Anwendung von Kationenaustausch-Hochdruckflüssigchromatographie in Kopplung mit on-line-Feststoffszintillationszählung zur Charakterisierung actinidenhaltiger Prozesslösungen
Anwendung von Kationenaustausch-Hochdruckflüssigchromatographie in Kopplung mit on-line-Feststoffszintillationszählung zur Charakterisierung actinidenhaltiger Prozesslösungen
On the basis of a liquid chromatography system the possibility was created to carry out a qualitative and quantitative determination of the actinides U, Np, Pu, Am and Cm in the presence of the lanthanide metals La to Gd, which are typical of radioactive process solutions, on an analytical scale and...
| Personal Name(s): | Lochny, M. (Corresponding author) |
|---|---|
| Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
| Imprint: |
Jülich
Forschungszentrum Jülich, Zentralbibliothek, Verlag
1998
|
| Physical Description: |
III, 142 p. |
| Document Type: |
Report Book |
| Research Program: |
ohne Topic |
| Series Title: |
Berichte des Forschungszentrums Jülich
3569 |
| Link: |
OpenAccess OpenAccess |
| Publikationsportal JuSER |
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| 100 | 1 | |a Lochny, M. |0 P:(DE-HGF)0 |b 0 |e Corresponding author | |
| 245 | |a Anwendung von Kationenaustausch-Hochdruckflüssigchromatographie in Kopplung mit on-line-Feststoffszintillationszählung zur Charakterisierung actinidenhaltiger Prozesslösungen | ||
| 260 | |a Jülich |c 1998 |b Forschungszentrum Jülich, Zentralbibliothek, Verlag | ||
| 300 | |a III, 142 p. | ||
| 490 | 0 | |a Berichte des Forschungszentrums Jülich |v 3569 | |
| 520 | |a On the basis of a liquid chromatography system the possibility was created to carry out a qualitative and quantitative determination of the actinides U, Np, Pu, Am and Cm in the presence of the lanthanide metals La to Gd, which are typical of radioactive process solutions, on an analytical scale and simple manner. The simultaneous separation on the cation exchanger Aminex® A9 is possible with 0.4 $\underline{M}$ citric acid and 0.02 $\underline{M}$ ascorbic acid, added as a reductant. Detection is effected on line via a UV/VIS and a radioactivity detector connected in series. The latter is provided with a self-made measuring cell on the basis of the thermoplastic solid scintillator Meltilex™. The cell, whose development and construction are described, is comparatively cheap, chemically inert, shows hardly any memory effects and offers the possibility for $\alpha$/$\beta$ discrimination. Its geometry determines the detection limits specified. With the detector cell presented, detection limits of 50 to 150 Bq absolute are reached for the $\alpha$-radiating actinides. The limits of detection for the $\beta$-radiating fission products and lanthanides are a function of the maximum energy of their radiation and provide values in the interval from 1 to 70 Bq absolute. The reproducibility of the obtained values (retention time, peak area, efficiencies, ...) is given in the range of 5 %. The possible differences in quantification can be specified within 10 - 30 %. Interferences due to the presence of fission products are shown. Calculations of the radiation exposure of the ion exchanger under real conditions show sufficient resistance of the resin on an analytical scale. | ||
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