Performance of U-Pu-Zr fuel cast into zirconium molds

Conference · Thu Oct 01 00:00:00 EDT 1992

DOI:https://doi.org/10.1016/0022-3115(93)90212-H· OSTI ID:6832647

Crawford, D C; Lahm, C E ^[1]; Tsai, H ^[2]

---

1. Argonne National Lab., Idaho Falls, ID (United States)
2. Argonne National Lab., IL (United States)

U-3Zr and U-20.5Pu-3Zr were injection cast into Zr tubes, or sheaths, rather than into quartz molds and clad in 316SS. These elements and standard-cast U-l0Zr and U-IgPu-l0Zr elements were irradiated in EBR-II to 2 at.% and removed for interim examination. Measurements of axial growth at indicate that the Zr-sheathed elements exhibited significantly less axial elongation than the standard-cast elements (1.3 to 1.8% versus 4.9 to 8.1%). Fuel material extruded through the ends of the Zr sheaths. allowing the low-Zr fuel to contact the cladding in some cases. Transverse metallographic sections reveal cracks in the Zr sheath through which fuel extruded and contacted cladding. The sheath is not a sufficient barrier between fuel and cladding to reduce FCCI. and any adverse effects due to increased FCCI will be evident as the elements attain higher burnup.

• Research Organization: Argonne National Lab., Idaho Falls, ID (United States); Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6832647
• Report Number(s): ANL/FE/CP-76392; CONF-921102-44; ON: DE93004239
• Resource Relation: Journal Volume: 204; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
FUEL ELEMENTS
PERFORMANCE
PLUTONIUM
URANIUM
ZIRCONIUM
CLADDING
CRACKS
EBR-2 REACTOR
PHYSICAL RADIATION EFFECTS
STAINLESS STEEL-316
ACTINIDES
ALLOYS
AUSTENITIC STEELS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
DEPOSITION
ELEMENTS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT RESIS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STAINLESS STEELS
STEEL-CR17NI12MO3
STEELS
SURFACE COATING
TRANSITION ELEMENTS
TRANSURANIUM ELEMENTS
220300* - Nuclear Reactor Technology- Fuel Elements
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties