Abstract
An axially heterogeneous sodium-cooled fast reactor design is developed for converting minor actinide waste isotopes into plutonium fuel. The reactor design incorporates zirconium hydride moderating rods in an axial blanket above the active core. The blanket design traps the active core's axial leakage for the purpose of transmuting 241Aminto 238Pu. This 238Pu is then co-recycled with the spent driver fuel to make new driver fuel. Because 238Pu is significantly more fissionable than 241Am in a fast neutron spectrum, the fissile worth of the initial minor actinide material is upgraded by its preconditioning via transmutation in the axial targets. Because the 241 Am neutron capture worth is significantly greater in a moderated epithermal spectrum than the fast spectrum, the axial targets serve as a neutron trap that recovers some of the axial leakage lost by the active core.
| Original language | English |
|---|---|
| Pages (from-to) | 115-134 |
| Number of pages | 20 |
| Journal | Nuclear Technology |
| Volume | 173 |
| Issue number | 2 |
| DOIs | |
| State | Published - Feb 2011 |
Keywords
- Axial target
- Heterogeneous recycle
- Sodium-cooled fast reactor
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