Nitride Fuel for a Prospective BN-1200 Type Fast Sodium Reactor

Autor:	V. A. Eliseev, L. M. Zaboudko, I. V. Malysheva, V.I. Matveev
Rok vydání:	2013
Předmět:	Materials science Sodium Inorganic chemistry technology industry and agriculture Oxide chemistry.chemical_element Nitride equipment and supplies complex mixtures chemistry.chemical_compound Nuclear Energy and Engineering Nuclear reactor core chemistry Reactivity (chemistry) Reactor safety Burnup
Zdroj:	Atomic Energy. 114:331-336
ISSN:	1573-8205 1063-4258
Popis:	The developers of fast sodium reactors are studying nitride fuel for use soon after oxide fuel. Together with a significant increase in the total BR, dense nitride fuel also permits improving a characteristic that is important for reactor safety – significantly decreasing the reactivity excess on burnup. The results of physical calculations of a BN-1200 reactor core, using fuel elements with gas or sodium sublayer on nitride fuel, are presented.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::495a3abd3874b93f82f137d76316a39c https://doi.org/10.1007/s10512-013-9720-0 Zobrazit plný text záznamu Full text from SpringerLink