Safety Analysis of Na and Pb-Bi Coolants in Response to Beam Instabilities
2003 (English)In: UTILISATION AND RELIABILITY OF HIGH POWER PROTON ACCELERATORS, WORKSHOP PROCEEDINGS, 2003, 227-236 p.Conference paper (Refereed)
A comparative safety study has been performed on sodium vs. lead/bismuth as coolant for accelerator-driven systems. Transient studies are performed for a beam overpower event. We examine a fuel type of recent interest in the research on minor actinide burners, i.e. uranium-free oxide fuel. A strong positive void coefficient is calculated for both sodium and lead/bismuth. This is attributed to the high fraction of americium in the fuel. It is shown that the lead/bismuth-cooled reactor features twice the grace time with respect to fuel or cladding damage compared to the sodium-cooled reactor of comparable core size and power rating. This accounts to the difference in void reactivity contribution and to the low boiling point of sodium. For improved safety features the general objective is to reduce the coolant void reactivity effect. An important safety issue is the high void worth that could possibly drive the system to prompt criticality.
Place, publisher, year, edition, pages
2003. 227-236 p.
IdentifiersURN: urn:nbn:se:kth:diva-4983ISI: 000184283600019ISBN: 92-64-10211-6OAI: oai:DiVA.org:kth-4983DiVA: diva2:7339
3rd Workshop on Utilisation and Reliability of High Power Proton Accelerators
QC 20101011 NR 201408052005-03-072005-03-072012-01-31Bibliographically approved