Numerical results of PT-IP-338A and supplement A: DR reactor heat decay test at high outlet water temperatures

PDF Version Also Available for Download.

Description

This report summarizes the results obtained in the experimental measurement of the reactor heat extracted by the coolant during two different scrams of the DR Reactor. These tests were conducted with the reactor flow carefully controlled to establish different reactor coolant temperatures following the scram. During normal reactor scrams, which have been used in the past to measure the reactor heat output, a high coolant flow was maintained. Consequently, the coolant outlet temperature dropped very quickly from an operating value of 90 to 95 C down to 20 to 30 C following the scram. Under emergency conditions, however, with only ... continued below

Physical Description

40 p.

Creation Information

Jones, S.S. & Manuel, J.L. December 3, 1962.

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.

Sponsor

Publisher

  • Hanford Atomic Products Operation
    Publisher Info: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
    Place of Publication: Richland, Washington

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

This report summarizes the results obtained in the experimental measurement of the reactor heat extracted by the coolant during two different scrams of the DR Reactor. These tests were conducted with the reactor flow carefully controlled to establish different reactor coolant temperatures following the scram. During normal reactor scrams, which have been used in the past to measure the reactor heat output, a high coolant flow was maintained. Consequently, the coolant outlet temperature dropped very quickly from an operating value of 90 to 95 C down to 20 to 30 C following the scram. Under emergency conditions, however, with only the last ditch emergency flow available, the coolant outlet temperature could remain as high as 80 to 90 C. This condition could prevail because of the small amount of last ditch flow available, and could last for 5 to as long as 70 minutes after the reactor scram.

Physical Description

40 p.

Notes

OSTI as DE95007377

Source

  • Other Information: DN: Declassified

Language

Item Type

Identifier

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

  • Other: DE95007377
  • Report No.: HW--75727
  • Grant Number: AC06-76RL01830
  • DOI: 10.2172/29395 | External Link
  • Office of Scientific & Technical Information Report Number: 29395
  • Archival Resource Key: ark:/67531/metadc677696

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

  • December 3, 1962

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

Description Last Updated

  • Feb. 20, 2017, 4:30 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.

Citations, Rights, Re-Use

Jones, S.S. & Manuel, J.L. Numerical results of PT-IP-338A and supplement A: DR reactor heat decay test at high outlet water temperatures, report, December 3, 1962; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc677696/: accessed October 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.