Published September 1, 2007 | Version v1
Report

Physics Characterization of a Heterogeneous Sodium Fast Reactor Transmutation System

Description

The threshold-fission (fertile) nature of Am-241 is used to destroy this minor actinide 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.

Additional details

Publishing Information

Imprint Pagination
vp.
Report number
INL/CON--07-12476

Conference

Title
Advanced Nuclear Fuel Cycles and Systems
Acronym
Global 2007
Dates
9-13 Sep 2007
Place
Boise, ID (United States)

Optional Information

Contract/Grant/Project number
AC07-99ID-13727
Funding organization
DOE - NE (United States)