Transmutation of americium in a medium size sodium cooled fast reactor design
2010 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 37, no 5, 629-638 p.Article, review/survey (Refereed) Published
We have performed transient analysis of a medium size sodium cooled reactor loaded with different fractions of americium in the fuel. Unprotected Loss of Flow (ULOF) and Unprotected Transient over Power (UTOP) accidents were simulated in a geometrical model of BN600, using safety parameters obtained with the SERPENT Monte Carlo code. For the reference case of MOX fuel, with 1 wt.% Am concentration at BOL and EOEC, the margin to melt following a design basis condition UTOP is about 100 K for a maximum linear rating of 37 kW/m. Introducing Am, the maximum fuel temperature increases by 50 K per percent Am in the fuel. In order to maintain a margin of 100 K to fuel failure, the linear rating has to be reduced by similar to 6% for each percent Am added to the fuel. Hence, an Am concentration of 2-3 wt.% in the fuel would lead to a power penalty of 6-13%, permitting a consumption rate of 1.7-3.4 kg Am/TWh(th). (C) 2009 Elsevier Ltd. All rights reserved.
Place, publisher, year, edition, pages
2010. Vol. 37, no 5, 629-638 p.
Subatomic Physics Engineering and Technology
IdentifiersURN: urn:nbn:se:kth:diva-27895DOI: 10.1016/j.anucene.2009.12.014ISI: 000277540000001ScopusID: 2-s2.0-77950299511OAI: oai:DiVA.org:kth-27895DiVA: diva2:384434
QC 201101102011-01-102011-01-032012-02-01Bibliographically approved