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Effects of multiple transients on fast reactor fuel pin cladding mechanical properties

Conference ·
OSTI ID:6349132
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.
Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA)
DOE Contract Number:
EY-76-C-14-2170
OSTI ID:
6349132
Report Number(s):
HEDL-SA-1598-FP; CONF-781105-97
Country of Publication:
United States
Language:
English