Communication Dans Un Congrès Année : 2024

Separation and quantification method for Pd-107 in radioactive waste

Résumé

In spent nuclear fuel, palladium 107 (Pd-107) is one of the longest-lived fission products (FP) resulting from the fission of uranium and plutonium. After use of the UOX fuel in a PWR reactor, 4% of its mass composition is FP, among which 0.66% is Pd-107. This pure beta emitter decays to a stable Ag-107 with a half-life of 6.5 x 106 years. In 2022, the French government has announced new nuclear power plants projects in parallel with the increase in decommissioning and dismantling activities (D&D) of nuclear sites. In order to ensure a correct disposal of nuclear waste and safe longterm storage in the required facilities, the Pd-107 concentration must be precisely quantified in a variety of materials.
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Dates et versions

cea-04715498 , version 1 (30-09-2024)

Identifiants

  • HAL Id : cea-04715498 , version 1

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Marina Faure, Celine Gautier, Pascal Fichet, Christèle Colin, Elodie Laporte, et al.. Separation and quantification method for Pd-107 in radioactive waste. 10th International Conference on Nuclear and Radiochemistry – NRC10, Aug 2024, brighton, United Kingdom. ⟨cea-04715498⟩
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