Method for processing spent nuclear reactor fuel
AssigneeElectric Power Research Institute, Inc.
InventorsMilton Levenson, Edwin L. Zebroski
Life of this patent
Estimating the term…
Abstract
A method and apparatus for processing spent nuclear reactor fuel wherein plutonium is continuously contaminated with radioactive fission products and diluted with uranium. Plutonium of sufficient purity to fabricate nuclear weapons cannot be produced by the process or in the disclosed reprocessing plant. Diversion of plutonium is prevented by radiation hazards and ease of detection.
Claims13
A method for processing spent nuclear reactor fuel, comprising the steps of:
- (a) dissolving spent nuclear reactor fuel into a spent fuel stream, said stream containing plutonium, uranium, and short-lived and long-lived radioactive fission products in an aqueous solution;
- (b) extracting from the spent fuel stream plutonium and uranium together with a substantial quantity of long-lived fission products and discharging them together in an organic product stream;
- and
- (c) partitioning the product stream into a uranium product stream and a fuel fabrication stream containing plutonium, uranium and long-lived fission products in an aqueous solution, the quantity of uranium in the fuel fabrication stream being equal to or greater than the quantity of plutonium therein.
A method for processing spent nuclear reactor fuel, comprising the steps of:
- (a) dissolving spent nuclear reactor fuel into a spent fuel stream, said stream containing plutonium, uranium and short and long-lived radioactive fission products in an aqueous solution;
- (b) extracting from the spent fuel stream plutonium and uranium together with a substantial quantity of the long-lived fission products and discharging them together in an organic product stream;
- (c) partitioning the product stream into a uranium product stream and a fuel fabricating stream containing plutonium, uranium, and long-lived fission products in an aqueous solution;
- and
- (d) fluoride purifying the uranium product stream for producing substantially pure uranium, any plutonium remaining after fluoride purification of the uranium being contaminated with long-lived fission products.
A method for processing spent nuclear reactor fuel, comprising the steps of:
- (a) dissolving spent nuclear reactor fuel into a spent fuel stream, said stream containing plutonium, uranium, and short and long-lived radioactive fission products in an aqueous solution;
- (b) extracting from the spent fuel stream plutonium and uranium together with a substantial quantity of the long-lived fission products and discharging them together in an organic product stream;
- (c) partitioning the product stream into a uranium product stream and a fuel fabrication stream containing plutonium, uranium, and some long-lived fission products in an aqueous solution;
- and
- (d) fabricating a mixed oxide nuclear reactor fuel from the fuel fabrication stream, said mixed oxide fuel having sufficient penetrating radiation from residual radioactivity to be readily detectable if diversion is attempted.
A method for processing spent nuclear reactor fuel, comprising the steps of:
- (a) directing an extractant stream (HAX) and a high activity feed stream (HAF) into a countercurrent flow liquid-liquid contactor (HA), said feed stream (HAF) containing plutonium, uranium, and radioactive fission products in an aqueous solution;
- (b) discharging a high activity waste stream (HAW) from the liquid-liquid contactor;
- (c) discharging a high activity organic product stream (HAP) from the liquid-liquid contactor;
- and
- (d) discharging in the high activity product stream (HAP) long-lived radioactive fission products having sufficient radioactivity that the high activity product stream (HAP) has a concentration of between 10 and 80 curies per liter after a 100 day cool-down period together with plutonium having a concentration of less than 0.06 molar.
A method for processing spent nuclear reactor fuel, comprising the steps of:
- (a) directing an extractant stream (HAX) and a high activity feed stream (HAF) into a countercurrent flow liquid-liquid contactor (HA), said feed stream (HAF) containing plutonium, uranium, and radioactive fission products in an aqueous solution;
- (b) discharging a high activity waste stream (HAW) from the HA contactor;
- (c) discharging a high activity organic product stream (HAP) from the HA exchanger into a second countercurrent liquid-liquid contactor (HB);
- (d) directing an extractant stream (HBX) into the HB exchanger;
- (e) discharging a uranium product stream (HBU) and a plutonium product stream (HBP) from the HB exchanger;
- and
- (f) discharging in the plutonium product stream (HBP) long-lived radioactive fission products having sufficient radioactivity that the plutonium product stream (HBP) has a concentration of between 5 and 50 curies per liter after a 100 day cool-down period together with plutonium having a concentration of less than 0.06 molar.
Dependencies are inferred from the claim text.