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AbstractAbstract
[en] Coolant boiling experiments were conducted with DK1-1 diagnostic rod cluster wherein the flow rate was decreased step by step from the nominal level down to 25%. The primary circuit pressure was 9.8 MPa, inlet temperature - 246 degrees centigrade. The major objecive of the study was to detect by means of a noise diagnostic system the onset of subcooled boiling. For interpretation of the obtained data well defined steady-state thermal-hydraulic reactor characteristics are needed
Original Title
Teplogidravlicheskie izmereniya na diagnosticheskoj kassete AEhS Rheinsberg
Primary Subject
Secondary Subject
Source
Sovet Ehkonomicheskoj Vzaimopomoshchi, Moscow (USSR). Postoyannaya Komissiya po Ispol'zovaniyu Atomnoj Ehnergii v Mirnykh Tselyakh; 250 p; 1985; p. 213-225; Thermal physics 84. Thermal aspects of WWER nuclear reactor safety; Teplofizika 84. Teplotekhnicheskaya bezopasnost' yadernykh reaktorov VVEhR; Varna (Bulgaria); Oct 1984; 2 tabs.; 8 figs.
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
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