Liquid Metal Loops Irradiated on the ORNL Graphite Reactor and the LITR

One of 1,742 reports in the series: Atomic Energy Commission Reports available on this site.

PDF Version Also Available for Download.

Description

From abstract: Liquid alkali metals were circulated in a series of structural alloy loops under reactor radiation at high temperature. The first of these loops was a lithium-stainless steel (type 316) system, and the remainder were sodium-Inconel. No effect of radiation other than radioactivation was found. Mass transfer and metallurgical processes attributable to the operating temperatures were observed."

Physical Description

iii, 36 p. : plates, tables, graphs, diagrams ; 28 cm.

Creation Information

Parkinson, W. W. & Sisman, O. June 1, 1959.

Context

This report is part of the collection entitled: Technical Report Archive and Image Library and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 23 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.

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.

Contact Us

What

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

Titles

Description

From abstract: Liquid alkali metals were circulated in a series of structural alloy loops under reactor radiation at high temperature. The first of these loops was a lithium-stainless steel (type 316) system, and the remainder were sodium-Inconel. No effect of radiation other than radioactivation was found. Mass transfer and metallurgical processes attributable to the operating temperatures were observed."

Physical Description

iii, 36 p. : plates, tables, graphs, diagrams ; 28 cm.

Subjects

Keyword

Library of Congress Subject Headings

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.

Technical Report Archive and Image Library

This selection of materials from the Technical Report Archive and Image Library (TRAIL) includes hard-to-find reports published by various government agencies. The technical publications contain reports, images, and technical descriptions of research performed for U.S. government agencies. Topics range from mining, desalination, and radiation to broader physics, biology, and chemistry studies. Some reports include maps, foldouts, blueprints, and other oversize materials.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • June 1, 1959

Added to The UNT Digital Library

  • Feb. 24, 2016, 4:27 p.m.

Description Last Updated

  • Aug. 4, 2016, 2:44 p.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 1
Total Uses: 23

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

Citations, Rights, Re-Use

Parkinson, W. W. & Sisman, O. Liquid Metal Loops Irradiated on the ORNL Graphite Reactor and the LITR, report, June 1, 1959; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc100277/: accessed November 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.