scholarly journals K-Edge X-ray Fluorescence Analysis for Actinide and Heavy Elements Solution Concentration Measurements

1984 ◽  
Vol 28 ◽  
pp. 91-98 ◽  
Author(s):  
David C. Camp

There are currently no plans for the commercial reprocessing of nuclear fuel in the U.S. This is not the case in Japan, England, France, Germany, or the USSR. The U.S. does, however, include the reprocessing of spent nuclear fuel as a part of its defense programs. The Office of Safeguards and Security of DOE's Defense Programs has funded the development and optimization of numerous nondestructive analysis techniques including K-edge x-ray fluorescence analysis. This paper reviews some of the implementation efforts resulting from R&D supported by that office.In 1979, the concept of using K-edge x-ray fluorescence analysis (K XRFA) for the analysis of actinide solution concentrations was first presented. K XRFA using small radioactive Co-57 sources has been shown to be a practical way to measure actinide solution concentrations in offline, at-line, or on-line configurations. The experimental methodology is elegant and the hardware is simple.

1975 ◽  
Vol 19 ◽  
pp. 267-272 ◽  
Author(s):  
W. Ratyński ◽  
J. Parus ◽  
J. Tys ◽  
A. Ciszek

X-ray fluorescence spectroscopy is new becoming a tool in research and. industry. Semiconductor detectors are proving valuable in measuring fluorescent X rays, and so are providing a versatile tool for rapid multielement analysis of many types of samples. This paper will mainly be concerned with, different types of copper ore. An experimental setup has been designed to determine Cu, Fe and Pb of concentration ranging from 0.1 to 20, to 5, and to 4 percent, respectively, with analytical precision of 20% relative at 0.1% Cu, and 3% relative at 20% Cu. For excitation a 100 mCi Pu-238 source and/or a low power air-cooled X-ray tube were used. Data acquisition and “on-line” evaluation for each sample takes about 100 seconds. Electronics blocks and sub-systems used In the set-up are available commercially. The most important benefit to be obtained from the setup is the ability to provide precise, reproducible determinations of large numbers of samples day after day.


1979 ◽  
Vol 23 ◽  
pp. 163-176
Author(s):  
D. C. Camp ◽  
W. D. Ruhter

In the event that nuclear fuel from light water reactors (LWR) is reprocessed to reclaim the uranium or plutonium, several analytical techniques will be used for product accountability. Generally, the isotopic content of both the plutonium and uranium in the reprocessed product will have to be accurately determined. One plan for the reprocessing of LWR spent fuel incorporates the following scheme. After separation from both the fission products and transplutonium actinides (including neptunium and americium), part of the uranium and all of the plutonium in a nitrate solution will merge together to form a coprocessed stream. This solution will be concentrated by evaporation and sent to a hold tank for accountability. Input concentrations into the hold tank could be up to 350 g U/ℓ and nearly 50 g Pu/ℓ. The variation to be expected in these concentrations is not known. The remaining uranium fraction will be further purified and sent to a separate storage tank. Its expected stream concentration will be about 60 g U/ℓ. These two relatively high actinide stream concentrations can be monitored rapidly, quantitatively, and nondestructively using the technique of energy-dispersive x-ray fluorescence analysis(XRFA).


1980 ◽  
Vol 24 ◽  
pp. 289-296
Author(s):  
S. K. Kawatra ◽  
J. L. Dalton

AbstractOn-line X-ray fluorescence analysis is used in the mineral processing industry to monitor the composition of the solids contained in various slurry streams. This study compares wavelength dispersive and energy dispersive techniques by using a slurry recirculation system employing both an X-ray tube excitation-wavelength dispersive system, and an isotope-excitation energy dispersive system. The results showed the less costly energy dispersive system yields accurate information that can be used to control milling operations.


2022 ◽  
Vol 29 (1) ◽  
Author(s):  
Alexander Scott Ditter ◽  
Danil E. Smiles ◽  
Daniel Lussier ◽  
Alison B. Altman ◽  
Mukesh Bachhav ◽  
...  

Soft X-ray spectromicroscopy at the O K-edge, U N 4,5-edges and Ce M 4,5-edges has been performed on focused ion beam sections of spent nuclear fuel for the first time, yielding chemical information on the sub-micrometer scale. To analyze these data, a modification to non-negative matrix factorization (NMF) was developed, in which the data are no longer required to be non-negative, but the non-negativity of the spectral components and fit coefficients is largely preserved. The modified NMF method was utilized at the O K-edge to distinguish between two components, one present in the bulk of the sample similar to UO2 and one present at the interface of the sample which is a hyperstoichiometric UO2+x species. The species maps are consistent with a model of a thin layer of UO2+x over the entire sample, which is likely explained by oxidation after focused ion beam (FIB) sectioning. In addition to the uranium oxide bulk of the sample, Ce measurements were also performed to investigate the oxidation state of that fission product, which is the subject of considerable interest. Analysis of the Ce spectra shows that Ce is in a predominantly trivalent state, with a possible contribution from tetravalent Ce. Atom probe analysis was performed to provide confirmation of the presence and localization of Ce in the spent fuel.


1992 ◽  
Vol 36 ◽  
pp. 111-120
Author(s):  
Naoki Matsuura ◽  
Shigetoshi Kurozumi ◽  
Tatsuo Fukuzaki ◽  
Tomoya Arai

Coating weight measurements by X-ray fluorescence analysis have been well established technology in industrial applications. The coating film measurements such as tin-plated steel and galvanized steel are carried out with an on-line gauge which is based on laboratory experiments. The approximate sample speed is 200m/min for a tin plate gauge, 150m/min for galvanized steel and 100m/min for electrolytic zinc coating steel.


1985 ◽  
Vol 29 ◽  
pp. 485-492
Author(s):  
Claude R. Hudgens

This project was Initiated for the purpose of demonstrating the feasibility of on-line x-ray fluorescence (XRF) analysis for the nondestructive assay of fissile elements (SNM) in reactor fuel reprocessing (dlssolver) solutions, using wavelength dispersive x-ray fluorescence analysis because of its high immunity to the intense gamma emissions of the solutions. A prime objective of this project was the identification and dimensioning of.the parameters critical to XRF assays of high accuracy. The concepts presented herein, though directed primarily to assay of solutions with emphasis on low signal-to-noise conditions and low count rates, are applicable to all assays of solids, slurries, and gases.


2012 ◽  
Vol 1518 ◽  
pp. 111-116 ◽  
Author(s):  
Martin C. Stennett ◽  
Daniel J. Backhouse ◽  
Colin L. Freeman ◽  
Neil C. Hyatt

ABSTRACTTechnetium-99 (99Tc) is a fission product produced during the burning of nuclear fuel and is particularly hazardous due to its long half life (210000 years), relatively high content in nuclear fuel (approx. 1 kg per ton of SNF), low sorption, and high mobility in aerobic environments. During spent nuclear fuel (SNF) reprocessing Tc is released either as a separate fraction or in complexes with actinides and zirconium. Although Tc has historically been discharged into the marine environment more stringent regulations mean that the preferred long term option is to immobilise Tc in a highly stable and durable matrix. This study investigated the feasibility of incorporating of Mo (as a Tc analogue) in a crystalline host matrix, synthesis by solid state synthesis under different atmospheres. Samples have been characterised with X-ray diffraction (XRD), scanning electron microscopy (SEM) and X-ray absorption spectroscopy (XAS).


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