Extraction process

1. A process for extracting Cs-137 from i) an acidic solution obtained by dissolving an irradiated solid target comprising uranium, ii) an acidic solution comprising uranium which has previously been irradiated in a nuclear reactor, or iii) an acidic solution comprising uranium which has been used as reactor fuel in a homogeneous reactor, the process comprising

(a) harvesting Mo-99 from the solution i), ii) or iii) prior to extracting Cs-137,

(b) contacting the acidic solution from step (a) with an adsorbent comprising ammonium molybdophosphate (AMP) to extract Cs-137, and

(c) when the solution is solution ii) or solution iii), returning the depleted Cs-137 solution from step (b) to the nuclear reactor or the homogenous reactor;

wherein harvesting Mo-99 from the acidic solution prior to step (b) prevents the Mo component present in the AMP from leaching into and contaminating the Mo-99.

2. A process according to claim 1 , wherein the AMP is combined with an organic or inorganic polymeric support.

3. A process according to claim 2 , wherein the AMP combined with an inorganic polymeric support is AMP that is synthesised within hollow aluminosilicate microspheres (AMP-C).

4. A process according to claim 1 , wherein Mo-99 is harvested from solution ii) or iii) in step (a), and the process further comprises a step of removing Mo, leached from the AMP, from the Cs-137-depleted solution prior to its return to be irradiated in the nuclear reactor, or prior to its return to the homogeneous reactor.

5. A process according to claim 4 , wherein the step of removing Mo, leached from the AMP, from the Cs-137-depleted solution comprises contacting said Cs-137-depleted solution with a zirconium-containing sorbent.

6. The process of claim 5 , wherein the zirconium-containing sorbent is a zirconium/titania-based sorbent.

7. An apparatus for carrying out the process of claim 1 , the apparatus comprising a vessel containing an adsorbent for the extraction of Mo-99, a source of the uranium containing acidic solution of claim 1 arranged in fluid communication with the vessel containing an adsorbent for the extraction of Mo-99, and a vessel containing an adsorbent comprising ammonium molybdophosphate (AMP) and arranged in downstream fluid communication with the vessel containing the adsorbent for extraction of Mo-99.

8. An apparatus according to claim 7 , further comprising a nuclear reactor for the production of Mo-99, wherein the nuclear reactor has a valve at its outlet, the vessel containing an adsorbent for the extraction of Mo-99 is arranged, and the vessel containing an adsorbent comprising AMP is arranged in downstream fluid communication with the valve and in downstream fluid communication with the vessel containing an adsorbent for the extraction of Mo-99.

9. An apparatus according to claim 7 , further comprising a homogeneous reactor, which uses a solution comprising uranium as reactor fuel for the production of Mo-99, wherein the homogeneous reactor has a valve at its outlet, the vessel containing an adsorbent for the extraction of Mo-99 is arranged, and the vessel containing an adsorbent comprising AMP is arranged in downstream fluid communication with the valve and in downstream fluid communication with the vessel containing an adsorbent for the extraction of Mo-99.

10. An apparatus according to claim 7 , the apparatus further comprising a vessel containing an adsorbent for removing Mo, leached from the AMP, in downstream fluid communication with the vessel containing an adsorbent comprising AMP.