации позволяет подготовить рабочие части кольцевого образца перед его последующим испытанием на растяжение. При этом напряженно-деформированное состояние образца на рабочей части способствует симметричному распределению пластической деформации по толщине стенки образца. Это приводит к более корректной оценке характеристик пластичности и прочности материалов оболочек твэлов.
Ключевые слова: оболочка твэла, кольцевой образец, пластическая деформация, механические свойства, напряженно-деформированное состояние, комбинированный способ Библиография:
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Библиографическая ссылка на статью
Karagergi R. P., Konovalov A. V., Kozlov A. V. A Combined Method for the Mechanical Testing of Ring Specimens from the Fuel Element Cladding of a Fast Neutron Reactor // Diagnostics, Resource and Mechanics of materials and structures. -
2026. - Iss. 3. - P. 116-139. - DOI: 10.17804/2410-9908.2026.3.116-139. -
URL: http://dream-journal.org/issues/2026-3/2026-3_574.html (accessed: 26.09.2026).
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