Measurement of the parameters of the VVÉR reactor at the Kalinin nuclear power plant

Autor:	A. I. Musorin, L. N. Bogachek, I. V. Sokolova, V. V. Kuz'min, N. N. Davidenko, V. Ya. Grubman, S. G. Tsypin, V. F. Bai, V. V. Lysenko, V. G. Dumshev, O. M. Kovalevich
Rok vydání:	1994
Předmět:	Nuclear Energy and Engineering law Nuclear engineering System of measurement Nuclear power plant Environmental science Thermal power station Coolant flow Radiation VVER Reactor pressure vessel law.invention Volumetric flow rate
Zdroj:	Atomic Energy. 77:724-726
ISSN:	1573-8205 1063-4258
Popis:	Measurements of the primary coolant flow rate and reactor thermal power were compared in a VVER type reactor for two measurement systems. Monthly measurements taken for a year by the automated radiation system (AIRM) and the standard SVRK system were compared. The systems showed an error of 1 to 2% in measuring the coolant flow rate through the reactor. When the units operate on two or three loops in the backward coolant flow regime, the SVRK system overestimated the coolant flow by approximately 8000 cubic meters per hour. 3 refs., 2 tabs.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::ae89bc1f64bb6d2423b5a7c1b1efc38c https://doi.org/10.1007/bf02418631 Zobrazit plný text záznamu Full text from SpringerLink