Upper limits to americium concentration in large sized sodium-cooled fast reactors loaded with metallic fuel
2014 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 70, 180-187 p.Article in journal (Refereed) Published
Transient analysis of a large sized sodium-cooled reactor loaded with metallic fuel modified by different fractions of americium have been performed. Unprotected loss-of-offsite power, unprotected loss-of-flow and unprotected transient-over-power accidents were simulated with the SAS4A/SASSYS code based on the geometrical model of an IFR1 with power rating of 2500 MW th, using safety parameters obtained with the SERPENT Monte Carlo code. The Ti-modified austenitic D9 steel, having higher creep rupture strength, was considered as the cladding and structural material apart from the ferritic/martensitic HT9 steel. For the reference case of U-12Pu-1Am-10Zr fuel at EOEC, the margin to fuel melt during a design basis condition UTOP is about 50 K for a maximum linear rating of 30 kW/m. In order to maintain a margin of 50 K to fuel failure, the linear power rating has to be reduced by ∼3% and 6% for 2 wt.% and 3 wt.% Am introduction into the fuel respectively. Hence, an Am concentration of 2-3 wt.% in the fuel would lead to a power penalty of 3-6%, permitting a consumption rate of 3.0-5.1 kg Am/TW hth. This consumption rate is significantly higher than the one previously obtained for oxide fuelled SFRs.
Place, publisher, year, edition, pages
2014. Vol. 70, 180-187 p.
Americium transmutation, IFR, Transient analysis
IdentifiersURN: urn:nbn:se:kth:diva-145382DOI: 10.1016/j.anucene.2014.03.007ISI: 000336358400024ScopusID: 2-s2.0-84898060725OAI: oai:DiVA.org:kth-145382DiVA: diva2:718191
QC 201405202014-05-202014-05-192014-06-27Bibliographically approved