SM-2 Full Scale Flow Studies Termination Report

One of 93 reports in the series: AEC Research and Development Report available on this site.

PDF Version Also Available for Download.

Description

Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of water at 200 degree F, 31% higher than predicted, part of which was due to presence of instrument leads. Element to element flow … continued below

Physical Description

xxi, 198 pages.

Creation Information

Christenson, J. A.; Richards, W. M. S. & Davidson, S. L. July 30, 1961.

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. 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

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

Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of water at 200 degree F, 31% higher than predicted, part of which was due to presence of instrument leads. Element to element flow distribution varied approximately +-8% from pass average. Channel-to-channel stationary element flow distribution varied approximately +-10% from element average and control rod flow distribution varied from +-8.9% to +-6.4 and -11.6% depending upon rod locations. These variations exceed the original goals of a +-10% and +-12% combined deviation for stationary and control rod elements respectively, but are satisfactory in relation to thermal design. There was no indication of unsatisfactory structural performance of any components under hydrodynamic loadings up to 130% of design values. The test program was terminated after determining flow distribution in the reference core design, omitting any work on the less critical first pass. Based on present understanding of the causes for the observed non-uniformity in distribution, achievement of the target tolerances throughout the reactor should be possible if the test program is to be continued. Recommendations for some of the modifications are contained in this report.

Physical Description

xxi, 198 pages.

Notes

Digitized from microopaque cards.

Contract No. AT(30-3)-326 with the U.S. Atomic Energy Commission, New York Operations Office.

Includes bibliographic references (page 171)

Language

Item Type

Identifier

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

  • Report No.: APAE-89
  • Grant Number: AT(30-3)-326
  • SuDoc Number: Y 3.AT 7:22/APAE-89
  • Accession or Local Control No: metadc1201985
  • Archival Resource Key: ark:/67531/metadc1201985

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.

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).

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • July 30, 1961

Added to The UNT Digital Library

  • Aug. 15, 2019, 10:26 p.m.

Description Last Updated

  • March 20, 2023, 5:48 p.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.

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

Christenson, J. A.; Richards, W. M. S. & Davidson, S. L. SM-2 Full Scale Flow Studies Termination Report, report, July 30, 1961; Schenectady, New York.. (https://digital.library.unt.edu/ark:/67531/metadc1201985/: accessed May 21, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

Back to Top of Screen