Separation of Trivalent Minor Actinides from Fission Products Using Single R-BTP Column Extraction Chromatography

2011 ◽  
Vol 48 (6) ◽  
pp. 855-858 ◽  
Author(s):  
Tatsuro MATSUMURA ◽  
Kazumi MATSUMURA ◽  
Yasuji MORITA ◽  
Yoshikazu KOMA ◽  
Yuichi SANO ◽  
...  
Keyword(s):  
Extraction Chromatography ◽  
Fission Products ◽  
Minor Actinides ◽  
Column Extraction

Separation of actinides by extraction chromatography prior to X-ray fluorescence measurement for analytical control of a PUREX test

2007 ◽  
Vol 95 (11) ◽  
Author(s):  
Marielle Crozet ◽  
Mireille Guigue
Keyword(s):  
Extraction Chromatography ◽  
Fission Products ◽  
Purex Process ◽  
Fluorescence Measurement ◽  
Analytical Control ◽  
Performance Control ◽  
X Ray ◽  
Extraction Step ◽  
Extraction Test ◽  
Column Extraction

Five separation methods by Eichrom column extraction chromatography were developed and implemented for performance control of a PUREX (Plutonium, Uranium Refining by EXtraction) test.Four of them, concerning the separation between actinides, are described in this work. The latest, concerning the separation of actinides from fission products in a main raffinate is described in another article submitted to the same journal.For the production of U, Pu and Np streams following the “main extraction” step in the PUREX process, it is necessary to determine the concentration of the two residual actinides in the third actinide stream:A final separation method was developed to quantify the residual U in a Pu/Np flow for the Np/Pu partitioning step of the PUREX process. This separation is a prerequisite for LXF to eliminate any interference due to Pu and Np when measuring the U concentration.These separation methods necessary upstream from the LXF measurement were applied during the PUREX test in 2005 in ATALANTE (French acronym for “Alpha facilities and analysis laboratories, transuranics and reprocessing research”).

Separation of actinides from fission products by extraction chromatography prior to X-ray fluorescence measurement for analytical control of a PUREX test

2007 ◽  
Vol 95 (11) ◽  
Author(s):  
Marielle Crozet ◽  
Mireille Guigue
Keyword(s):  
Extraction Chromatography ◽  
Fission Products ◽  
Purex Process ◽  
Fluorescence Measurement ◽  
Analytical Control ◽  
Performance Control ◽  
X Ray ◽  
Extraction Test ◽  
The Subject ◽  
Column Extraction

Five separation methods by Eichrom column extraction chromatography were developed and implemented for performance control of a PUREX (Plutonium, Uranium Refining by EXtraction) test. One of them concerning the separation of actinides from fission products in the main PUREX raffinate is the subject of this work. The others, concerning separation between actinides, are described in another article submitted to the same journal.Analytical control of a PUREX process test implies measuring the neptunium, plutonium and uranium concentrations in the main extraction raffinate. The fission products are the major constituents of the raffinate, and thus prevent the use of direct L-line X-ray fluorescence (LXF) for these determinations. An actinide separation process by extraction chromatography with quantitative efficiency was therefore developed.This separation method necessary upstream from the LXF measurement was applied during the PUREX test in 2005 in ATALANTE (French acronym for “Alpha facilities and analysis laboratories, transuranics and reprocessing research”).

Determination of Hg(II) in drinking water by atomic absorption spectrometry - Cold vapour method after concentration by column extraction chromatography

1984 ◽  
Vol 49 (5) ◽  
pp. 1134-1139 ◽  
Author(s):  
Zdeněk Šmejkal ◽  
Jitka Tauferová ◽  
Mária Madová ◽  
Zlatica Teplá
Keyword(s):  
Drinking Water ◽  
Atomic Absorption Spectrometry ◽  
Atomic Absorption ◽  
Extraction Chromatography ◽  
Absorption Spectrometry ◽  
Average Yield ◽  
Water Mains ◽  
Cold Vapour ◽  
Column Extraction

The method describes concentration of mercury in samples of drinking water from water mains with Hg concentration above 1.0 . 10-7 g l-1 (5.0 . 10-10mol l-1) by means of extraction chromatography on a column packed with a carrier Synachrom E-5 wetted with saturated solution of bis(diethyldithiocarbamate)copper(II) complex in 1 : 1 mixture 1,2-dichlorobenzene + cyclohexane. After elution with 3.0 mol l-1 HCl the mercury concentration in the eluate is determined by atomic absorption spectrometry - cold vapour method. Average yield of the mercury separation from the model solutions was 95.8%.

A fast, single column extraction chromatography method for the isolation of Neodymium from iron-rich materials prior to radiogenic isotope ratio measurements

2022 ◽  
Author(s):  
Abdelmouhcine GANNOUN ◽  
Krzysztof SUCHORSK ◽  
Christian Pin
Keyword(s):  
Extraction Chromatography ◽  
Isotope Ratio ◽  
Separation Method ◽  
Chromatography Method ◽  
Radiogenic Isotope ◽  
Synergistic Enhancement ◽  
Isotopic Analyses ◽  
Single Column ◽  
Column Extraction ◽  
Isotope Ratio Measurements

A novel separation method is described for the separation of Nd from Fe-rich, silicate samples in view of isotopic analyses. The procedure is based on the synergistic enhancement of the...

A tandem-column extraction chromatography for Nd separation: minimizing mass-independent isotope fractionation for ultrahigh-precision Nd isotope-ratio analysis

2022 ◽  
Author(s):  
Da Wang ◽  
Richard Carlson
Keyword(s):  
Solar System ◽  
Extraction Chromatography ◽  
Isotope Ratio ◽  
Isotope Fractionation ◽  
Ratio Analysis ◽  
Nd Isotope ◽  
Planetary Differentiation ◽  
Isotope Ratio Analysis ◽  
Isotope System ◽  
Column Extraction

The short-lived 146Sm-142Nd isotope system traces key early planetary differentiation processes that occurred during the first 500 million-years of solar system history. The variations of 142Nd/144Nd in terrestrial samples, typically...

Zirconia Inert Matrix Fuel for Plutonium and Minor Actinides Management in Reactors and as an Ultimate Waste Form

2008 ◽  
Vol 1104 ◽  
Author(s):  
Claude Degueldre ◽  
Wolfgang Wiesenack
Keyword(s):  
Near Field ◽  
Fission Products ◽  
Minor Actinides ◽  
Spent Fuel ◽  
Geological Disposal ◽  
Inert Matrix Fuel ◽  
Inert Matrix ◽  
Fuel Pellets ◽  
Reducing Conditions ◽  
Deep Geological Disposal

AbstractA plutonia stabilised zirconia doped with yttria and erbia has been selected as inert matrix fuel (IMF) at PSI. The results of experimental irradiation tests on yttria-stabilised zirconia doped with plutonia and erbia pellets in the Halden research reactor as well as a study of zirconia solubility are presented. Zirconia must be stabilised by yttria to form a solid solution such as MAz(Y,Er)yPuxZr1-yO2-ζ where minor actinides (MA) oxides are also soluble. (Er,Y,Pu,Zr)O2-ζ (with Pu containing 5% Am) was successfully prepared at PSI and irradiated in the Halden reactor. Emphasis is given on the zirconia-IMF properties under in-pile irradiation, on the fuel material centre temperatures and on the fission gas release. The retention of fission products in zirconia may be stronger at similar temperature, compared to UO2. The outstanding behaviour of plutonia-zirconia inert matrix fuel is compared to the classical (U,Pu)O2 fuels. The properties of the spent fuel pellets are presented focusing on the once through strategy. For this strategy, low solubility of the inert matrix is required for geological disposal. This parameter was studied in detail for a range of solutions corresponding to groundwater under near field conditions. Under these conditions the IMF solubility is about 109 times smaller than glass, several orders of magnitude lower than UO2 in oxidising conditions (Yucca Mountain) and comparable in reducing conditions, which makes the zirconia material very attractive for deep geological disposal. The behaviour of plutonia-zirconia inert matrix fuel is discussed within a burn and bury strategy.

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