Transmutation of americium in a medium size sodium cooled fast reactor design
In: Annals of Nuclear Energy, Jg. 37 (2010), Heft 5, S. 629-638
Online
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Zugriff:
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.
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Transmutation of americium in a medium size sodium cooled fast reactor design
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Autor/in / Beteiligte Person: | Zhang, Youpeng ; Wallenius, Janne ; Fokau, Andrei |
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Zeitschrift: | Annals of Nuclear Energy, Jg. 37 (2010), Heft 5, S. 629-638 |
Veröffentlichung: | 2010 |
Medientyp: | unknown |
ISSN: | 0306-4549 (print) ; 1873-2100 (print) |
DOI: | 10.1016/j.anucene.2009.12.014 |
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