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Purex process



Purex – Industrialised spent fuel processing

Pulsed columns
At the UP3 plant in La Hague, the separation process takes place in pulsed columns in the T2 high-level waste extraction shop. These pulsed columns are being phased out and replaced by more compact centrifugal extractors that purify the plutonium.
AREVA / JEZEQUEL (SIDNEY)

Fuel is processed at the LaHague facility using a hydrometallurgical process known as Purex (Plutonium Uranium Refining by Extraction). This process was originally developed in the USA during the 1940's as a means of recovering plutonium from reactors designed to produce military-grade plutonium with a high fissile isotope 239 content.

Reprocessing is considered to be a proliferating technology, even though plutonium produced in civilian reactors is unsuitable for use in atomic bomb-making. This is because the technique may also be applied to irradiated fuel from specialised reactors that produce military-grade plutonium. Consequently, reprocessing activities are closely monitored, and IAEA and EURATOM cameras constantly track operations at La Hague.

The aim of this chemical extraction process is to separate irradiated fuel's two main components - uranium and plutonium - from a residue of fission products and minor actinides considered to be waste.

Extraction phase
The uranium and plutonium (shown in green) are initially mixed with other radioactive elements (shown in dark blue) in strongly acidic water. A kerosene-based oily mixture (light yellow) is added. This mixture contains a special molecule, TriButylPhosphate or TBP (bright yellow), which is only effective in the presence of strongly acidic water. The mixture is agitated (C) and the TBP traps the uranium and plutonium in the kerosene. The acidic water naturally separates from the kerosene when the mixture is allowed to rest. The uranium and plutonium remain trapped in the kerosene. The kerosene containing the uranium and plutonium are then drawn off, leaving behind the acid bath containing the remaining elements.
IN2P3 (I. Billard)

During shearing operations, irradiated fuel pellets fall into a bath of boiling nitric acid, where they dissolve at a ratio of around 40 kg in approximately 600 litres of acid solution. The resulting solution contains multiple chemical elements, including radioactive and non-radioactive fission products, uranium and plutonium.

A kerosene-based oily mixture containing a special-purpose molecule - TriButylPhosphate or TBP – is then added. TBP, which acts like an enzyme absorbing uranium and plutonium atoms, is only effective in the presence of strongly acidic water. The mixture is agitated - as though making French dressing - and the TBP selectively traps the uranium and plutonium in the kerosene.

Back-extraction phase
The purpose of the second stage of the process is to recover the uranium and plutonium from the kerosene. The kerosene is brought into contact with pure water and the resulting mixture agitated as before. TBP is no longer effective, as the water is not sufficiently acidic. As a result, it releases the uranium and plutonium, which enter the pure water. The water and kerosene naturally separate when the mixture is allowed to rest. All that remains is to transfer the kerosene. This results in water containing just the uranium and plutonium, and the kerosene-TBP mixture, which can be reused (almost indefinitely) in subsequent extraction operations.
IN2P3 (I. Billard)

Ultimately, the kerosene solution contains the majority of the plutonium and uranium. The fission products and other transuranium elements remain in the aqueous solution.

The plutonium and uranium are then separated from each other by reducing the plutonium. Several cycles are necessary in order to achieve maximum purification. The uranium, in the form of uranyl nitrate, is purified in several stages by liquid-liquid extraction, removing the fission products. The plutonium is also purified, by extraction, and then concentrated and precipitated as oxalate. The residual solution containing the fission products and actinides is calcined to enable it to be vitrified.

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