Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor

Thumbnail image of item number 1 in: 'Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor'.
Thumbnail image of item number 2 in: 'Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor'.
Thumbnail image of item number 3 in: 'Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor'.
Thumbnail image of item number 4 in: 'Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor'.
Showing 1-4 of 59 pages in this report.

PDF Version Also Available for Download.

Description

The effect of very high heat fluxes on the corrosion of 1100 and 6061 aluminum alloys by water was investigated. The test conditions generally simulated those expected to exist during operation of the High-Flux lsotope Reactor. At heat fluxes between 1 and 2 x l0/sup 6/ Btu/hr-ft/sup 2/ and with coolant temperatures and velocities in the ranges of 13l to 250 deg F and 3l to 51 fps, respectively, a layer of boehmite ( alpha Al/sub 2/O/sub 3/- H/sub 2/0), which has low thermal conductivity, formed on the water-cooled aluminum surfaces during test. When only relatively thin films formed, the … continued below

Physical Description

55 pages

Creation Information

Griess, J. C.; Savage, H. C.; Rainwater, J. G.; Mauney, T. H. & English, J. L. December 20, 1961.

Context

This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports 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 25 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.

Authors

Publisher

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.

Description

The effect of very high heat fluxes on the corrosion of 1100 and 6061 aluminum alloys by water was investigated. The test conditions generally simulated those expected to exist during operation of the High-Flux lsotope Reactor. At heat fluxes between 1 and 2 x l0/sup 6/ Btu/hr-ft/sup 2/ and with coolant temperatures and velocities in the ranges of 13l to 250 deg F and 3l to 51 fps, respectively, a layer of boehmite ( alpha Al/sub 2/O/sub 3/- H/sub 2/0), which has low thermal conductivity, formed on the water-cooled aluminum surfaces during test. When only relatively thin films formed, the boehmite adhered tightly to the aluminum, but in those cases where relatively thick films formed, some boehmite spontaneously spalled from the surface. The rate at which the boehmite formed on the surface (and consequently the rate at which the aluminum temperature increased) was a function of the temperature at the specimen-water interface and the pH of the coolant. The lower the temperature and the lower the pH (in the range of 5.0 to 6.5 with HNO/sub 3/), the lower the rate of corrosion- product formation. Within the ranges investigated, pressure and flow rate were without effect, and the same results were obtained with 6061 and 1100 , aluminum. In those cases where the pH of the coolant was adjusted to 5, corrosion penetration was uniform and even under the most severe conditions did not exceed l.5 mils in 10 days. When the test conditions were such that the rate of oxide formation was high and oxide spalled from the surface of the specimen, localized attack of the aluminum in the form of subsurface voids extending several mils into the metal was always observed. From the experimental data, fluid-film heat- transfer coefficients were calculated and the thermal conductivity of the corrosion product was estimated. The fluid-film heat-transfer coefficients were in excellent agreement with those determined by others under similar conditions, and a value of 1.3 plus or minus 0.2 Btu/hr-ft/sup 2/ deg F/ft was obtained as the thermal conductivity of the corrosion-product film. The results indicate that from a corrosion standpoint either 6061 or 1100 aluminum could be used as cladding material for the High-Flux lsotope Reactor fuel elements, provided the pH of the coolant is maintained at 5.0 to 5.3 with nitric acid. Under test condstions simulating the most severe conditions anticipated during operation of the reactor (hot spot--hot channel) the maximum penetration observed was only 1 mil in 10 days. Although somewhat excessive temperatures are probable at hot spots due to a high rate of corrosion-product buildup, the great majority of the fuel plates will operate at reasonable temperatures. (auth)

Physical Description

55 pages

Notes

Other Information: Orig. Receipt Date: 31-DEC-62

Language

Item Type

Identifier

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

Collections

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

Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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

  • December 20, 1961

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

Description Last Updated

  • Nov. 23, 2024, 2:31 a.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 25
More Statistics

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

Thumbnail image of item number 1 in: 'Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor'.
Thumbnail image of item number 2 in: 'Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor'.
Thumbnail image of item number 3 in: 'Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor'.
Thumbnail image of item number 4 in: 'Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor'.

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

Griess, J. C.; Savage, H. C.; Rainwater, J. G.; Mauney, T. H. & English, J. L. Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor, report, December 20, 1961; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc1056523/: accessed July 19, 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