Experimental database on fast-reactor thermohydraulics for computational code verification

Autor:	A.V. Zhukov, A. D. Efanov, M. A. Fedosova, N. A. Denisova, G. A. Sorokin, A. P. Sorokin, Yu. A. Kuzina
Rok vydání:	2009
Předmět:	Thermal hydraulics Nuclear Energy and Engineering Nuclear reactor core law Nuclear engineering Benchmark (computing) Code (cryptography) Experimental data Power engineering Nuclear reactor law.invention Coolant
Zdroj:	Atomic Energy. 107:162-172
ISSN:	1573-8205 1063-4258
Popis:	The results of benchmark experiments on the thermohydraulics of a model fuel assembly and models of targets used in an accelerator-controlled system with a liquid-metal coolant are presented. Calculations performed using the domestic MIF code and foreign codes are compared. The data obtained from experimental studies of the hydrodynamics and heat-exchange in a fast-reactor core cooled by liquid sodium, which were performed primarily at the Physics and Power Engineering Institute over a long period of time, are briefly reviewed. It is shown that the experimental data for use as verification tests need to be systematized, evaluated, and generalized. The analysis shows the degree of completeness of the experimental data and permits making recommendations for performing experiments to fill the existing lacunas.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::275d639db8578ea6aaee9b97f4a09dcc https://doi.org/10.1007/s10512-010-9211-5 Zobrazit plný text záznamu Full text from SpringerLink