Process for Treating Spent Nuclear Fuel,Rod pulling system and process for nuclear fuel assembly,Dry recycling technology for MOX fuel pellet waste,Breeding Nuclear Fuel Mixture Using Metallic Thorium

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4 results about "Nuclear fuel" patented technology

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Nuclear fuel is material used in nuclear power stations to produce heat to power turbines. Heat is created when nuclear fuel undergoes nuclear fission. Most nuclear fuels contain heavy fissile actinide elements that are capable of undergoing and sustaining nuclear fission. The three most relevant fissile isotopes are Uranium-233, Uranium-235 and Plutonium-239. When the unstable nuclei of these atoms are hit by a slow-moving neutron, they split, creating two daughter nuclei and two or three more neutrons. These neutrons then go on to split more nuclei. This creates a self-sustaining chain reaction that is controlled in a nuclear reactor, or uncontrolled in a nuclear weapon.

Process for Treating Spent Nuclear Fuel

InactiveUS20100301287A1Other chemical processesNuclear energy generationOrganic solventCarboxylic acid

Process for treating spent nuclear fuel (SNF) to make mixed metal oxides of UO₃and PuO₂to prevent nuclear proliferation. The process comprises the steps of (1) dissolving spent nuclear fuel in an acidic solution in the presence of an agent that reduces Pu⁺⁶to Pu⁺⁴and an agent that oxidizes Pu⁺³to Pu⁺⁴; (2) extracting U⁺⁶and Pu⁺⁴from acidic solution with an organic solvent comprising a ligand that binds U⁺⁶and Pu⁺⁴and which is soluble in the organic solvent; (3) jointly extracting U⁺⁶and Pu⁺⁴from the organic solvent with an acidic aqueous solution; and (4) precipitating a mixture of U⁺⁶and Pu⁺⁴by adding a carboxylic acid to the acidic aqueous solution. The U⁺⁶and Pu⁺⁴precipitate is then be calcined to form a mixed metal oxide of UO₃and PuO₂. Additional steps can result in the formation of a mixed metal oxide of UO₃, PuO₂and NpO₂as well as the removal and isolation of technecium from the SNF.

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Owner:CH2M HILL

Rod pulling system and process for nuclear fuel assembly

PendingCN107610797AHigh degree of automationQuality improvementNuclear energy generationReactors manufactureEngineeringAutomation

The invention relates to a rod pulling system and process for a nuclear fuel assembly. The system comprises a rod pulling and preassembling box platform, a skeleton assembling and clamping platform and a rod pulling host machine, wherein the skeleton assembling and clamping platform is arranged between the rod pulling and preassembling box platform and the rod pulling host machine. According to the device, a moving mechanism and a lifting mechanism are arranged on the rod pulling and preassembling box platform and the rod pulling host machine, thereby improving the automation degree in the whole technical process. According to the process, each cylinder is further controlled through a PLC program, thereby realizing the control on each pull rod, ensuring more flexible rod pulling, and improving the quality and efficiency of the process.

Rod pulling system and process for nuclear fuel assembly

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Owner:CMCU ENG

Dry recycling technology for MOX fuel pellet waste

ActiveCN106782736AHigh recovery rateShort recycling processRadioactive decontaminationLiquid wasteCombustion

The invention belongs to the field of nuclear fuel. In order to solve the problem that an MOX fuel pellet waste wet recycling technology has many defects, the invention provides a dry recycling technology for MOX fuel pellet waste. The technology comprises the following steps of 1, burning MOX fuel pellet waste; 2, crushing by using a crusher; 3, screening; 4, ball milling; and 5 recycling. According to the technology provided by the invention, powdering of the MOX fuel pellet waste is achieved by crushing-ball milling technologies, so that the technology is fundamentally different from a dry recycling technology for UO2 fuel pellet waste using an oxidized crushing technology. Practical application shows that the MOX fuel pellet waste wet recycling technology provided by the invention has the advantages of high recycling rate, short recycling technical process, high in speed, simple in equipment, low in cost, and being free from generating radioactive liquid waste, and can be recycled in an MOX combustion manufacturer; the recycled power has similar sintering performance with the common MOX raw material powder, and can be mixed with common raw materials for preparing MOX fuel pellets.

Owner:CHINA INSTITUTE OF ATOMIC ENERGY

Breeding Nuclear Fuel Mixture Using Metallic Thorium

InactiveUS20110299645A1Improve economyImprove thermal conductivityFuel elementsConversion outside reactor/acceleratorsNuclear plantNuclear power

Disclosed is a breeding nuclear fuel mixture including metallic thorium useable in a nuclear power plant, prepared by mixing uranium dioxide (UO2) or plutonium dioxide (PuO2) having ceramic properties with metallic thorium (Th), in order to enable thorium breeding by neutrons released during nuclear fission of U or Pu and conversion of the bred thorium into a novel nuclear fissile material, i.e., U-233, thereby ensuring continuous nuclear fission. The foregoing nuclear fuel mixture may be burned at a reactor core of a nuclear power plant through thorium breeding over a long period of time. Therefore, when the inventive breeding nuclear fuel mixture is employed in a nuclear power plant, utilization of the nuclear power plant may be increased while maximizing conservation of limited uranium resources.

Owner:KOREA ATOMIC ENERGY RES INST +1

4 results about "Nuclear fuel" patented technology

Process for Treating Spent Nuclear Fuel

Rod pulling system and process for nuclear fuel assembly

Dry recycling technology for MOX fuel pellet waste

Breeding Nuclear Fuel Mixture Using Metallic Thorium

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