METHOD FOR CHECKING SHIPBOARD NUCLEAR POWER PLANT FOR TIGHTNESS

摘要

FIELD: nuclear power engineering; checking steam generators of shipboard pressurized-water reactor for tightness during hydraulic tests. ^ SUBSTANCE: proposed method for checking steam generator of shipboard power plant for tightness includes measurement of reference radionuclide content in primary and secondary coolant samples with reactor shut down followed by calculation of amount of leakage. Primary and secondary coolant samples are taken from each steam generator upon completion of hydraulic tests. Prior to do so, primary-circuit water is stirred. This method provides for unbiased check of steam generator for tightness at low estimation threshold and identifying leaks of any amount. ^ EFFECT: ability of monitoring each steam generator for condition. ^ 3 cl, 1 tbl