Transmutation of americium in a large sized sodium-cooled fast reactor loaded with nitride fuel
2013 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 53, 26-34 p.Article in journal (Refereed) Published
We have performed the transient analysis of a large sized sodium-cooled reactor loaded with nitride fuel modified by different fractions of americium. Unprotected loss-of-offsite power, unprotected loss-of-flow and unprotected transient-over-power accidents were considered as the postulated transient and simulated with the SAS4A/SASSYS code based on the geometrical model of a BN1200 type sodium-cooled fast reactor (SFR) with the rated power of 2900 MWth. Safety parameters used in the transient simulation model were obtained from the SERPENT Monte Carlo calculations. If 100 K margin to fuel melting was maintained, 2 wt.% and 6 wt.% Am content could be permitted for the nitride fuel loaded BN1200 operating with the maximum linear power rating of 37 kW/m and 33 kW/m respectively, providing Am transmutation rates of 3.9 kg/TW h(th) and 13.7 kg/TW h(th). These transmutation rates are more than 6 times higher than the ones previously reported for oxide fuel loaded BN600 operating with the maximum linear power ratings of 37 kW/m and metallic fuel loaded Integral Fast Reactor (IFR) operating with the maximum linear power rating of 33 kW/m respectively, being their reference cases with permitting 1 wt.% Am content.
Place, publisher, year, edition, pages
2013. Vol. 53, 26-34 p.
BN1200, Nitride fuel, Americium transmutation, Transient analysis
IdentifiersURN: urn:nbn:se:kth:diva-120294DOI: 10.1016/j.anucene.2012.08.009ISI: 000315550500004ScopusID: 2-s2.0-84870179549OAI: oai:DiVA.org:kth-120294DiVA: diva2:614630
QC 201304052013-04-052013-04-042013-04-05Bibliographically approved