Dynamic ion exchange chromatography for determination of number of fissions in thorium-uranium dioxide fuels

Knight, C. H.; Cassidy, R. M.; Recoskie, B. M.; Green, L. W.

doi:10.1021/ac00267a041

Cited by 140 publications

(52 citation statements)

References 9 publications

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“…Due to the fast separation and less amount of the sample handling in HPLC, it minimizes the exposure to highly radioactive samples and is, therefore, attractive for the separation of fission products. Cassidy et al studied the separation of lanthanides fission products using a dynamic ion exchange column from different fuel samples like UO 2 and (Th, U)O 2 fuels [17,18]. However, in presence of bulk of actinides, the individual separation of lanthanides was not reported.…”

Section: Introductionmentioning

confidence: 99%

Determination of Lanthanides, Thorium, Uranium and Plutonium in Irradiated (Th, Pu)O2 by Liquid Chromatography Using α-Hydroxyiso Butyric Acid (α-HIBA)

Kumar¹,

Jaison²,

Telmore³

et al. 2013

IJAMSC

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An HPLC method is presented for the separation and determination of lanthanides (Lns), thorium (Th), uranium (U) and plutonium (Pu) from irradiated (Th, Pu)O 2 . Individual separation of Lns, Th, U and Pu is a challenging task because of 1) lanthanides having similar physical and chemical properties, 2) presence of complex matrix like irradiated fuel and 3) the co-existence of multiple oxidation states of Pu. Different procedures were developed for separation of individual lanthanides and actinides. The individual lanthanides were separated on a dynamically modified reversed phase (RP) column using n-octane sulfonic acid as an ion interaction reagent and employing dual gradient (pH and concentration) of α-hydroxyisobutyric acid (HIBA). In order to improve the precision on the determination of Lns, terbium (Tb) was used as an internal standard. The method was validated employing simulated high level liquid waste. Concentrations of lanthanides viz. lanthanum (La) and neodymium (Nd) in the dissolver solution were determined based on their peak areas. Th, U and Pu were separated on a RP column using mobile phase containing HIBA and methanol. Since Pu is prone to exist in multiple oxidation states, all the oxidation states were converted into Pu (IV) using H 2 O 2 in 3 M HNO 3 . Under the optimized conditions, Pu(IV) eluted first followed by Th and U. The concentrations of Th, U and Pu were determined by standard addition method and were found to be 1.10 ± 0.02 mg/g, 5.3 ± 0.3 µg/g and 27 ± 1 µg/g, respectively, in the dissolver solution of irradiated fuel. These values were in good agreement with the concentration of Th determined by biamperometry and those of U and Pu by isotope dilution thermal ionization mass spectrometry.

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Section: Introductionmentioning

confidence: 99%

Determination of Lanthanides, Thorium, Uranium and Plutonium in Irradiated (Th, Pu)O2 by Liquid Chromatography Using α-Hydroxyiso Butyric Acid (α-HIBA)

Kumar¹,

Jaison²,

Telmore³

et al. 2013

IJAMSC

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“…Many other eluent ions, which were the conjugate bases of weak acids (e.g., borate), were amenable to suppression and used for specific separations. Using similar technology and making some changes to the detection system, researchers developed suppressed IC into a technique that successfully separates inorganic cations (often with color-forming postcolumn reactions as the basis of detection [12]), organic acids and bases (13), carbohydrates (14), and amino acids (15).…”

Section: N Ne Ew W S St Ta At Ti Io On Na Ar Ry Y P Ph Ha As Se Es S mentioning

confidence: 99%

Peer Reviewed: Ion Chromatography Retrospective

Haddad¹

2001

Anal. Chem.

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“…The measurement of burn-up on dissolver solution of fuel subjected to high burn-up is challenging due to the high levels of radioactivity associated with the fuel. Various methods have been developed to measure the burn-up of spent nuclear fuels [1][2][3][4][5][6][7][8]. Among these, isotope dilution mass spectrometric technique (IDMS) is recognized as an established technique [2].…”

Section: Introductionmentioning

confidence: 99%

“…The HPLC based techniques using dynamic ion-exchange (individual lanthanide separation) and reversed phase chromatography (uranium and plutonium) were employed for the determination of lanthanides and actinides [3][4][5]7].…”

Section: Introductionmentioning

confidence: 99%

Burn-Up Measurements on Dissolver Solution of Mixed Oxide Fuel Using HPLC-Mass Spectrometric Method

Bera¹,

Balasubramanian²,

Datta³

et al. 2013

IJAMSC

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Burn-up measurement on an irradiated mixed oxide (MOX) test fuel pellet was carried out through measurements on the dissolver solution by HPLC-Thermal Ionization Mass Spectrometric (TIMS) technique. The studies carried out using HPLC as well as TIMS for quantification of burn-up value are described. While in one case, both the separation and determination of elements of interest (U, Pu and Nd) were carried out by HPLC; in another case, TIMS technique was used to quantify them from the HPLC separated fractions. The rapid separation procedures developed in our laboratory earlier were employed to isolate pure fractions of the desired elements. The individual lanthanide fission products (La to Eu) were separated from each other using dynamic ion-exchange chromatographic technique whereas uranium and plutonium were separated from each other using reversed phase chromatographic technique. The pure fractions of U, Pu and Nd obtained after HPLC separation procedure for "spiked" and "unspiked" dissolver solutions were used in TIMS measurements for the first time in our laboratory. In TIMS analysis, isotopic abundances of uranium, plutonium and neodymium fractions obtained from HPLC separation procedure on an "unspiked" fuel sample were measured. Nd were employed as spikes). The burn-up values from duplicate spiking experiments were computed based on the summation of 145 Nd + 146 Nd. The concentrations of neodymium, uranium and plutonium were also measured using HPLC with post-column derivatisation technique using aresenazo(III) as the post-column reagent. The atom % burn-up computed from HPLC and TIMS techniques were in good agreement.

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Dynamic ion exchange chromatography for determination of number of fissions in thorium-uranium dioxide fuels

Cited by 140 publications

References 9 publications

Determination of Lanthanides, Thorium, Uranium and Plutonium in Irradiated (Th, Pu)O2 by Liquid Chromatography Using α-Hydroxyiso Butyric Acid (α-HIBA)

Determination of Lanthanides, Thorium, Uranium and Plutonium in Irradiated (Th, Pu)O2 by Liquid Chromatography Using α-Hydroxyiso Butyric Acid (α-HIBA)

Peer Reviewed: Ion Chromatography Retrospective

Burn-Up Measurements on Dissolver Solution of Mixed Oxide Fuel Using HPLC-Mass Spectrometric Method

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