Separation and purification of 90Sr from PUREX HLLW using N,N,N′,N′-tetra(2-ethylhexyl) diglycolamide

Dhami, P.S.; Janardanan, C.; Jagasia, Poonam; Pahan, S.; Tripathi, S. C.; Gandhi, P.M.; Wattal, P.K.

doi:10.1007/s10967-012-2302-0

Cited by 12 publications

(4 citation statements)

References 17 publications

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“…This aqueous phase generated from stripping also contains minor actinides/lanthanides and traces of 137 Cs activity. 18 Purification of 90 Sr: In the first step, trace impurities of 137 Cs was removed using granulated ammonium phosphomolybdate column. In the second step, a emitters, namely minor actinides, lanthanides, and traces of U and Pu, were removed by extraction chromatography using Truex solvent {0.2 M octyl(phenyl)-N,N-diisobutylcarbamoylmethyl phosphine oxide (CMPO, synthesized in-house) and 1.2 M TBP in n-dodecane}.…”

Section: Methodsmentioning

confidence: 99%

“…These steps were carried out to reduce the gross a levels of clinical-grade 90 Y-Acetate from 10 -8 Ci/1.0 Ci of 90 Y to <10 -9 Ci/1.0 Ci of 90 Y. 18 Separation of clinical-grade 90 Y in 90 Y-Acetate form using the two-stage SLM generator A two-stage SLM-based generator system developed in-house and used for the separation of carrier-free 90 Y based on the solvent extraction properties of two ligands, namely 2-ethylhexyl 2-ethylhexyl phosphonic acid (KSM-17; BARC) and octyl phenyl-N,N-diisobutylcarbamoyl methyl phosphine oxide (CMPO; BARC) under optimum conditions. The system was operated in sequential modes with each borosilicate glass cell having 5 mL capacity (BARC).…”

Section: Additional Purification Of 90 Srmentioning

confidence: 99%

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On the Separation of Yttrium-90 from High-Level Liquid Waste: Purification to Clinical-Grade Radiochemical Precursor, Clinical Translation in Formulation of⁹⁰Y-DOTATATE Patient Dose

Mitra¹,

Gaikwad

et al. 2021

Cancer Biotherapy and Radiopharmaceuticals

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Introduction: The quality control parameters of in-house-produced 90 Y-Acetate from high-level liquid waste (HLLW) using supported liquid membrane (SLM) technology were validated and compared with the pharmacopeia standard. The radiolabeling of DOTATATE yielding 90 Y-DOTATATE in acceptable radiochemical purity (RCP), with expected pharmacological behavior in in vivo models, establish the quality of 90 Y-Acetate. Clinical translation of 90 Y-Acetate in formulation of 90 Y-DOTATATE adds support toward its use as clinicalgrade radiochemical. Methods: Quality control parameters of 90 Y-Acetate, namely radionuclide purity (RNP), were evaluated using bspectrometry, c-spectroscopy, and liquid scintillation counting. RCP and metallic impurities were established using high-performance liquid chromatography and inductively coupled plasma optical emission spectrometry, respectively. The suitability of 90 Y-Acetate as an active pharmaceutical ingredient radiochemical was ascertained by radiolabeling with DOTATATE. In vivo biodistribution of 90 Y-DOTATATE was carried out in nude mice bearing AR42J xenografted tumor. Clinical efficacy of 90 Y-DOTATATE was established after using in patients with large-volume neuroendocrine tumors (NET). Bremsstrahlung imaging was carried out in dualhead gamma camera with a wide energy window setting (100-250 keV). Results: In-house-produced 90 Y-Acetate was clear, colorless, and radioactive concentration (RAC) in the range of 40-50 mCi/mL. RCP was >98%. 90 Sr content was <0.85 lCi/Ci of 90 Y. Gross k content was <0.8 nCi/Ci of 90 Y and no c peak was observed. Fe 3+ , Cu 2+ , Zn 2+ , Cd 2+ , and Pb 2+ contents were <1.7 lg/Ci. The radiolabeling yield (RLY) of 90 Y-DOTATATE was >94%, RCP was >98%. The in vitro stability of 90 Y-DOTATATE was up to 72 h postradiolabeling, upon storage at -20°C. Post-therapy (24 h) Bremsstrahlung image of patients with large NET exhibit complete localization of 90 Y-DOTATATE in tumor region. Conclusions: This study demonstrates that the in-house-produced 90 Y-Acetate from HLLW can be used for the formulation of various therapeutic 90 Y-based radiopharmaceuticals. Since 90 Y is an imported radiochemical precursor available at a high cost in India, this study which demonstrates the suitability of indigenously sourced 90 Y, ideally exemplifies the recovery of ''wealth from waste.'' The Clinical Trial Registration number: (P17/FEB/2019).

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Section: Methodsmentioning

confidence: 99%

Section: Additional Purification Of 90 Srmentioning

confidence: 99%

On the Separation of Yttrium-90 from High-Level Liquid Waste: Purification to Clinical-Grade Radiochemical Precursor, Clinical Translation in Formulation of⁹⁰Y-DOTATATE Patient Dose

Mitra¹,

Gaikwad

et al. 2021

Cancer Biotherapy and Radiopharmaceuticals

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“…3 shows a correlation between the D Sr values and the initial Sr 2+ concentration. The initial Sr 2+ concentration was investigated in the range of 0.4-2 mol•L -1 , considering the average concentration of 90 Sr 2+ in HLLW 5,14 . As indicated, D Sr values were barely affected by the initial Sr 2+ concentration in the aqueous medium within a certain range.…”

Section: Effect Of the Dch18c6 And Initial Sr 2+ Concentrationmentioning

confidence: 99%

The extraction of SR2+ with dicyclohexano-18-crown-6 in conventional organic solvent and ionic liquid diluents

et al. 2020

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90 Sr (t 1/2 = 28.8 a), one of the most significant fission products in high-level radioactive liquid waste (HLLW), contributes to a large part of the heat load and radiation. Removal of 90 Sr from the HLLW is beneficial for the final treatment of nuclear waste. In this paper, the extraction of Sr 2+ was carried out using dicyclohexano-18-crown-6 (DCH18C6) in a variety of diluents including conventional organic solvents and novel ionic liquid solvents. The effect of several factors, such as nitric acid concentration, crown ether concentration and initial strontium concentration on the extraction of Sr 2+ have been studied comprehensively. The higher distribution ratio and the stripping efficiency of Sr 2+ were obtained with the binary diluents consisted of n-octanol and acetylene tetrachloride, which were compared with that using pure n-octanol as diluent. As for the C n mimNTf 2 (n = 2, 4, 6) ionic liquid solvent systems, the distribution ratio of Sr 2+ was much higher in the nitric acid medium with low concentration than in the traditional solvent systems. The results showed that D C2mimNTf2 > D C4mimNTf2 > D C6mimNTf2 , which indicated that shorter carbon chain benefits the extraction of Sr 2+ .

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“…The high level waste, in general, has an acidity in the range of 3-4 M HNO 3 . However, in certain cases, like the research reactor HLW, the acidity is neutralized by NaOH to about 2 M [25]. Therefore, it was required to understand the acid concentration dependence of Am 3+ extraction using the extractants L-I-L-III.…”

Section: Effect Of the Feed Aciditymentioning

confidence: 99%

A comparative evaluation of the liquid–liquid extraction and pertraction efficiency of a both-side diglycolamide-functionalized calix[4]arene with analogous upper and lower-rim calixarenes for actinide separations

Mohapatra

Rout

Iqbal³

et al. 2013

Journal of Membrane Science

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Separation and purification of 90Sr from PUREX HLLW using N,N,N′,N′-tetra(2-ethylhexyl) diglycolamide

Cited by 12 publications

References 17 publications

On the Separation of Yttrium-90 from High-Level Liquid Waste: Purification to Clinical-Grade Radiochemical Precursor, Clinical Translation in Formulation of⁹⁰Y-DOTATATE Patient Dose

On the Separation of Yttrium-90 from High-Level Liquid Waste: Purification to Clinical-Grade Radiochemical Precursor, Clinical Translation in Formulation of⁹⁰Y-DOTATATE Patient Dose

The extraction of SR2+ with dicyclohexano-18-crown-6 in conventional organic solvent and ionic liquid diluents

A comparative evaluation of the liquid–liquid extraction and pertraction efficiency of a both-side diglycolamide-functionalized calix[4]arene with analogous upper and lower-rim calixarenes for actinide separations

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Separation and purification of 90Sr from PUREX HLLW using N,N,N′,N′-tetra(2-ethylhexyl) diglycolamide

Cited by 12 publications

References 17 publications

On the Separation of Yttrium-90 from High-Level Liquid Waste: Purification to Clinical-Grade Radiochemical Precursor, Clinical Translation in Formulation of90Y-DOTATATE Patient Dose

On the Separation of Yttrium-90 from High-Level Liquid Waste: Purification to Clinical-Grade Radiochemical Precursor, Clinical Translation in Formulation of90Y-DOTATATE Patient Dose

The extraction of SR2+ with dicyclohexano-18-crown-6 in conventional organic solvent and ionic liquid diluents

A comparative evaluation of the liquid–liquid extraction and pertraction efficiency of a both-side diglycolamide-functionalized calix[4]arene with analogous upper and lower-rim calixarenes for actinide separations

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On the Separation of Yttrium-90 from High-Level Liquid Waste: Purification to Clinical-Grade Radiochemical Precursor, Clinical Translation in Formulation of⁹⁰Y-DOTATATE Patient Dose

On the Separation of Yttrium-90 from High-Level Liquid Waste: Purification to Clinical-Grade Radiochemical Precursor, Clinical Translation in Formulation of⁹⁰Y-DOTATATE Patient Dose