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A method (approach) have been developed for SCC tests of sheet specimens from zirconium alloys which includes: exposure in iodine-methanol solution, quantitative analysis of corrosion defects, tensile tests of corroded specimens and quantitative analysis of fracture surfaces and cross sections. A comparison was made between sheets of as-received and ultrafinegrained zirconium alloys for nuclear reactors to discuss its applicability in the nuclear industry.
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