Studies on the Development of a Two Stage SLM System for the Separation of Carrier‐free⁹⁰Y using KSM‐17 and CMPO as Carriers

Interfacial Complexation Reactions of Sr2+ with Octyl(phenyl)‐N,N‐diisobutylcarbamoylmethylphosphine Oxide for Understanding Its Extraction in Reprocessing Spent Nuclear Fuels

“…Two stoichiometries at the w j DCE interface were discovered, that is, [Sr-A C H T U N G T R E N N U N G (CMPO) 2 , respectively. Only one stoichiometry was observed at the w j RTIL interface: [Sr-A C H T U N G T R E N N U N G (CMPO) 3 ] 2 + with b equal to 1. 5 10 34 .…”

“…MS/ MS involves the linear combination of quadrupole mass analyzers; the mass spectrum is first scanned, the ion stream undergoes collision with an inert gas, and finally the fragments are analyzed with the second MS. According to tandem MS spectra, [SrA C H T U N G T R E N N U N G (CMPO) 3 ] 2 + easily lost one CMPO during collision-induced dissociation with very low collision energy, while the other two CMPO complexes, including [Sr- The experimental and calculated mass peak profiles are in excellent agreement and are characteristic of the stable strontium isotopes 86 Sr, 87 Sr, and 88 Sr which have an abundance of 9.86, 7.00, and 82.58 %, [21] respectively. Since only one strontium atom is found each complex, these isotopic ratios result in two short peaks, preceding a large main peak; these were faithfully reproduced in the calculated and experimental profiles.…”

“…[3,5] Several nuclear fuel reprocessing [5,6] technologies are currently being implemented around the world on an industrial and laboratory scale, including the transuranic extraction (TRUEX) process. [3,7] This method makes use of octyl-A C H T U N G T R E N N U N G (phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) as a chelating agent in a biphasic solvent extraction procedure between water and an organic solvent, typically n-dodecane; [3,7] this process can be summarized by Equation (1); however, the stoichiometry for this reaction is not clear.…”

“…[3,5] Several nuclear fuel reprocessing [5,6] technologies are currently being implemented around the world on an industrial and laboratory scale, including the transuranic extraction (TRUEX) process. [3,7] This method makes use of octyl-A C H T U N G T R E N N U N G (phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) as a chelating agent in a biphasic solvent extraction procedure between water and an organic solvent, typically n-dodecane; [3,7] this process can be summarized by Equation (1); however, the stoichiometry for this reaction is not clear. Prompted by the pioneering work of Dai et al, [8] recent research towards improving the TRUEX process [6, 7b,c,i] and other metal-extraction techniques [9] has focused on replacing the organic solvent with a room-temperature ionic liquid (RTIL); RTILs are organic salts with a melting point below 100 8C.…”

“…[1c] The 90 Y isotope can be acquired through neutron-irradiation of yttrium metal oxide [3] or through the isotopic decay of 90 Sr. [4] Owing to its short halflife and the expense of transporting radioactive material, an in house 90 Y generator is deemed preferable with several designs having been proposed to use 90 Sr as a perpetual feed stock.…”