Dimensional, microstructural and compositional stability of metal fuels. Final performance report
The projects undertaken were to address two areas of concern for metal-fueled fast reactors: metallurgical compatibility of fuel and its fission products with the stainless steel cladding, and effects of porosity development in the fuel on fuel/cladding interactions and on sodium penetration in fuel. The following studies are reported on extensively in appendices: hot isostatic pressing of U-10Zr by coupled boundary diffusion/power law creep cavitation, liquid Na intrusion into porous U-10Zr fuel alloy by differential capillarity, interdiffusion between U-Zr fuel and selected Fe-Ni-Cr alloys, interdiffusion between U-Zr fuel vs selected cladding steels, and interdiffusion of Ce in Fe-base alloys with Ni or Cr.
- Research Organization:
- Purdue Univ., Lafayette, IN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- FG02-88ER12814
- OSTI ID:
- 10136824
- Report Number(s):
- DOE/ER/12814-4; ON: DE93010920
- Resource Relation:
- Other Information: PBD: 15 Mar 1993
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALLOY NUCLEAR FUELS
URANIUM BASE ALLOYS
HOT PRESSING
ZIRCONIUM ALLOYS
FUEL-CLADDING INTERACTIONS
IFR REACTOR
PROGRESS REPORT
SODIUM COOLED REACTORS
POROUS MATERIALS
FISSION PRODUCTS
DIFFUSION
GRAIN BOUNDARIES
LIQUID METALS
SODIUM
210500
POWER REACTORS
BREEDING