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

Cassidy, R. M.; Elchuk, S.; Elliot, N. L.; Green, L. W.; Knight, C. H.; Recoskie, B. M.

doi:10.1021/ac00297a045

Cited by 85 publications

(43 citation statements)

References 7 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Unlike pure HNO 3 , KNO 3 (up to 2 M) could not elute Th(IV) from the cation exchange column. Uranium was eluted with 0.32 M KNO 3 and increase in the KNO 3 concentration up to 1.5 M decreased the retention time of U(VI). The trend obtained with KNO 3 eluent is depicted in Fig.…”

Section: Elution With Pure Knomentioning

confidence: 98%

“…An important observation was that broad uranium peak appeared and the elution characteristics were inferior to pure HNO 3 elution and Th(IV) could not be eluted at all. It seems that unlike U(VI), Th(IV) does not form cationic species with pure KNO 3 . This shows that the formation of Th(IV)-nitrato complex not only depends on the nitrate concentration but also on the acid concentration.…”

Section: Elution With Pure Knomentioning

confidence: 99%

See 1 more Smart Citation

Separation behavior of U(VI) and Th(IV) on a cation exchange column using 2,6‐pyridine dicarboxylic acid as a complexing agent and its application for the rapid separation and determination of U and Th by ion chromatography

Jeyakumar

Mishra

Das

et al. 2011

J of Separation Science

View full text Add to dashboard Cite

The retention behavior of U and Th as their 2,6-pyridine dicarboxylic acid (PDCA) complexes on a cation exchange column was investigated under low pH conditions. Based on the observed retention characteristics, an ion chromatographic method for the rapid separation of uranium and thorium in isocratic elution mode using 0.08 mM PDCA and 0.24 M KNO(3) in 0.22 M HNO(3) as the eluent was developed. Both uranium and thorium were eluted as their PDCA complexes within 2 min, whereas the transition and lanthanide metal cations were eluted as an unresolved broad peak after thorium. Under the optimized conditions both U and Th have no interference either from alkali and alkaline earth elements up to a concentration ratio of 1:500 or from other elements up to 1:100. The detection limits (LOD) of U and Th were calculated as 0.04 and 0.06 ppm, respectively (S/N=3). The precision in the measurement of peak area of 0.5 ppm of both U and Th was better than 5% and a linear calibration in the concentration range of 0.25-25 ppm of U and Th was obtained. The method was successfully applied to determine U and Th in effluent water samples.

show abstract

Section: Elution With Pure Knomentioning

confidence: 98%

Section: Elution With Pure Knomentioning

confidence: 99%

Separation behavior of U(VI) and Th(IV) on a cation exchange column using 2,6‐pyridine dicarboxylic acid as a complexing agent and its application for the rapid separation and determination of U and Th by ion chromatography

Jeyakumar

Mishra

Das

et al. 2011

J of Separation Science

View full text Add to dashboard Cite

show abstract

“…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

View full text Add to dashboard Cite

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.

show abstract

“…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

View full text Add to dashboard Cite

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.

show abstract

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

Cited by 85 publications

References 7 publications

Separation behavior of U(VI) and Th(IV) on a cation exchange column using 2,6‐pyridine dicarboxylic acid as a complexing agent and its application for the rapid separation and determination of U and Th by ion chromatography

Separation behavior of U(VI) and Th(IV) on a cation exchange column using 2,6‐pyridine dicarboxylic acid as a complexing agent and its application for the rapid separation and determination of U and Th by ion chromatography

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

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

Contact Info

Product

Resources

About