Sodium Cavitation Damage Tests in Vibratory Facility-Temperature and Pressure Effects.

摘要

Cavitation damage data is reported for tests in sodium and water in a vibratory facility (20kHz, 51micrometers double amplitude) over the temperature range 300-500C at suppression pressure (NPSH/density) of 3bar on stainless steel type 316 L. The results are compared with other pertinent related data. Maximum damage temperature is of the order of 300C and thus is in the range of reactor operation for LMFBR,whereas this is not the case for water-cooled power reactors as PWR and BWR,where the maximum cavitation damage temperature is far below operating temperature. At their respective maximum damage temperatures,cavitation damage potential for water and sodium are of the same order of magnitude. Attempts are made to generalize existing results for various cavitating liquids.