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Published in: Thermal Engineering 12/2023

01-12-2023 | NUCLEAR POWER PLANTS

Experimental Studies of the Float-Discrete Method for Measuring the Level of a Heavy Liquid-Metallic Coolant

Authors: T. A. Bokova, A. G. Meluzov, N. S. Volkov, A. R. Marov, T. K. Zyryanova, R. V. Sumin, M. D. Pogorelov

Published in: Thermal Engineering | Issue 12/2023

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Abstract

The results of experimental studies of the applicability of the float-discrete method for measuring the level of a heavy liquid-metal coolant (HLMC) using sealed magnetically controlled contacts as a sensitive element are presented. These contacts register the coolant level in the field of a permanent magnet located on the surface of a heavy liquid-metal coolant. The performance of such a level sensor was studied using a control tank with a lead-bismuth coolant under conditions close to natural ones. This method is simple, but its main problem is maintaining the integrity of sealed magnetically controlled contacts when exposed to high temperatures. The experiments were carried out using a float-discrete level sensor prototype on a high-temperature stand with a lead-bismuth coolant. The data collected during the processing of the results confirm with reliable accuracy the applicability of the float-discrete method for monitoring the level of a heavy liquid-metal coolant. An HLMC level measuring device operating according to this method makes it possible to monitor the level in tanks while maintaining the tightness of the circuit. Due to this, it is possible to abandon the currently common methods for determining the level of HLMC using electric contact level sensors in which the sealing of the circuit is impossible. This device can be used on various experimental stands with liquid-metal coolants as well as in reactor plants and accelerator-controlled systems in the temperature range of 210–230°C, for example MYRRHA. To ensure the operability of the level transmitter at higher temperatures, it is necessary to upgrade the reed switch cooling system.

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Footnotes
1
BREST is a natural safety fast reactor with a lead coolant, SVBR is a lead-bismuth fast reactor, BRS-GPG is a lead-cooled fast reactor with a horizontal steam generator.
 
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Metadata
Title
Experimental Studies of the Float-Discrete Method for Measuring the Level of a Heavy Liquid-Metallic Coolant
Authors
T. A. Bokova
A. G. Meluzov
N. S. Volkov
A. R. Marov
T. K. Zyryanova
R. V. Sumin
M. D. Pogorelov
Publication date
01-12-2023
Publisher
Pleiades Publishing
Published in
Thermal Engineering / Issue 12/2023
Print ISSN: 0040-6015
Electronic ISSN: 1555-6301
DOI
https://doi.org/10.1134/S0040601523120030

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