Publication:
Evaluation of tensile strength of nuclear fuel samples

Простая страница элемента
dc.contributor.authorGoltsev, V. Y.
dc.contributor.authorOsintsev, A. V.
dc.contributor.authorОсинцев, Андрей Вениаминович
dc.date.accessioned2024-11-21T10:18:22Z
dc.date.available2024-11-21T10:18:22Z
dc.date.issued2019
dc.description.abstract© 2019 IOP Publishing Ltd. All rights reserved.For estimation of the strength of the nuclear fuel material as well and for further refinement of nuclear fuel test technology we propose to use small discoid samples, similar in shape to the elements of nuclear fuel in the context of "Brazilian test". We present here the results of testing small discoid specimens with and without center hole, made of brittle materials, such as cast iron and graphite (both being considered as possible model materials for the nuclear fuel). We compared these materials to nuclear fuel itself (as represented by uranium dioxide). The type of deformation and fracture found in samples made from cast iron suggests that this material cannot be used as a model for the nuclear fuel. In addition, the effect of the specimen size on resistance to destruction was investigated. The results obtained in tests on samples of graphite ARV-1 were in good agreement with the results of tests on uranium dioxide. Using the data obtained in this study, a calculation formula for determining the strength of the nuclear fuel material based on the "Brazilian test" results is proposed.
dc.identifier.citationGoltsev, V. Y. Evaluation of tensile strength of nuclear fuel samples / Goltsev, V.Y., Osintsev, A.V. // IOP Conference Series: Materials Science and Engineering. - 2019. - 558. - № 1. - 10.1088/1757-899X/558/1/012013
dc.identifier.doi10.1088/1757-899X/558/1/012013
dc.identifier.urihttps://www.doi.org/10.1088/1757-899X/558/1/012013
dc.identifier.urihttps://www.scopus.com/record/display.uri?eid=2-s2.0-85068958352&origin=resultslist
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/18405
dc.relation.ispartofIOP Conference Series: Materials Science and Engineering
dc.titleEvaluation of tensile strength of nuclear fuel samples
dc.typeConference Paper
dspace.entity.typePublication
oaire.citation.issue1
oaire.citation.volume558
relation.isAuthorOfPublication1f6d90d6-cadd-4c1d-aa29-f4220a454da2
relation.isAuthorOfPublication.latestForDiscovery1f6d90d6-cadd-4c1d-aa29-f4220a454da2
relation.isOrgUnitOfPublicationd19559ab-04cd-486a-ae8e-f40ccd36a1a6
relation.isOrgUnitOfPublication.latestForDiscoveryd19559ab-04cd-486a-ae8e-f40ccd36a1a6
Файлы
Коллекции
Публикации