Stressed state of a uranium-graphite fuel element under the action of temperature difference

Autor:	V. A. Zaznoba, E. E. Konoplev, V. P. Isakov
Rok vydání:	2006
Předmět:	Materials science Nuclear fuel General Chemical Engineering chemistry.chemical_element General Chemistry Uranium Action (physics) Matrix (geology) chemistry Stressed state Graphite Pyrolytic carbon Physics::Chemical Physics Composite material Radial stress
Zdroj:	Theoretical Foundations of Chemical Engineering. 40:431-434
ISSN:	1608-3431 0040-5795
DOI:	10.1134/s0040579506040142
Popis:	The problem of the stress distribution in a cylindrical nuclear fuel element with a graphite matrix and spherical inclusions is solved by the finite-element method. Recommendations are made on how to reduce the stress level in production of fuel elements to avoid surface cracks.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::caa5a8204ea702c253765de54ca817b3 https://doi.org/10.1134/s0040579506040142 Zobrazit plný text záznamu Plný text ve formátu PDF