Predicting the in-reactor mechanical behavior of Zr-2.5Nb pressure tubes from postirradiation microstructural examination data

ASTM Special Technical Publication

Volumn , Issue 1423, 2002, Pages 507-521

  Griffiths, M ^a   Davies, P H ^a   Davies, W G ^a   Sagat, S ^a  

^a CANADIAN NUCLEAR LABORATORIES   (Canada)

Author keywords

Correlation; Delayed hydride cracking; Mechanical properties; Microstructure; Neutron irradiation; Nuclear reactor materials; Pressure tubes; Radiation damage; Total elongation; Ultimate tensile strength; Yield stress; Zirconium alloys; Zr 2.5Nb

Indexed keywords

CORRELATION METHODS; CRACK INITIATION; DISLOCATIONS (CRYSTALS); FRACTURE TOUGHNESS; HYDRIDES; MICROSTRUCTURE; NEUTRON IRRADIATION; PRESSURE TUBE REACTORS; RADIATION DAMAGE; TENSILE STRENGTH; TUBES (COMPONENTS); X RAY DIFFRACTION ANALYSIS; YIELD STRESS;

BETA-PHASES; DELAYED HYDRIDE CRACKING; DISLOCATION DENSITY; LINE BROADENING; NUCLEAR REACTOR MATERIALS; PRESSURE TUBES; TOTAL ELONGATION; ULTIMATE TENSILE STRENGTH; ZR-2.5NB ALLOYS;

ZIRCONIUM ALLOYS;

EID: 8844231034     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp11404s     Document Type: Conference Paper

References (13)

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2. Sagat, S., Coleman, C. E., Griffiths, M., and Wilkins, B. J. S., "The Effect of Fluence and Irradiation Temperature on Delayed Hydride Cracking in Zr-2.5Nb," Tenth International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1245, American Society for Testing and Materials, 1994. pp. 35-61.
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