Published 1997 | Version v1
Journal article

Anisotropic biaxial creep of textured zircaloy: Application to in-reactor life prediction

Creators

  • 1. North Carolina State Univ., Raleigh, NC (United States)

Description

Zirconium alloys are commonly used in light water reactors as thin-walled tubings to prevent coolant-fuel contact and to retain fission gases. These alloys have hexagonal close-packed crystal structure with low c/a ratio at and below the reactor operating temperatures and exhibit preferred orientations or textures. The anisotropic mechanical properties in turn affect their in-service behavior such as in-pile creep-down of the cladding tubes. Creep anisotropy was characterized using biaxial creep tests and the creep-loci constructed at constant energy dissipation deviated from isotropy. The anisotropy parameters derived from the loci agreed with those obtained from the strain-rate ratios at varied stress ratios. Effects of cold work were clearly revealed in that the relatively strong hoop direction for the recrystallized (Rx) material became far weaker

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
77
Journal Page Range
p. 167-168.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
1997 American Nuclear Society (ANS) winter meeting.
Dates
16-20 Nov 1997.
Place
Albuquerque, NM (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
29020979
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CREEP; CRYSTAL STRUCTURE; ISOTROPY; MECHANICAL PROPERTIES; REACTOR COMPONENTS; STRAIN RATE; TUBES; WATER COOLED REACTORS; ZIRCALOY
Descriptors DEC
ALLOYS; REACTORS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Secondary number(s)
CONF-971125--.