On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors

Abstract

A few tests were performed to evaluate the feasibility of 2205 duplex stainless steel (DSS) as an accident tolerant fuel (ATF) cladding material, including corrosion tests in simulated pressure water reactor (PWR) primary water and high-temperature steam, stress corrosion cracking (SCC) initiation test, mechanical properties test and thermal aging effects. In both 360 °C PWR primary water and 1200 °C steam, DSS 2205 showed weight changes comparable to the high-Cr alloys. After 3163 h of exposure in 400 °C steam, U-bend specimens of DSS 2205 showed no obvious cracks, suggesting that SCC is not likely to be initiated during the service life. Compared to FeCrAl alloys, DSS 2205 showed comparable strength but greater ductility. Though 400 °C thermal aging caused an increase in strength for DSS 2205, total elongation was more than 35% even after 11,061 h aging, greater than other Fe-based ATF alloys. Also, concerns on neutron penalty, irradiation, fabrication and spent fuel storage were discussed. The overall results suggest that DSS 2205 could be considered as a candidate ATF cladding material.