Published 1977 | Version v1
Report Restricted

Experimental and theoretical studies on water and gas release from heated concrete

Description

Procedures currently used in licensing of nuclear facilities require analysis of postulated accidents which are more severe than ''design basis'' events. For breeder program reactors, some accidents in this severe category involve spillage of sodium coolant onto concrete protected by a steel liner. Heat transfer through the liner heats the concrete, causing a part of the mixing water and other gases to be driven off. These gases would add to pressure in the containment atmosphere, and the water vapor can form hydrogen if it contacts sodium. Evaluations of containment integrity for such postulated accidents will be aided by knowledge of how much water and other gases are released from heated concrete. The report presents results of a research effort at Hanford Engineering Development Laboratory designed to improve understanding of the release of water and gases from heated concrete

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
LMFBR

Publishing Information

Imprint Pagination
11 p.
Report number
HEDL-SA--1380

Conference

Title
Post accident heat removal information exchange meeting.
Dates
2 - 3 Nov 1977.
Place
Chicago, IL, USA.

Optional Information

Secondary number(s)
CONF-771108--8.