Properties of an irradiated heat-treated Zr-2.5Nb pressure tube removed from the NPD reactor

ASTM Special Technical Publication

Volumn 1295, Issue , 1996, Pages 469-491

  Chow, C K ^a   Coleman, C E ^b   Koike, M H ^c   Causey, A R ^b   Ells, C E ^b   Hosbons, R R ^b   Sagat, S ^b   Urbanic, V F ^b   Rodgers, D K ^b  

^a ATOMIC ENERGY OF CANADA LIMITED   (Canada)

^b CANADIAN NUCLEAR LABORATORIES   (Canada)

^c JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

Creep; Delayed hydride cracking; Deuterium; DHC; Fatigue; Fracture toughness; Heat treated Zr 2.5Nb; Irradiation deformation; Oxidation; Pressure tube; Tensile properties

Indexed keywords

CORROSION; CRACK INITIATION; CRACK PROPAGATION; CREEP TESTING; FATIGUE OF MATERIALS; FRACTURE TOUGHNESS; HEAT TREATMENT; HEAVY WATER REACTORS; PRESSURE TUBE REACTORS; STRESS INTENSITY FACTORS; TENSILE STRENGTH; TENSILE TESTING;

CRACK GROWTH RATES; DELAYED HYDRIDE CRACKING;

ZIRCONIUM ALLOYS;

EID: 0030289409     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp16186s     Document Type: Article

References (33)

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