High-abundance Pu-238 produced by nuclear transmutation of liquid MA fuel in reactor
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The feasibility of mass producing high-abundance 238Pu using liquid fuel containing minor actinides (MA) in a reactor is discussed. A chemically stable liquid solution or molten salt with MA dissolved, is evenly distributed in the inner or outer region of the reactor core to ensure that the MA materials receive sufficient neutron irradiation and achieve a high transmutation rate. The transmutation products of 241Am or 237Np are mainly 238Pu and fission products. After being burned, the liquid fuel is extracted from the reactor and separated in a reprocessing plant to obtain high-abundance 238Pu material. To maximize the abundance of 238Pu in reaction products, a thorium-based molten salt fast reactor was adopted. Its inner and outer regions of core are loaded with molten salts LiF + ThF4+XF4 and LiF + ThF4, where X is 233U or 235U. Fluoride salts of 241Am, 237Np, or TRU-MAs (a mixture primarily composed of 241Am and 237Np) are added to one of these molten salts. Depending on the different driving fuels and MA targets, the annual output of 238Pu ranges from 6.9 to 130.2 kg, with abundances varying from 67.7 % to 99.4 %. The annual transmutation rates for single nuclide 241Am or 237Np, can reach up to 21.4 % or 20.0 %.
Abstract
The feasibility of mass producing high-abundance 238Pu using liquid fuel containing minor actinides (MA) in a reactor is discussed. A chemically stable liquid solution or molten salt with MA dissolved, is evenly distributed in the inner or outer region of the reactor core to ensure that the MA materials receive sufficient neutron irradiation and achieve a high transmutation rate. The transmutation products of 241Am or 237Np are mainly 238Pu and fission products. After being burned, the liquid fuel is extracted from the reactor and separated in a reprocessing plant to obtain high-abundance 238Pu material. To maximize the abundance of 238Pu in reaction products, a thorium-based molten salt fast reactor was adopted. Its inner and outer regions of core are loaded with molten salts LiF + ThF4+XF4 and LiF + ThF4, where X is 233U or 235U. Fluoride salts of 241Am, 237Np, or TRU-MAs (a mixture primarily composed of 241Am and 237Np) are added to one of these molten salts. Depending on the different driving fuels and MA targets, the annual output of 238Pu ranges from 6.9 to 130.2 kg, with abundances varying from 67.7 % to 99.4 %. The annual transmutation rates for single nuclide 241Am or 237Np, can reach up to 21.4 % or 20.0 %.