CRITICAL HEAT FLUX AND FLOW PATTERN CHARACTERISTICS OF HIGH PRESSURE BOILING WATER IN FORCED CONVECTION

PDF Version Also Available for Download.

Description

High-speed motion pictures of boiling water flow patterns in conditions of forced flow at 1000 psia pressure in a vertical heated rectangular channel were taken at mass velocities from 50 to 400 lbs/sec-ft/sup 2/, fluid states from 170 Btu/lb buik enthalpy of subcooling to 0.68 bulk steam quality, and heat tluxes up to and including the critical heat flux level. An objective of the work was to make the results available for continued experimental and theoretical investigation of the critical heat flux phenomenon in forced-flow bulk-boiling systems. The results are intended to be applicable to design and development of nuclear ... continued below

Physical Description

Pages: 223

Creation Information

Tippets, F.E. April 1, 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.

Author

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

High-speed motion pictures of boiling water flow patterns in conditions of forced flow at 1000 psia pressure in a vertical heated rectangular channel were taken at mass velocities from 50 to 400 lbs/sec-ft/sup 2/, fluid states from 170 Btu/lb buik enthalpy of subcooling to 0.68 bulk steam quality, and heat tluxes up to and including the critical heat flux level. An objective of the work was to make the results available for continued experimental and theoretical investigation of the critical heat flux phenomenon in forced-flow bulk-boiling systems. The results are intended to be applicable to design and development of nuclear power reactors employing high-pressure boiling water as a working fluid. Motion pictures show substantial, but not indisputable, evidence that the general arrangement of the flow, in conditions of bulk boiling, at heat fluxes near and including the critical heat flux level is characteristically a wavy turbulent liquid film, in which there is vapor formation, flowing along the channel walls with the balance of the liquid being carried as either dispersed droplets or as an emulsion with the vapor in an adjacent more rapidly and steadily moving core. (auth)

Physical Description

Pages: 223

Source

  • Other Information: Orig. Receipt Date: 31-DEC-63

Language

Item Type

Identifier

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

  • Report No.: GEAP-3766
  • Grant Number: AT(04-3)-189
  • DOI: 10.2172/4757612 | External Link
  • Office of Scientific & Technical Information Report Number: 4757612
  • Archival Resource Key: ark:/67531/metadc1034485

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

  • April 1, 1962

Added to The UNT Digital Library

  • Oct. 18, 2017, 7:39 a.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 2

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

Tippets, F.E. CRITICAL HEAT FLUX AND FLOW PATTERN CHARACTERISTICS OF HIGH PRESSURE BOILING WATER IN FORCED CONVECTION, report, April 1, 1962; United States. (digital.library.unt.edu/ark:/67531/metadc1034485/: accessed June 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.