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PUREX Process

1950
  • Herbert H. Anderson
  • Larned B. Asprey
Nuclear reprocessing facility utilizing the PUREX process for uranium and plutonium extraction.

(generated image for illustration only)

PUREX, an acronym for Plutonium and Uranium Recovery by Extraction, is the primary industrial method for reprocessing spent nuclear fuel. It employs liquid-liquid extraction (LLE) to separate uranium and plutonium from highly radioactive fission products. The process uses a 30% solution of tributyl phosphate (TBP) in a hydrocarbon diluent to selectively extract U(VI) and Pu(IV) from a nitric acid feed.

The PUREX process, developed in the late 1940s as part of the US nuclear program, became the global standard for nuclear reprocessing. Its success lies in the high selectivity of the extractant, tributyl phosphate (TBP), for uranium and plutonium in specific oxidation states. The process begins by dissolving spent fuel rods in hot nitric acid. In the first extraction step, the aqueous nitric acid solution containing uranium, plutonium, and fission products is contacted with the TBP/kerosene solvent. TBP forms stable complexes with hexavalent uranium (as \(UO_2(NO_3)_2(TBP)_2\)) and tetravalent plutonium (as \(Pu(NO_3)_4(TBP)_2\)), extracting them into the organic phase while most fission products, typically in the +1, +2, or +3 oxidation states, remain in the aqueous raffinate.

Separation of uranium and plutonium is then achieved in a subsequent step. A reducing agent, such as ferrous sulfamate or hydroxylamine nitrate, is added to selectively reduce plutonium from Pu(IV) to the inextractable Pu(III) state. This allows plutonium to be ‘stripped’ back into a fresh aqueous phase, while uranium remains in the organic phase. Finally, the uranium is stripped from the organic solvent using a dilute nitric acid solution. The process is highly efficient but generates significant volumes of liquid radioactive waste and carries proliferation concerns due to the separation of pure plutonium. Advanced variants of the PUREX process are being developed to co-extract plutonium with other actinides to create a more proliferation-resistant product.

UNESCO Nomenclature: 2209
– Nuclear and high-energy physics

Type

Chemical Process

Disruption

Substancial

Usage

Widespread Use

Precursors

  • discovery of nuclear fission and transuranic elements
  • the Manhattan project’s need for plutonium separation (e.g., the earlier bismuth phosphate process)
  • development of tributyl phosphate (TBP) as a plasticizer and solvent
  • advances in remote handling technology for highly radioactive materials
  • development of mixer-settler and pulsed column contactors

Applications

  • recovering fissile materials (uranium-235, plutonium-239) for reuse in nuclear reactors
  • producing separated plutonium for nuclear weapons
  • manufacturing mixed oxide (MOX) fuel
  • reducing the volume and long-term radiotoxicity of high-level nuclear waste
  • isolating specific isotopes for medical or industrial use

Patents:

  • US2924506A

Potential Innovations Ideas

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Related to: PUREX, nuclear reprocessing, spent nuclear fuel, plutonium, uranium, tributyl phosphate, TBP, solvent extraction, nuclear chemistry, radioactive waste.

Historical Context

PUREX Process

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(if date is unknown or not relevant, e.g. "fluid mechanics", a rounded estimation of its notable emergence is provided)

Related Invention, Innovation & Technical Principles

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