Irradiation performance of Fast Flux Test Facility drivers using D9 alloy

Conference · Wed Jun 01 04:00:00 EDT 1994

OSTI ID:10169416

Pitner, A L; Gneiting, B C; Bard, F E

Six test assemblies similar in design to the FFTF driver assembly but employing the advanced alloy D9 in place of Type 316 stainless steel for duct, cladding, and wire wrap material were irradiated to demonstrate the improved performance and lifetime capability of this design. A single pinhole-type breach was incurred in one of the high exposure tests after a peak fuel burnup of 155 MWd/kgM and peak fast neutron fluence of 25 {times} 10{sup 22} n/cm{sup 2} (E > 0.1 MeV). Postirradiation examinations were performed on four of the test assemblies and measured results were compared to analytical evaluations. A revised swelling correlation for D9 Alloy was developed to provide improved agreement between calculated and measured cladding deformation results. A fuel pin lifetime design criterion of 5% calculated hoop strain was derived. Alternatively, fuel pin lifetimes were developed for two irradiation parameters using statistical failure analyses. For a 99.99% reliability, the analyses indicated a peak fast fluence lifetime of 21.0 {times} 10{sup 22} n/cm{sup 2}, or a peak fuel burnup greater than 120 MWd/kgM. The extended lifetime capability of this design would reduce fuel supply requirements for the FFTF by a third relative to the reference driver design.

• Research Organization: Westinghouse Hanford Co., Richland, WA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 10169416
• Report Number(s): WHC-SA--2261; CONF-940602--15; ON: DE94015711; BR: 35AF11201/35AF11202
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
36 MATERIALS SCIENCE
360106
ALLOY-D-9
DEFORMATION
FFTF REACTOR
FUEL ASSEMBLIES
FUEL CANS
MATERIAL SUBSTITUTION
MATERIALS TESTING
PHYSICAL RADIATION EFFECTS
POST-IRRADIATION EXAMINATION
POWER REACTORS
BREEDING
RADIATION EFFECTS
RELIABILITY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
SERVICE LIFE
STAINLESS STEEL-316