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NEUTRON SPECTRA IN FUSION-FISSION HYBRID REACTOR (FFHR) FOR SPENT FUEL TREATMENT
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Executive Summary
This presentation introduces a concentric model for a Fusion-Fission Hybrid Reactor (FFHR) tailored for spent nuclear fuel treatment. It details geometric and material specifications for dual fuel shells, lithium silicate breeder blankets, and tungsten reflectors, along with normalized neutron flux spectra and 14 MeV neutron shielding analyses.
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ST_CODE: EACTOR
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DOC-GERVASON
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Title Slide
NEUTRON SPECTRA IN FUSION-FISSION HYBRID REACTOR (FFHR) FOR SPENT FUEL TREATMENT
Jorge GARCIA GALLARDO, Juana GERVASONI, Fabricio RUIZ, Nicolas GIMENEZ
Centro Atómico Bariloche, Argentina
Comisión Nacional de Energía Atómica (CNEA).
Consejo Nacional de Investigaciones Científicas y Técnicas (CONICET).
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This presentation introduces a concentric model for a Fusion-Fission Hybrid Reactor (FFHR) tailored for spent nuclear fuel treatment. It details geometric and material specifications for dual fuel shells, lithium silicate breeder blankets, and tungsten reflectors, along with normalized neutron flux ...