It seems you're expecting to use Boron-11 in the reactor itself. The energy required is 675 keV for the lowest resonance capture energy with a high cross-section as compared to100 MeV for D-T so the input power requirement is much greater. It does have the advantage of removing the neutrons altogether although there might well be neutrons produced from p-He-4 interactions I expect. Electrical power is directly obtainable in this scheme.
http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/24/028/24028563.pdf
My proposal for using Boron-10 would be to place it externally to the reactor behind a moderating blanket of a plastic such as polypropylene or similar that would thermalise the neutrons to about 0.025 MeV; the thermal energy could be extracted using a Brayton cycle. The kinetic energy of the Helium and Lithium ions would be directly converted or the Brayton cycle used.
The cross-section for Boron-10 is much higher than for Boron-11, which is why it was used in neutron detectors in preference to Boron-11, for example, Boron Trifluoride proportional counters.
n + B-10 → He-4 + Li-7 (2.79 MeV) with 6% probabilty
or
n + B-10 → He-4 + Li-7 (2.31MeV) + γ (0.48MeV) with 94% probability
Potentially the energy of 0.48 MeV gamma ray is directly convertible but using the Brayton cycle might be simpler.