The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes

One of 776 items in the series: AEC research and development report available on this site.

PDF Version Also Available for Download.

Description

Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).

Physical Description

20 p. : ill. ; 27 cm.

Creation Information

Pessl, H. J. July 30, 1963.

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 133 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

  • Pessl, H. J. Metallurgy Research, Reactor and Fuels Laboratory, Hanford Laboratories

Publisher

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.

Contact Us

What

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

Titles

Description

Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).

Physical Description

20 p. : ill. ; 27 cm.

Subjects

Language

Item Type

Identifier

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

  • OCLC: 702188382
  • SuDoc Number: Y 3.At 7:22/HW-78424
  • Grant Number: AT(45-1)-1350
  • Report No.: HW-78424
  • Archival Resource Key: ark:/67531/metadc100631

Collections

This report is part of the following collection 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.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • July 30, 1963

Added to The UNT Digital Library

  • Jan. 31, 2014, 11:57 a.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 133

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

Pessl, H. J. The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes, report, July 30, 1963; Washington D.C.. (https://digital.library.unt.edu/ark:/67531/metadc100631/: accessed February 17, 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