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AbstractAbstract
[en] 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
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1 Sep 2007; vp; Global 2007: Advanced Nuclear Fuel Cycles and Systems; Boise, ID (United States); 9-13 Sep 2007; AC07-99ID-13727; Available from http://www.inl.gov/technicalpublications/Documents/3792212.pdf; PURL: https://www.osti.gov/servlets/purl/918168-6ua4k9/
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Report
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Conference
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ACTINIDE NUCLEI, ALKALI METALS, ALPHA DECAY RADIOISOTOPES, AMERICIUM ISOTOPES, BARYON REACTIONS, ELEMENTS, ENERGY SOURCES, EPITHERMAL REACTORS, FUEL ELEMENTS, FUELS, HADRON REACTIONS, HEAVY NUCLEI, ISOTOPES, MATERIALS, METALS, NUCLEAR REACTIONS, NUCLEI, NUCLEON REACTIONS, ODD-EVEN NUCLEI, RADIOISOTOPES, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, YEARS LIVING RADIOISOTOPES
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