| 11. |
- Aneheim, Emma, 1982, et al.
(författare)
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A TBP/BTBP-Based GANEX Separation Process Part 3: Fission Product Handling
- 2013
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Ingår i: Solvent Extraction and Ion Exchange. - : Informa UK Limited. - 0736-6299 .- 1532-2262. ; 31:3, s. 237-252
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Tidskriftsartikel (refereegranskat)abstract
- A Group ActiNide EXtraction (GANEX) separation system for transmutation has been developed, combining CyMe4-BTBP with TBP and cyclohexanone. This new GANEX solvent has proven efficient in actinide extraction but also been found to extract some undesired fission products and corrosion products. Three major fission products were primarily selected for the study: Mo, Zr, and Pd. There are three main strategies for handling the extraction problem, all of which have been investigated and discussed; these are Pre-extraction, Suppression, and Scrubbing. The only strategy that was found to control the behavior of all three main fission products was suppression by the combination of two water-soluble complexing agents bimet and mannitol.
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| 12. |
- Aneheim, Emma, 1982, et al.
(författare)
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A TBP/BTBP-based GANEX Separation ProcessPart 2: Ageing, Hydrolytic, and Radiolytic Stability
- 2011
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Ingår i: Solvent Extraction and Ion Exchange. - : Informa UK Limited. - 0736-6299 .- 1532-2262. ; 29:2, s. 157-175
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Tidskriftsartikel (refereegranskat)abstract
- The waste from nuclear power plants worldwide has to be isolated from man and his environment for about 100,000 years to equal the levels of natural uranium. If, however, the long-lived actinides could be separated from the spent fuel and transmuted, then the isolation time could be shortened to about 1,000 years. This does, however, require the selective separation of the actinides from the rest of the waste. Several processes exist for such a separation, of which one is the Group ActiNide Extraction (GANEX) process. A novel GANEX process has been developed at the Chalmers University of Technology utilizing the properties of already well known extractants by combining BTBP and TBP into one solvent. The stability provided by this GANEX solvent towards ageing, hydrolysis, and radiolysis has been investigated. The results show that the actinide distribution ratios are maintained after a long duration of contact with strong nitric acid. The solvent has also been found to be stable towards radiolysis up to 200 kGy in contact with 4 M nitric acid.
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| 13. |
- Aneheim, Emma, 1982, et al.
(författare)
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Aqueous complexation of palladium to prevent precipitation and extraction in a group actinide extraction system
- 2012
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Ingår i: Hydrometallurgy. - : Elsevier BV. - 0304-386X. ; 115, s. 71-76
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Tidskriftsartikel (refereegranskat)abstract
- It has recently been reported that a cyclohexanone based solvent containing the extractant, CyMe4-BTBP (BisTriazine,BiPyridine) together with tri-butyl phosphate intended for use in a GANEX (Group Actinide Extraction) process also extracts the fission product palladium. When cyclohexanone was used as a diluent it was also observed that without any extractant present in the organic phase, palladium rapidly formed a fine black precipitate of metallic palladium. In this work, two water soluble complexing agents were identified and found to be able to stabilize the palladium in 1 M nitric acid, preventing it from precipitating, namely the amino acid methionine and its derivative (25,2'S)-4,4'-(ethane-12-diylbis(sulfanediyl))bis(2-aminobutanoic acid) (bimet). Of these two, however, only bimet could reliably prevent the precipitation of palladium from the process aqueous solution (4 M nitric acid) and stop its extraction by the organic solvent. It was also found that an addition of bimet to the aqueous phase did not alter the actinide extraction by the GANEX solvent, thus making it a feasible candidate for masking the palladium extraction in a future process.
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| 14. |
- Aneheim, Emma, 1982, et al.
(författare)
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Development of a Novel GANEX Process
- 2010
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Ingår i: ACS Symposium Series. - Washington, DC : American Chemical Society. - 1947-5918 .- 0097-6156. ; 1046, s. 119-130
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Konferensbidrag (refereegranskat)abstract
- The waste from nuclear power plants has to be isolated from man and his environment for about 100,000 years to be considered safe. It has been suggested that if the long-lived actinides could be separated from the spent fuel and transmuted, the isolation time could be shortened to about 1,000 years. This, however, requires selective separation of parts of the waste. The partitioning for transmutation research in Europe has for the major part taken place within several European Union Framework Programmes. Within the projects NEWPART, PARTNEW and EUROPART a process scheme for the partitioning of nuclear waste from the PUREX process was developed. The scheme includes the DIAMEX, SANEX and SESAME-processes among which both the DIAMEX and SANEX process has been successfully tested on genuine spent fuel. However, in the latest EU Project ACSEPT, which started in 2008, another approach towards partitioning is being investigated. This is the so called GANEX (Group ActiNide EXtraction) process. In the GANEX process all the actinides in the dissolved spent fuel are extracted as a group and hence separated from the lanthanides as well as the rest of the fission and corrosion/activation products. A novel GANEX process has been developed at Chalmers university of Technology in Sweden. This new process utilizes the properties of already well known extractants by combining BTBP and TBP into one solvent. The system is able to extract U, Np, Pu and Am from strong nitric acid and simultaneously separate these elements from the lanthanides. This is done with sufficiently high distribution ratios and separation factors without the need for any redox control.
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| 15. |
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| 16. |
- Aneheim, Emma, 1982, et al.
(författare)
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Extraction experiments after radiolysis of a proposed GANEX solvent - the effect of time
- 2012
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Ingår i: Procedia Chemistry. - : Elsevier BV. - 1876-6196. ; 7, s. 123-129
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Konferensbidrag (refereegranskat)abstract
- In a solvent intended for use within group actinide extraction CyMe4-BTBP and TBP are combined together in cyclohexanone. After irradiating the solvent in acid contact a latency period before extraction reduced the extraction capability of plutonium. This reduction was larger when the solvent was kept in contact with the acid after irradiation. The decrease in plutonium extraction could be an effect of both a reduced extraction performance of CyMe4-BTBP caused by hydrolysis as well as a shift in oxidation state of the plutonium as it was shown that oxidizing Pu(IV) to Pu(VI) decreased the extraction by the solvent. (C) 2012 Elsevier B. V. .. Selection and/or peer-review under responsibility of the Chairman of the ATALANTE 2012 Program Committee
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| 17. |
- Aneheim, Emma, 1982, et al.
(författare)
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Fission product interactions with nitrogen donor ligands used for spent nuclear fuel treatment
- 2013
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Ingår i: Polyhedron. - : Elsevier BV. - 0277-5387. ; 50:1, s. 154-163
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Tidskriftsartikel (refereegranskat)abstract
- The so called BTBP (bis-triazine bi-pyridine)-type molecules have been developed for liquid-liquid extraction in the advanced reprocessing of used nuclear fuel. One solvent composition that has proven to be promising for such an application is the combination of CyMe4-BTBP and tri-butyl phosphate (TBP) in cyclohexanone. This solvent can extract the actinides successfully but unfortunately some fission products are also co-extracted. One of the most problematic fission products is palladium, but silver and cadmium are also extracted by the proposed solvent, which has been investigated here. In this study it was found that CyMe4-BTBP in cyclohexanone, when extracting palladium from nitric acid, forms complexes that are soluble both in the organic and aqueous phase. The predominant complex observed in both phases established with mass spectrometry and confirmed by NMR is a 1:1 complex, contrary to silver that forms 2:2 complexes and cadmium that forms 1:2 complexes. The nitrate dependency of the palladium extraction from nitric acid into a BTBP containing organic phase was found to be two. However, with higher ionic strengths, such as under process conditions, the palladium was found to be salted out into the organic phase.
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| 18. |
- Aneheim, Emma, 1982, et al.
(författare)
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Studies of a Solvent for GANEX Applications Containing CyMe4-BTBP and DEHBA in Cyclohexanone
- 2012
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Ingår i: Separation Science and Technology. - : Informa UK Limited. - 1520-5754 .- 0149-6395. ; 47:5, s. 663-669
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Tidskriftsartikel (refereegranskat)abstract
- Research focus within separation for transmutation in Europe today lies in the development of a solvent extraction separation process called GANEX (Group ActiNide EXtraction). In this type of process the actinides should be extracted as a group and separated from the lanthanides and the other fission and corrosion/activation products. One GANEX process has been developed combining the two extractants bis-triazine-bi-pyridine (BTBP) and tri-butyl phosphate (TBP) in cyclohexanone. In previous work the TBP has been successfully substituted with N,N-di-2-ethylhexylbutyramide (DEHBA). In this paper, this exchange has been further studied investigating also fission product extraction as well as hydrolytic and radiolytic stability and acid extraction.
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| 19. |
- Aneheim, Emma, 1982, et al.
(författare)
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Technetium chemistry in a novel group actinide extraction process
- 2013
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Ingår i: Journal of Radioanalytical and Nuclear Chemistry. - : Springer Science and Business Media LLC. - 0236-5731 .- 1588-2780. ; 296:2, s. 743-748
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Tidskriftsartikel (refereegranskat)abstract
- A newly developed method for advanced reprocessing of used nuclear fuel is the Group ActiNide EXtraction (GANEX) process. It is a liquid-liquid extraction process that aims at extracting all the actinides as a group from dissolved used nuclear fuel. This extraction can either be performed after a removal of the bulk uranium or directly on the dissolution liquor. At Chalmers University of Technology in Sweden a solvent that utilizes tributyl-phosphate (TBP) and a molecule from the bis-triazine bipyridine (BTBP) class of ligands dissolved in cyclohexanone has been developed for the use in a GANEX process. Previously the system has not been tested with the presence of technetium that is one of the major fission products. Technetium is often considered a problem within reprocessing since it has a chemical behaviour that differs from most other elements in the spent fuel. Therefore, a special emphasis was put on the investigation of technetium in the selected GANEX system. It was shown that technetium is readily extracted by the GANEX solvent and that cyclohexanone is the main extractant when no other metals were present in the system. It was also found that the presence of uranium decreased the overall technetium extraction despite a slight co-extraction with TBP, while irradiation of the GANEX solvent to large doses ([>1 MGy) increased its technetium extraction capability. It was also discovered that an increased nitrate concentration in the aqueous phase and an addition of other fission products both inhibited the technetium extraction even though fission product loading most likely changed the extraction mechanism to co-extraction by BTBP.
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| 20. |
- Bauhn, Lovisa, 1981, et al.
(författare)
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A micro hot test of the Chalmers-GANEX extraction system on used nuclear fuel
- 2013
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Ingår i: International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads. ; 1, s. 335-340
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Konferensbidrag (refereegranskat)abstract
- In the present study, a "micro hot test" has been performed using the Chalmers-GANEX (Group ActiNide EXtraction) system for partitioning of used nuclear fuel. The test included a pre-extraction step using N,N-di-2- ethylhexylbutyramide (DEHBA) in n-octanol to remove the bulk part of the uranium. This pre-extraction was followed by a group extraction of actinides using the mixture of TBP and CyMe4-BTBP in cyclohexanone as suggested in the Chalmers-GANEX process, and a three stage stripping of the extracted actinides. Distribution ratios for the extractions and stripping were determined based on a combination of γ- and α-spectrometry, as well as ICP-MS measurements. Successful extraction of uranium, plutonium and the minor actinides neptunium, americium and curium was achieved. However, measurements also indicated that co-extraction of europium occurs to some extent during the separation. These results were expected based on previous experiments using trace concentrations of actinides and lanthanides. Since this test was only performed in one stage with respect to the group actinide extraction, it is expected that multi stage tests will give even better results.
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