Effects of Multiple Transients on Fast Reactor Fuel Pin Cladding Mechanical Properties

摘要

The effects of various TREAT and simulated transient events on subsequent burst strength of 20% cold worked AISI 316 irradiated fast reactor fuel pin cladding were evaluated. Cladding strength after transient exposure was compared to strength prior to transient exposure, using a HEDL correlation of failure temperatures with irradiation and test parameters. The simulated transients and post-transient strength tests were performed in the Fuel Cladding Transient Tester (FCTT), which was developed at HEDL to simulate cladding conditions during in-reactor transient events by pressurizing tubing specimens under transient heating conditions. (ERA citation 04:022854)