Heterogeneous Transmutation Sodium Fast Reactor

Bays, S. E.

Idaho National Laboratory

关键词: Fuel Pins;    Minor Actinide;    11 - Nuclear Fuel Cycle And Fuel Materials;    Transmutation Axial Target;    Fuel Cycle;   

DOI  :  10.2172/920415
RP-ID  :  INL/EXT-07-13252
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  920415

美国|英语

来源: UNT Digital Library

【 摘 要 】

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 neutron 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 non-flattened and flattened core geometries. 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 comparable size. A mass balance analysis revealed that the heterogeneous design may reduce the number of fast reactors needed to close the current once-through light water reactor fuel cycle.