Study of Morphological, Structural, and Strength Properties of Model Prototypes of New Generation TRISO Fuels.

TRISO fuel mechanical testing nuclear fuel nuclear power structure

Journal

Materials (Basel, Switzerland)
ISSN: 1996-1944
Titre abrégé: Materials (Basel)
Pays: Switzerland
ID NLM: 101555929

Informations de publication

Date de publication:
06 Jul 2022
Historique:
received: 29 05 2022
revised: 02 07 2022
accepted: 04 07 2022
entrez: 27 7 2022
pubmed: 28 7 2022
medline: 28 7 2022
Statut: epublish

Résumé

The purpose of this work is to characterize the morphological, structural, and strength properties of model prototypes of new-generation TRi-structural ISOtropic particle fuel (TRISO) designed for Generation IV high-temperature gas reactors (HTGR-type). The choice of model structures consisting of inner pyrolytic carbon (I-PyC), silicon carbide (SiC), and outer pyrolytic carbon (O-PyC) as objects of research is motivated by their potential use in creating a new generation of fuel for high-temperature nuclear reactors. To fully assess their full functional value, it is necessary to understand the mechanisms of resistance to external influences, including mechanical, as in the process of operation there may be external factors associated with deformation and leading to the destruction of the surface of fuel structures, which will critically affect the service life. The objective of these studies is to obtain new data on the fuel properties, as well as their resistance to external influences arising from mechanical friction. Such studies are necessary for further tests of this fuel on corrosion and irradiation resistance, as closely as possible to real conditions in the reactor. The research revealed that the study samples have a high degree of resistance to external mechanical influences, due to the high strength of the upper layer consisting of pyrolytic carbon. The presented results of the radiation resistance of TRISO fuel testify to the high resistance of the near-surface layer to high-dose irradiation.

Identifiants

pubmed: 35888209
pii: ma15144741
doi: 10.3390/ma15144741
pmc: PMC9317622
pii:
doi:

Types de publication

Journal Article

Langues

eng

Subventions

Organisme : Ministry of Education and Science of the Republic of Kazakhstan
ID : АР08052726

Références

J Phys Chem A. 2018 Jan 11;122(1):28-32
pubmed: 29232114
J Environ Radioact. 2021 Aug;234:106630
pubmed: 33989844

Auteurs

Inesh Kenzhina (I)

Laboratory of Structural Materials for Nuclear Power Plants, Al-Farabi Kazakh National University, Almaty 050032, Kazakhstan.
Advanced Electronics Development Laboratory, Kazakh-British Technical University, 59 Tole bi St., Almaty 050000, Kazakhstan.
Laboratory of Solid State Physics, The Institute of Nuclear Physics, Almaty 050032, Kazakhstan.
Department of General Physics, Satbayev University, Almaty 050032, Kazakhstan.

Petr Blynskiy (P)

Laboratory of Structural Materials for Nuclear Power Plants, Al-Farabi Kazakh National University, Almaty 050032, Kazakhstan.

Artem Kozlovskiy (A)

Laboratory of Solid State Physics, The Institute of Nuclear Physics, Almaty 050032, Kazakhstan.
Department of General Physics, Satbayev University, Almaty 050032, Kazakhstan.

Meiram Begentayev (M)

Department of General Physics, Satbayev University, Almaty 050032, Kazakhstan.

Saulet Askerbekov (S)

Laboratory of Structural Materials for Nuclear Power Plants, Al-Farabi Kazakh National University, Almaty 050032, Kazakhstan.
Laboratory of Solid State Physics, The Institute of Nuclear Physics, Almaty 050032, Kazakhstan.

Zhanna Zaurbekova (Z)

Laboratory of Structural Materials for Nuclear Power Plants, Al-Farabi Kazakh National University, Almaty 050032, Kazakhstan.

Aktolkyn Tolenova (A)

Laboratory of Structural Materials for Nuclear Power Plants, Al-Farabi Kazakh National University, Almaty 050032, Kazakhstan.
Department of General Physics, Satbayev University, Almaty 050032, Kazakhstan.

Classifications MeSH