Thermohydraulics of fuel-element bundles with low water flow rates and steam-water counterflow

Autor:	B. F. Balunov, S. V. Gur'yanov, A. S. Babykin, Yu. N. Ilyukhin, V. V. Bakhrushev, V. S. Kuul, A. A. Fal'kov
Rok vydání:	1993
Předmět:	Thermal hydraulics Natural circulation Nuclear Energy and Engineering Nuclear reactor core law Water flow Bundle Nuclear engineering Fluid dynamics Environmental science Nuclear reactor law.invention Coolant
Zdroj:	Atomic Energy. 75:775-780
ISSN:	1573-8205 1063-4258
Popis:	This paper examines the features of numerous types of natural circulation (core cooling) that occurs after large amounts of coolant has been lost from the primary loop. These types of flow included cascade flow, steam-condensate flow, interassembly natural circulation and descending circulation in the interassembly gap. The examination is based upon experiments done on natural circulation loop simulators of reactors and associated equipment. The experimental loops included electric mockups of fuel-element bundles for domestic water cooled reactors. The models considered were; (1) A VVER-1000 fuel element bundle, and (2) An AST-500 fuel element bundle. Under the conditions of the experiment, recommendations are made for calculating the steam content and the critical power for the fuel element bundle.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::842adc797f39862f8ca4808fc3c692e5 https://doi.org/10.1007/bf00739358 Zobrazit plný text záznamu Full text from SpringerLink