Plutonium (IV) Quantification in Technologically Relevant Media Using Potentiometric Sensor Array

The quantification of plutonium in technological streams during spent nuclear fuel (SNF) reprocessing is an important practical task that has to be solved to ensure the safety of the process. Currently applied methods are tedious, time-consuming and can hardly be implemented in on-line mode. A fast and simple quantitative plutonium (IV) analysis using a potentiometric sensor array based on extracting agents is suggested in this study. The response of the set of specially designed PVC-plasticized membrane sensors can be related to plutonium content in solutions simulating real SNF-reprocessing media through multivariate regression modeling, providing 30% higher precision of plutonium quantification than optical spectroscopy.

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Combination of optical spectroscopy and chemometric techniques—a possible way for on-line monitoring of spent nuclear fuel (SNF) reprocessing

Radiochimica Acta ◽

10.1524/ract.2012.1901 ◽

2012 ◽

Vol 100 (3) ◽

pp. 185-188 ◽

Cited By ~ 11

Author(s):

D. Kirsanov ◽

V. Babain ◽

M. Agafonova-Moroz ◽

A. Lumpov ◽

A. Legin

Keyword(s):

Nuclear Fuel ◽

Optical Spectroscopy ◽

Spent Nuclear Fuel ◽

On Line ◽

Chemometric Techniques ◽

Snf Reprocessing

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

Advances in X-ray Analysis ◽

10.1154/s0376030800013823 ◽

1984 ◽

Vol 28 ◽

pp. 91-98 ◽

Cited By ~ 1

Author(s):

David C. Camp

Keyword(s):

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

Fluorescence Analysis ◽

Solution Concentration ◽

Experimental Methodology ◽

Nondestructive Analysis ◽

X Ray ◽

Analysis Techniques ◽

On Line ◽

The U.S

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.

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Ceramic Immobilisation Options for Technetium

MRS Proceedings ◽

10.1557/opl.2012.1567 ◽

2012 ◽

Vol 1518 ◽

pp. 111-116 ◽

Cited By ~ 2

Author(s):

Martin C. Stennett ◽

Daniel J. Backhouse ◽

Colin L. Freeman ◽

Neil C. Hyatt

Keyword(s):

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

High Mobility ◽

X Ray Diffraction ◽

Host Matrix ◽

X Ray ◽

Separate Fraction ◽

X Ray Absorption ◽

Snf Reprocessing

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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On-line molecular iodine isotopologue detection in gaseous media during spent nuclear fuel reprocessing using a laser-induced fluorescence method

Laser Physics Letters ◽

10.1088/1612-2011/12/6/065601 ◽

2015 ◽

Vol 12 (6) ◽

pp. 065601

Author(s):

S V Kireev ◽

S L Shnyrev

Keyword(s):

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

Molecular Iodine ◽

Laser Induced Fluorescence ◽

Fluorescence Method ◽

Spent Nuclear Fuel Reprocessing ◽

Nuclear Fuel Reprocessing ◽

Gaseous Media ◽

On Line ◽

Fuel Reprocessing

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Mathematic Simulation of Crystallization Refining Process of Spent Nuclear Fuel Reprocessing Desired Products in Linear Crystallizer

Advanced Materials Research ◽

10.4028/www.scientific.net/amr.1084.666 ◽

2015 ◽

Vol 1084 ◽

pp. 666-672 ◽

Cited By ~ 6

Author(s):

Sergey Veselov ◽

Vladimir Volk ◽

Vladimir Kasheev ◽

Tatiana Podimova ◽

Evgeny Posenitskiy

Keyword(s):

Nuclear Fuel ◽

Uranyl Nitrate ◽

Spent Nuclear Fuel ◽

Refining Process ◽

Nitrate Hexahydrate ◽

Active Volume ◽

Operating Modes ◽

Extraction And Purification ◽

The Mathematical Model ◽

Snf Reprocessing

The object of research is crystallization refining process of uranyl nitrate (UN) from nitric acid solution. The process of crystallization refining is a working operation which can provide effective extraction and purification of desired products (fission materials) during spent nuclear fuel (SNF) reprocessing. The purpose of the work is mathematical description of the linear continuous crystallizer operating modes using the example of uranyl nitrate hexahydrate crystals sorting. The mathematical model presented in the work allows describing changes of crystallization process parameters in the active volume of crystallizer and choosing the most effective operating modes in terms of extraction of SNF reprocessing desired products.

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Toward a Greenish Nuclear Fuel Cycle: Ionic Liquids as Solvents for Spent Nuclear Fuel Reprocessing and Other Decontamination Processes for Contaminated Metal Waste

Physical Sciences Reviews ◽

10.1515/psr-2016-0074 ◽

2016 ◽

Vol 1 (12) ◽

Cited By ~ 4

Author(s):

Martin Straka

Keyword(s):

Ionic Liquids ◽

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

Fuel Cycle ◽

Nuclear Fuel Cycle ◽

Spent Nuclear Fuel Reprocessing ◽

Innovative Solutions ◽

Fuel Reprocessing ◽

Final Disposition ◽

Snf Reprocessing

Abstract The final disposition of spent nuclear fuel (SNF) is an area that requires innovative solutions. The use of ionic liquids (ILs) has been examined as one means to remediate SNF in a variety of different chemical environments and with different chemical starting materials. The effectiveness of various ILs for SNF reprocessing, as well as the reaction chemistry that occurs in them, is discussed.

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