Transmutation of Americium in Fast Neutron Facilities
In this thesis, the feasibility to use a medium sized sodium cooled fast reactor fully loaded with MOX fuel for efficient transmutation of americium is investigated by simulating the safety performance of a BN600-type fast reactor loaded with different fractions of americium in the fuel, using the s...
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| Format: | Others |
| Language: | English |
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KTH, Reaktorfysik
2011
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| Online Access: | http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-31518 http://nbn-resolving.de/urn:isbn:978-91-7415-890-8 |