Published January 13, 2000 | Version v1
Report Open

Investigation of vessel exterior air cooling for a HLMC reactor

Description

The Secure Transportable Autonomous Reactor (STAR) concept under development at Argonne National Laboratory provides a small (300 MWt) reactor module for steam supply that incorporates design features to attain proliferation resistance, heightened passive safety, and improved cost competitiveness through extreme simplification. Examples are the achievement of 100%+ natural circulation heat removal from the low power density/low pressure drop ultra-long lifetime core and utilization of lead-bismuth eutectic (LBE) coolant enabling elimination of main coolant pumps as well as the need for an intermediate heat transport circuit. It is required to provide a passive means of removing decay heat and effecting reactor cooldown in the event that the normal steam generator heat sink, including its normal shutdown heat removal mode, is postulated to be unavailable. In the present approach, denoted as the Reactor Exterior Cooling System (RECS), passive decay heat removal is provided by cooling the outside of the containment/guard vessel with air. RECS is similar to the Reactor Vessel Auxiliary Cooling System (RVACS) incorporated into the PRISM design. However, to enhance the heat removal, RECS incorporates fins on the containment vessel exterior to enhance heat transfer to air as well as removable steel venetian conductors that provide a conduction heat transfer path across the reactor vessel-containment vessel gap to enhance heat transfer between the vessels. The objective of the present work is to investigate the effectiveness of air cooling in removing heat from the vessel and limiting the coolant temperature increase following a sudden complete loss of the steam generator heat sink

Availability note (English)

Available from INIS in electronic form; Also available from OSTI as DE00751887; PURL: https://www.osti.gov/servlets/purl/751887-qmPS4n/webviewable/

Files

31047278.pdf

Files (134.1 kB)

Name Size Download all
md5:9ae24f14392387b066d6e169daf6f780
134.1 kB Preview Download

Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
ANL/RE/CP--100912

Conference

Title
4. ANS Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management
Dates
4-8 Jun 2000
Place
San Diego, CA (United States)

INIS

Optional Information

Contract/Grant/Project number
W-31109-ENG-38
Funding organization
US Department of Energy (United States)