Effects of hydride precipitate localization and neutron fluence on the ductility of irradiated Zircaloy-4
- ABB Combustion Engineering Nuclear Operations, Windsor, CT (United States)
The ductility of highly irradiated Zircaloy-4 material was evaluated by conducting tube burst, tube tensile, and ring tensile tests on fuel cladding and guide tubes irradiated in two PWRs. The specimen fluence ranged between 9 and 12.3 {times} 10{sup 21} n/cm{sup 2} (E > 1 MeV), and test temperatures ranged from 313 to 673 K. The average thickness of the waterside oxide layer on the specimens ranged from 12 to 114 {micro}m. Specimens with an oxide thickness greater than about 100 {micro}m contained regions of spalling oxide and local areas of oxide significantly thicker than the specimen average. The corresponding average hydrogen contents ranged from 40 to 674 ppm for specimens without spalling oxide and estimated to be greater than 950 ppm with spalling. Non-uniform hydride distributions were observed in the specimens due to temperature gradients during operation. The residual ductility for these high-fluence specimens is on the order of 1% uniform plastic strain for all the specimens except for two specimens with average concentration of hydrogen greater than 700 ppm and spalled oxide. Neckdown and spiral fractures were observed. Examination of fracture surfaces indicated ductile failure in the metallic ligaments separating the hydride precipitates that appeared to have failed in a brittle fashion. The ductility data are analyzed by treating the material as a composite hydride phase with a reduced presence of metallic ligaments in the composite results in reduction of ductility. A local hydride volume fraction greater than a critical value is needed to initiate and propagate fracture across the specimen cross section to thereby reduce the ductility below a set value. A model is proposed to suggest a possible ductility minima at intermediate fluences and the effect of hydride precipitates on ductility.
- OSTI ID:
- 479446
- Report Number(s):
- CONF-950926-; TRN: 97:010515
- Resource Relation:
- Conference: 11. international symposium on zirconium in the nuclear industry, Garmisch-Partenkirchen (Germany), 11-14 Sep 1995; Other Information: PBD: 1996; Related Information: Is Part Of Zirconium in the nuclear industry: Eleventh international symposium; Bradley, E.R. [ed.] [Sandvik Special Metals Corp., Kennewick, WA (United States)]; Sabol, G.P. [ed.] [Westinghouse Electric Corp., Pittsburgh, PA (United States)]; PB: 911 p.; American Society for Testing and Materials STP 1295
- Country of Publication:
- United States
- Language:
- English
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