Simulated Transient Behavior of Fuel Cladding of SFR

In Korea, advanced cladding such as FC92 is developed and its transient behaviors are required for the safety analysis of SFR. Design and safety analyses of sodium-cooled fast reactor (SFR) require understanding fuel pin responses to a wide range of off normal events. In a loss-of-flow (LOF) or transient over-power (TOP), the temperature of the cladding is rapidly increased above its steady-state service temperature. The concept and general approach of transient testing of fuel cladding specimens was to define the failure stress and strain for fuel cladding in the temperature up to 1400 .deg. C at transient heating rates of 0.56, 5.6 and 111 .deg. C/sec. Results obtained for FC92 and HT9 cladding in a variety of simulated transients using the facility in KAERI will be further presented. For the safety analyses in SFR in Korea, simulated transient tests with newly developed FC92 as well as HT9 cladding are being carried out. A development of a general description of the cumulative damage fraction (CDF) correlation of FC92 and HT9 cladding for the ramp test as well as ramp and hold test are carrying out.