3 results about "Sodium-cooled fast reactor" patented technology

A sodium-air heat exchanger according to the present disclosure may comprise: a vertically erected tubular body through which air flows; a heat transfer tube bundle arranged longitudinally within the tubular body through which sodium flows; an upper duct installed at the top of the tubular body through which sodium is introduced and air is discharged; and a lower duct installed at the bottom of the tubular body through which sodium is discharged and air is introduced.

The embodiment of the invention relates to the field of nuclear reactor monitoring, in particular to a method and system for detecting leakage of a sodium-cooled fast reactor steam generator. The method for detecting leakage of the sodium-cooled fast reactor steam generator comprises the following steps: S1, collecting vibration data of a steam generator shell; s2, performing gain and filtering processing on the vibration data; s3, acquiring a power spectrum corresponding to the vibration data; and S4, determining that the steam generator leaks according to the power spectrum. Compared with the method for determining the leakage of the steam generator according to the measured hydrogen concentration, the method for detecting the leakage of the sodium-cooled fast reactor steam generator provided by the embodiment of the invention has the advantages that the vibration data of the shell of the steam generator are collected and processed to determine the leakage of the steam generator; therefore, the leakage of the steam generator can be quickly detected, so that online monitoring of the leakage of the steam generator can be realized, and the safety of the steam generator can be ensured.