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Physics characterization of a heterogeneous sodium fast reactor transmutation system

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The threshold-fission (fertile) nature of Am-241 is used to destroy this minor actiniae by capitalizing upon neutron capture instead of fission within a sodium fast reactor. This neutron-capture and its subsequent decay chain leads to the breeding of even mass number plutonium isotopes. A slightly moderated target design is proposed for breeding plutonium in an axial blanket located above the active "fast reactor" driver fuel region. A parametric study on the core height and fuel pin diameter-to-pitch ratio is used to explore the reactor and fuel cycle aspects of this design. This study resulted in both a non-flattened and a pancake core geometry. Both of these designs demonstrated a high capacity for removing americium from the fuel cycle. A reactivity coefficient analysis revealed that this heterogeneous design will have comparable safety aspects to a homogeneous reactor of the same size.

Original languageEnglish
Title of host publicationGLOBAL 2007
Subtitle of host publicationAdvanced Nuclear Fuel Cycles and Systems
Pages87-97
Number of pages11
StatePublished - 2007
EventGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems - Boise, ID, United States
Duration: Sep 9 2007Sep 13 2007

Publication series

NameGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems

Conference

ConferenceGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
Country/TerritoryUnited States
CityBoise, ID
Period09/9/0709/13/07

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