THERMAL STRESS TESTING OF SM-2 FUEL ELEMENTS. Final Report for January 1, 1959 to July 1, 1960

PDF Version Also Available for Download.

Description

To determine the thermal stability of SM-2-welded plate type fuel elements, test specimens were subjected to temperature differences across plate width. Thermal deflections caused by the relatively cool side plates restraining the axial expansion of the fuel region were measured along the axial centerline of the test specimens. Region-averaged temperature differences varied from 0 to ll6/sup o/F, or about l35% of expected reactor operating differentials. Test specimens, machined from standard full-sized fuel elements, consisted of a single fuel plate and its proportionate share of element side plates, and displayed an l-shaped cross section. Thermal deflections of 0.005 in. maximum were ... continued below

Physical Description

Pages: 31

Creation Information

Christenson, J.A. & Kortheuer, J.D. September 20, 1960.

Context

This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. 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.

Description

To determine the thermal stability of SM-2-welded plate type fuel elements, test specimens were subjected to temperature differences across plate width. Thermal deflections caused by the relatively cool side plates restraining the axial expansion of the fuel region were measured along the axial centerline of the test specimens. Region-averaged temperature differences varied from 0 to ll6/sup o/F, or about l35% of expected reactor operating differentials. Test specimens, machined from standard full-sized fuel elements, consisted of a single fuel plate and its proportionate share of element side plates, and displayed an l-shaped cross section. Thermal deflections of 0.005 in. maximum were measured at the expected reactor operating conditions of 87/sup o/F region- averaged temperature differences. With initial (cold) deflections assumed within the SM-2 tolerance of (?) 0.008 in., test results indicated that the total operating deflections will be (?) 0.013 in. maximum. (auth)

Physical Description

Pages: 31

Notes

NTIS

Source

  • Other Information: Orig. Receipt Date: 31-DEC-61

Language

Item Type

Identifier

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

  • Report No.: APAE-Memo-268
  • Grant Number: AT(30-3)-326
  • DOI: 10.2172/4153294 | External Link
  • Office of Scientific & Technical Information Report Number: 4153294
  • Archival Resource Key: ark:/67531/metadc865270

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.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • September 20, 1960

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 3

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

Christenson, J.A. & Kortheuer, J.D. THERMAL STRESS TESTING OF SM-2 FUEL ELEMENTS. Final Report for January 1, 1959 to July 1, 1960, report, September 20, 1960; United States. (digital.library.unt.edu/ark:/67531/metadc865270/: accessed October 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.