Target/blanket design for LANL's accelerator transmutation of waste
M.W. Cappiello, John R. Ireland, William J. Rider
Abstract
M.W. Cappiello, John R. Ireland, William J. Rider
Abstract
The Los Alamos accelerator transmutation concept is directed at the problems associated with high-level wastes stored at several US Department of Energy sites. A more advanced long-term effort is investigating the potential of an accelerator-driven system to produce fission energy with a minimal nuclear waste stream. Both concepts employ a high-energy (1,600-MeV), high-current (25- to 60-mA) proton accelerator as the driver. The protons are directed onto a spallation target to produce neutrons, which are then moderated in the surrounding blanket. Because of the intense flux of neutrons generated, low-cross-section fission products such as {sup 99}Tc are easily transmuted, and higher actinide waste such as {sup 237}Np can be transmuted with a simple two-step capture/fission process. Also, very dilute mixtures are used, reducing the potential for criticality and power excursions. A layout for the target/blanket design is depicted. The most serious design challenges are associated with the flowing Pb-Bi target. Research is required to verify the thermal-hydraulic design and determine compatible container materials that can withstand the neutron environment.
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The Los Alamos accelerator transmutation concept is directed at the problems associated with high-level wastes stored at several US Department of Energy sites. A more advanced long-term effort is investigating the potential of an accelerator-driven system to produce fission energy with a minimal nuclear waste stream. Both concepts employ a high-energy (1,600-MeV), high-current (25- to 60-mA) proton accelerator as the driver. The protons are directed onto a spallation target to produce neutrons, which are then moderated in the surrounding blanket. Because of the intense flux of neutrons generated, low-cross-section fission products such as {sup 99}Tc are easily transmuted, and higher actinide waste such as {sup 237}Np can be transmuted with a simple two-step capture/fission process. Also, very dilute mixtures are used, reducing the potential for criticality and power excursions. A layout for the target/blanket design is depicted. The most serious design challenges are associated with the flowing Pb-Bi target. Research is required to verify the thermal-hydraulic design and determine compatible container materials that can withstand the neutron environment.
Key concepts: Nuclear transmutation, Blanket, Spallation, Nuclear engineering, Radioactive waste, Criticality, Nuclear physics, Neutron