Studies of critical heat fluxes in small diameter channels

نویسندگان

چکیده

The paper presents the results of experimental studies critical heat flows in vertical small diameter channels, when coolant moves from bottom to top, which were carried out Obninsk branch MEPhI 1970s last century but have not become widespread due lack demand for their practical use. Nowadays, interest such works is manifested, first all, development compact plants and devices, particularly nuclear power engineering. As a coolant, water, Freon-12 96% ethyl alcohol used. High velocities underheated liquid at high fluxes on channel wall lead so-called “fast crisis” transfer. In this case, magnitude flux depends mainly parameters flow zone rather than core. “slow observed vapor concentrations, relatively low mass rates an annular-dispersed flow. value case core, are probably close average parameters. conditions near-wall region also largely determined by transfer coefficients moving speed usually result much smaller slower rise temperature. Sometimes DNB can occur bypassing boiling process. core VVER-type reactor operating its nominal mode, surface present number fuel rods. Probably, will be transportable small-size plants. Therefore, important task conduct relevant research area.

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ژورنال

عنوان ژورنال: Nuclear Energy and Technology

سال: 2021

ISSN: ['2452-3038']

DOI: https://doi.org/10.3897/nucet.7.78624