Published October 17, 2002 | Version v1
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Analytical and Experimental Investigation of Mixing in Large Passive Containment Volumes

Description

This final report details results from the past three years of the three-year UC Berkeley NEER investigation of mixing phenomena in large-scale passive reactor containments. We have completed all of our three-year deliverables specified in our proposal, as summarized for each deliverable in the body of this report, except for the experiments of steam condensation in the presence of noncondensable gas. We have particularly exiting results from the experiments studying the mixing in large insulated containment with a vertical cooling plate. These experiments now have shown why augmentation has been observed in wall-condensation experiments due to the momentum of the steam break-flow entering large volumes. More importantly, we also have shown that the forced-jet augmentation can be predicted using relatively simple correlations, and that it is independent of the break diameter and depends only on the break flow orientation, location, and momentum. This suggests that we will now be able to take credit for this augmentation in reactor safety analysis, improving safety margins for containment structures. We have finished the version 1 of 1-D Lagrangian flow and heat transfer code BMIX++. This version has ability to solve many complex stratified problems, such as multi-components problems, multi-enclosures problems (two enclosures connected by one connection for the current version), incompressible and compressible problems, multi jets, plumes, sinks in one enclosure problems, problems with wall conduction, and the combinations of the above problems. We believe the BMIX++ code is a very powerful computation tool to study stratified enclosures mixing problems

Availability note (English)

Available from INIS in electronic form; Also available from OSTI as DE00805793; PURL: https://www.osti.gov/servlets/purl/805793-n1zoZ7/native/

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Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
DOE/ID--13769

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
34025386
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
CONTAINMENT; HEAT TRANSFER; LAGRANGIAN FUNCTION; ORIENTATION; PLUMES; REACTOR SAFETY; SAFETY; STEAM
Descriptors DEC
ENERGY TRANSFER; FUNCTIONS; SAFETY

Optional Information

Contract/Grant/Project number
FG07-99ID13769
Funding organization
United States (United States)