Postirradiation cladding strength under biaxial loading with an increasing temperature ramp. [LMFBR]

Conference · Tue Apr 01 04:00:00 EST 1980

OSTI ID:5208037

Duncan, D. R.; Hunter, C. W.

The flow behavior of unirradiated 20% cold worked AISI 316 tubing during constant pressure, increasing temperature tests was modeled with a constitutive relation approach; strain below approximately 0.2% came predominantly from an anelastic portion of the model while higher strains were predominantly plastic. The flow of cladding sections from irradiated fuel pins was largely restricted to the strain region attributed to anelastic deformation due to reduced ductility compared to unirradiated tubing. Another major effect of irradiation exposure on cladding flow was softening, or increased strain, found with increasing irradiation temperature. This was noted only when test pressures were high enough to cause flow below 950/sup 0/K.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC14-76FF02170
• OSTI ID: 5208037
• Report Number(s): HEDL-SA-2011-FP; CONF-800609-11
• Country of Publication: United States
• Language: English

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