SLIP CASTING OF NUCLEAR FUEL ELEMENTS
Technical Report
·
OSTI ID:4227625
A process was developed for fabricatmg thin dispersion fuel element cross sections entirely from powder by variations of the slip casting process. Elements were made 2 in. wide x 4 in. long having a 0.020 in. fuel core of 75% (wt.%) type 316 stainless steel and 25% (wt.%) uranium dioxide (UO/sub 2/ clad on each side with 0.005-in. of type 316 stainless steel. Microstructural examination indicated no fragmentation of the UO/sub 2/, solid demsity cladding, uniform and fine grain size of the stainless steel matrix and cladding, and no discontinuity at the cladding core interface even after drastic cold forming. Tensile properties of the annealed plate, as measured on 1 in. gage length, stamped specimens, were 55,800 psi ultimate stress, 27,600 psi (0.2% offset) yield stress and 19.4% elongation at room temperature. Samples of plates were successfully cold formed through as low as 0.005-in. radius of bend (t/r of 8). Cladding and matrix behaved integrally in tensile and cold forming tests. (auth)
- Research Organization:
- Stevens Inst. of Tech., Hoboken, N.J. Powder Metallurgy Lab.
- NSA Number:
- NSA-13-022379
- OSTI ID:
- 4227625
- Report Number(s):
- AECU-4255
- Country of Publication:
- United States
- Language:
- English
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