Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity

One of 5,980 items in the series: Atomic Energy Commission Reports available on this site.
Thumbnail image of item number 1 in: 'Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity'.
Thumbnail image of item number 2 in: 'Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity'.
Thumbnail image of item number 3 in: 'Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity'.
Thumbnail image of item number 4 in: 'Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity'.
Showing 1-4 of 22 pages in this report.

PDF Version Also Available for Download.

Description

Abstract: The question of how crack-free, protective oxide films can form on zirconium during oxidation when the Pilling-Bedworth ratio is about 1.5 has been considered by a study of the relative plasticity of various forms of zirconia. Hot hardness measurements showed that doping mono-clinic zirconia with iron, nickel, or chromium resulted in softer (more plastic) structures and that yttrium additions slightly reduced the plasticity. Calcia-stabilized cubic zirconia was found to be more plastic than mono-clinic zirconia when tested at temperatures above 200 degrees C. The behavior of anion-deficient oxides indicated that they were more plastic than stoichiometric oxides even though … continued below

Physical Description

20 pages ; illustrations.

Creation Information

Douglass, D. L. (David Leslie), 1931- February 20, 1964.

Context

This report is part of the collection entitled: Technical Report Archive and Image Library and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 19 times. More information about this report can be viewed below.

Who

People and organizations associated with either the creation of this report or its content.

Author

Sponsors

Publisher

  • Vallecitos Atomic Laboratory
    Publisher Info: General Electric Company. Vallecitos Atomic Laboratory. Atomic Power Equipment Department.
    Place of Publication: San Jose, California

Audiences

We've identified this report as a primary source within our collections. Researchers, educators, and students may find this report useful in their work.

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

About | Browse this Partner

Contact Us

Corrections Questions

What

Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.

Titles

Description

Abstract: The question of how crack-free, protective oxide films can form on zirconium during oxidation when the Pilling-Bedworth ratio is about 1.5 has been considered by a study of the relative plasticity of various forms of zirconia. Hot hardness measurements showed that doping mono-clinic zirconia with iron, nickel, or chromium resulted in softer (more plastic) structures and that yttrium additions slightly reduced the plasticity. Calcia-stabilized cubic zirconia was found to be more plastic than mono-clinic zirconia when tested at temperatures above 200 degrees C. The behavior of anion-deficient oxides indicated that they were more plastic than stoichiometric oxides even though the hardness values were identical at 23 degrees C. The former were free from cracks at the indentions, whereas, stoichiometric oxides exhibited extensive cracking around and between indentions. The behavior of actual, thick (72 microns) oxide films during tensile deformation of oxidized metal samples indicated that considerable plasticity occurs in the oxide at 500 degrees C but that the films are brittle at 23 degrees C. It was concluded that the plasticity of the oxide may be greater than that of the oxygen-contaminated substrate at elevated temperatures and may be the means by which epitaxial strains are minimized.

Physical Description

20 pages ; illustrations.

Notes

Digitized from microopaque cards.

U.S. Atomic Energy Commission Contract AT(04-3)-189 Project Agreement 24.

Includes bibliographic references (page 17).

Language

Item Type

Identifier

Unique identifying numbers for this report in the Digital Library or other systems.

  • Report No.: GEAP-4473
  • Grant Number: AT(04-3)-189 PA 24
  • SuDoc Number: Y 3.At 7:22/GEAP-4473
  • Accession or Local Control No: metadc1201412
  • Archival Resource Key: ark:/67531/metadc1201412

Collections

This report is part of the following collections of related materials.

Technical Report Archive and Image Library

The Technical Report Archive & Image Library (TRAIL) identifies, acquires, catalogs, digitizes and provides unrestricted access to U.S. government agency technical reports. The mission of TRAIL is to ensure preservation, discoverability, and persistent open access to government technical publications regardless of form or format.

About | Browse this Collection

TRAIL Microcard Collection

Imaged from microcard, these technical reports describe research performed for U.S. government agencies from the 1930s to the 1960s. The reports were provided by the Technical Report Archive and Image Library (TRAIL).

About | Browse this Collection

What responsibilities do I have when using this report?

Digital Files

When

Dates and time periods associated with this report.

Creation Date

  • February 20, 1964

Added to The UNT Digital Library

  • Aug. 15, 2019, 10:26 p.m.

Description Last Updated

  • June 25, 2024, 1:08 a.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 19
More Statistics

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

Thumbnail image of item number 1 in: 'Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity'.
Thumbnail image of item number 2 in: 'Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity'.
Thumbnail image of item number 3 in: 'Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity'.
Thumbnail image of item number 4 in: 'Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity'.

PDF Version Also Available for Download.

Citations, Rights, Re-Use

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

Links for Robots

Helpful links in machine-readable formats.

Archival Resource Key (ARK)

International Image Interoperability Framework (IIIF)

Metadata Formats

Images

URLs

Stats

Douglass, D. L. (David Leslie), 1931-. Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity, report, February 20, 1964; San Jose, California. (https://digital.library.unt.edu/ark:/67531/metadc1201412/: accessed March 23, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

Back to Top of Screen