Irradiation performance of Fast Flux Test Facility drivers using D9 alloy
Description
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 x 1022 n/cm2 (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 x 1022 n/cm2, 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
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE94015711; NTIS; US Govt. Printing Office Dep.Files
26000435.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 26 p.
- Report number
- WHC-SA--2261
Conference
- Title
- 35. annual meeting of the American Nuclear Society.
- Dates
- 11-16 Jun 1994.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26000435
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY-D-9; DEFORMATION; FFTF REACTOR; FUEL ASSEMBLIES; FUEL CANS; MATERIAL SUBSTITUTION; MATERIALS TESTING; PHYSICAL RADIATION EFFECTS; POST-IRRADIATION EXAMINATION; RELIABILITY; SERVICE LIFE; STAINLESS STEEL-316
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; EPITHERMAL REACTORS; FAST REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; LIQUID METAL COOLED REACTORS; MATERIALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; TEST FACILITIES; TEST REACTORS; TESTING
Optional Information
- Contract/Grant/Project number
- Contract AC06-87RL10930
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-940602--15.