Apart from the development of an adequate fusion-neutron generator, development needs for the hybrid reactor include (1) improved information on neutron cross sections at energies of 3 to 16 MeV, in nuclides of thorium, protactinium, uranium, neptunium, and plutonium, and on secondary gamma-ray spectra due to inelastic neutron scattering and (n, xn) events in these nuclides;(2) cross-section sensitivity analyses of breeding performance;(3) resolution of compatibility problems among potential fuels, claddings, and coolants;(4) more extensive data on coolant flow and heat transfer properties, for analyzing severe thermal hydraulics problems arising from sharp gradients in heat production;(5) quantitative information on the adverse effect of cyclic power operation on fuel-clad interaction and mechanical properties;(6) determination of radiation damage effects on candidate blanket materials.
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