A new approach to determine 147Pm in irradiated fuel solutions.

摘要: Abstract Developments carried out in the Laboratory of Isotopic, Nuclear and Elementary Analyses order to quantify 147 Pm spent nuclear fuels analyzed at CEA within framework Burn Up Credit research program for neutronic code validation are presented here. This determination is essential safety-criticality studies. The quantity nature radionuclides irradiated fuel solutions force us separate elements interest before measuring their isotopic content by mass spectrometry. main objective this study modify separation protocol used our laboratory recover measure same time as other lanthanides actinides determined A very complete on synthetic solution (containing or not Pm) was undertaken determine yield various stages obtaining isolated fraction from whole present solutions. With lack natural tracer carry measurement with isotope dilution technique, great number isotopes fuel, originality work rests use another lanthanide define output separation. yields were measured conclusion each stage two others show that one them could be a correct yield. total (at separation) ICP-MS liquid scintillation. last made it possible validate Sm (natural) since outputs scintillation (starting radioactive decrease source having been make solution) equivalent. It first such performed ICP-MS. finally taken UOx MOx using 153 Eu like results obtained good agreement those calculation code.