Authors & Affiliations
Kruglov A.B., Kharitonov V.S., Paredes L.P.
National Research Nuclear University (MEPhI), Moscow, Russia
Kruglov A.B. – Associate Professor, Cand. Sci. (Phys.-Math.). Contacts: 31, Kashirskoye sh., Moscow, Russia, 115409. Tel.: +7 (495) 788-56-99, +7 (909) 983-75-44; email:
Kharitonov V.S. – Associate Professor, Cand. Sci. (Tech.).
Paredes L.P. – Postgraduate Student.
Abstract
The article presents results of a study using the pulsed laser heating method of thermal resistances of liquid lead contacts in gaps simulating a heat-conducting liquid metal sublayer in fuel elements of new-generation fast reactors. The paper describes the designs of measuring cells, the methodology for obtaining and processing experimental data, provides information on the thermophysical properties of parts of the measuring cells, presents the results of estimating the measurement error, and studies the dependence of thermal resistances of liquid lead contacts in model gaps on the temperature and number of meltings and crystallizations of lead. When studying the wetting of steel and ceramic surfaces with lead and lead-sodium alloy, based on the results of measuring the contact angles using the sessile drop method, the measurements were performed during heating and subsequent cooling of the contacting pair. The results of the experiments showed that in the temperature range of 400–650 °C typical for the operation of the liquid metal heat-conducting sublayer, the thermal resistance of the contacts of the lead melt with the heat-transfer surfaces reaches 1·10-5 (m2·K)/W. Such thermal resistances must be taken into account when analyzing heat transfer in fuel elements with a liquid metal sublayer. The results of the wetting study showed the potential of using a lead-sodium alloy as a heat-conducting sublayer metal.
Keywords
fuel elements, heat-conducting sublayer, thermal resistance of the sublayer, pulse heating method, wetting in the sublayer, contact angle, sessile drop method
Article Text (PDF, in Russian)
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UDC 621.311.25(6)
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 3, 3:14