Biaxial creep behavior of textured zircaloy tubing

Journal Article · Sat Feb 01 04:00:00 EST 1992 · JOM (Journal of the Minerals, Metals and Materials Society); (United States)

DOI:https://doi.org/10.1007/BF03222771· OSTI ID:5576004

Murty, L K ^[1]

---

1. North Carolina State Univ., NC (US)

This paper reports on zirconium alloys which are commonly used in light-water reactors as thin-walled tubing to clad highly radioactive fuel. The tubes experience varied stresses at high temperatures while being exposed to high-neutron radiation, resulting in thermal creep and radiation growth and creep. However, the dimensional stability of these materials is important to preventing leakage of fission gases and contamination of the coolant water. Predicting the dimensional changes of the thin-walled tubes is further complicated by the anisotropic nature of the hexagonal close-packaged metals. This article summarizes the procedures used in the texture analyses and crystal plasticity in developing model equations to predict the dimensional changes of Zircaloy fuel cladding, both out-of-pile and in-reactor. These methodologies can be extended to the life prediction of these important structures in nuclear reactors.

• Sponsoring Organization: NSF; National Science Foundation, Washington, DC (United States)
• OSTI ID: 5576004
• Journal Information: JOM (Journal of the Minerals, Metals and Materials Society); (United States), Journal Name: JOM (Journal of the Minerals, Metals and Materials Society); (United States) Vol. 44:2; ISSN JOMME
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CREEP
DESIGN
ENVIRONMENTAL EFFECTS
FABRICATION
FUEL-CLADDING INTERACTIONS
HARDENING
HEAT TREATMENTS
MATERIALS TESTING
MATERIALS WORKING
MECHANICAL PROPERTIES
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
PLASTICITY
PRESSURE TUBES
RADIATION EFFECTS
RADIATION HARDENING
REACTOR COMPONENTS
REACTORS
STRUCTURAL MODELS
TESTING
TEXTURE
THERMOMECHANICAL TREATMENTS
TUBES
WATER COOLED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS