Performance of HT9 clad metallic fuel at high temperature

Conference · Tue Dec 01 04:00:00 EST 1992

DOI:https://doi.org/10.1016/0022-3115(93)90210-P· OSTI ID:10117065

Pahl, R G; Lahm, C E; Hayes, S L

Steady-state testing of HT9 clad metallic fuel at high temperatures was initiated in EBR-II in November of 1987. At that time U-10 wt. % Zr fuel clad with the low-swelling ferritic/martensitic alloy HT9 was being considered as driver fuel options for both EBR-II and FFTF. The objective of the X447 test described here was to determine the lifetime of HT9 cladding when operated with metallic fuel at beginning of life inside wall temperatures approaching {approximately}660{degree}C. Though stress-temperature design limits for HT9 preclude its use for high burnup applications under these conditions due to excessive thermal creep, the X447 test was carried out to obtain data on high temperature breach phenomena involving metallic fuel since little data existed in that area.

• Research Organization: Argonne National Lab., Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10117065
• Report Number(s): ANL/FE/CP--76393; CONF-921102--50; ON: DE93004852
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500
ALLOY-HT-9
CLADDING
EBR-2 REACTOR
FFTF REACTOR
FUEL ASSEMBLIES
FUEL ELEMENTS
MIXED OXIDE FUELS
POWER REACTORS
BREEDING
TEMPERATURE RANGE 0400-1000 K
TESTING
ZIRCONIUM ALLOYS