Prospects for the development of a direct-flow vessel reactor with superheated steam

Autor:	P. N. Alekseev, G. A. Filippov, P. A. Fomichenko, A. V. Chibinyaev, E. I. Grishanin, L. N. Fal’kovskii, B. I. Fonarev, N. E. Kukharkin, V. F. Tsibul’skii
Rok vydání:	2006
Předmět:	Materials science Nuclear engineering Superheated steam Uranium dioxide Nuclear reactor law.invention Coolant chemistry.chemical_compound Nuclear Energy and Engineering Nuclear reactor core chemistry law Pressurizer Light-water reactor Reactor pressure vessel Nuclear chemistry
Zdroj:	Atomic Energy. 100:192-198
ISSN:	1573-8205 1063-4258
DOI:	10.1007/s10512-006-0072-x
Popis:	A system of new technical solutions, which will make it possible to develop a reactor system using a coolant with supercritical parameters and efficiency 44%, solving the main problems of the nonuniformity of coolant heating in the core, is examined. This sytem contains a core based on fuel micropellets, a multistep fuel assembly with transverse coolant flow, coolant mixing after each step, and continual reloading of fuel micropellets into each fuel assembly.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::bdbfdc324b8dade3d8cf4144d327778c https://doi.org/10.1007/s10512-006-0072-x Zobrazit plný text záznamu Full text from SpringerLink