Reactor and process for production of novel nuclear fuel

A method of production of a novel nuclear fuel comprising the steps:

• (A) initially charging a light-water nuclear reactor with fertile thorium fuel elements and fissile uranium core elements in predetermined arrangements;
• wherein the thorium is segregated from the uranium and wherein some of said thorium fuel elements are extra-core fuel elements;
• (B) irradiating said thorium fuel elements and said fissile uranium core elements at an average driver fuel rod power output of approximately 7 kw thermal per foot;
• (C) continuing said irradiation of said extra-core thorium fuel elements for a period of two to three years at a power density of 50 to 100 kw thermal per liter;
• (D) thereafter removing and replacing preselected ones of said thorium fuel elements and said fissile uranium fuel elements;
• (E) further continuing said irradiation of the nonremoved thorium fuel elements until the U-232 content in the U-233 averages 300 to 500 parts per million;
• (F) removing and co-dissolving only said thorium fuel elements together with depleted uranium tailings from U-235 isotopic enrichment process in the proportion of 2 to 3% in totaluranium;
• (G) separating the uranium isotopes from those of other elements present;
• thereby producing a fissile fuel comprising U-233 with a U-232 content of less than 10 parts per million in total uranium.

A method of production of a novel nuclear fuel comprising the steps:

• (A) initially charging a light-water nuclear reactor with fertile thorium fuel elements and fissile uranium core elements in predetermined arrangements;
• wherein the thorium is segregated from the uranium and wherein some of said thorium fuel elements are extra-core fuel elements;
• (B) irradiating said thorium fuel elements and said fissile uranium core elements at an average driver fuel rod power output of approximately 7 kw thermal per foot;
• (C) continuing said irradiation of said extra-core thorium fuel elements for a period of two to three years at a power density of 50 to 100 kw thermal per liter;
• (D) thereafter removing and replacing preselected ones of said thorium fuel elements and said fissile uranium fuel elements;
• (E) further continuing said irradiation of the non-removed thorium fuel elements until the U-232 content in the U-233 averages 300 to 500 parts per million;
• (F) removing and co-dissolving only said thorium fuel elements together with depleted uranium from prior reactor irradiation in the proportion of two to three percent U-233 in total uranium;
• (G) separating the uranium isotopes from those of other elements present;
• thereby producing a fissile fuel comprising U-233 with a U-232 content of less than 10 parts per million in total uranium.