A Subcritical, Helium-Cooled Fast Reactor for the Transmutation of Spent Nuclear Fuel

W. M. StaceyGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

Z. AbbasiGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

C. J. BoydGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

A. H. BridgesGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

E. A. BurgettGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

M. W. CymborGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

S. W. FowlerGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

A. T. JonesGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

R. S. KelmGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

B. J. KernGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

D. B. LassiterGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

J. A. MaddoxGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

W. B. MurphyGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

H. ParkGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

J. M. PoundersGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

J. R. PrestonGeorgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425

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Abstract

A design concept and supporting analysis are presented for a He-cooled fast reactor for the transmutation of spent nuclear fuel. Coated transuranic (TRU) fuel particles in a SiC matrix are used. The reactor operates subcritical (k ≤ 0.95), with a tokamak D-T fusion neutron source, to achieve >90% TRU burnup in repeated five-batch fuel cycles, fissions 1.1 tonnes/full-power year, and produces 700 MW(electric) net electrical power. The reactor design is based on nuclear, fuels, materials, and separations technologies being developed in the Generation-IV, Next Generation Nuclear Plant, and Advanced Fuel Cycle Initiative programs and similar international programs, and the fusion neutron source is based on the physics and technology supporting the ITER design.

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A Subcritical, Helium-Cooled Fast Reactor for the Transmutation of Spent Nuclear Fuel

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A Subcritical, Helium-Cooled Fast Reactor for the Transmutation of Spent Nuclear Fuel

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