| 1. |
- Albertsson, Per, 1964, et al.
(författare)
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Astatine-211 based radionuclide therapy: Current clinical trial landscape
- 2023
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Ingår i: Frontiers in Medicine. - : Frontiers Media SA. - 2296-858X. ; 9
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Tidskriftsartikel (refereegranskat)abstract
- Astatine-211 (At-211) has physical properties that make it one of the top candidates for use as a radiation source for alpha particle-based radionuclide therapy, also referred to as targeted alpha therapy (TAT). Here, we summarize the main results of the completed clinical trials, further describe ongoing trials, and discuss future prospects.
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| 2. |
- Aneheim, Emma, 1982, et al.
(författare)
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A TBP/BTBP-based GANEX Separation Process. Part 1: Feasibility
- 2010
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Ingår i: Solvent Extraction and Ion Exchange. - : Informa UK Limited. - 0736-6299 .- 1532-2262. ; 28:4, s. 437-458
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Tidskriftsartikel (refereegranskat)abstract
- A GANEX (Group ActiNide EXtraction) separation system for transmutation has been developed. In this separation process the actinides should be extracted as a group from the lanthanides and the fission and corrosion/activation products. This can be achieved by combining BTBP (bis-triazine-bipyridine) with TBP (tri-butyl phosphate) in cyclohexanone. From 4M nitric acid this organic system extracts the actinides (log(DAm) = 2.19, log(DPu) = 2.31, log(DU) = 1.03, log(DNp) = 0.53) and also separates them from the lanthanides (log(DLa) = -2.0, log(DCe) = -1.72, log(DNd) = -1.05, log(DSm) = -0.18, log(DEu) = -0.02). One problem encountered is that some of the fission and corrosion products are also extracted. The new system however still looks feasible.
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| 3. |
- 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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| 4. |
- 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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| 5. |
- Aneheim, Emma, 1982, et al.
(författare)
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Affinity of charcoals for different forms of radioactive organic iodine
- 2018
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Ingår i: Nuclear Engineering and Design. - : Elsevier BV. - 0029-5493. ; 328, s. 228-240
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Tidskriftsartikel (refereegranskat)abstract
- During a serious nuclear reactor accident a large fraction of the radioactive iodine in the fuel can escape from the core and subsequently from the plant. While the noble gases in reactor fuel are more mobile than iodine, the iodine is often of greater concern as its chemistry and biology causes it to be more radiotoxic. Iodine has the potential to be re-concentrated in vivo in the thyroid. Filters containing charcoals are used both under normal operating conditions and during emergencies to retain iodine species, they are used in environmental sampling to estimate radioactive iodine and in respiratory protection systems such as air purifying filter respirators. During a nuclear accident iodine can exist in many forms. As the formation of organic iodine compounds other than methyl iodide has been observed in nuclear plants it can be reasoned that a failure of a charcoal to retain other organoiodines than methyl iodide could have adverse consequences. In this paper, the ability of different charcoals to capture various forms of radioactive organic iodine compounds has been explored. Besides elemental iodine used as reference methyl, chloromethyl, ethyl and isopropyl iodides have been studied together with iodoacetylene.
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| 6. |
- 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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| 7. |
- Aneheim, Emma, 1982, et al.
(författare)
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Astatine-211 labeling: a study towards automatic production of astatinated antibodies
- 2015
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Ingår i: Journal of Radioanalytical and Nuclear Chemistry. - : Springer Science and Business Media LLC. - 0236-5731 .- 1588-2780. ; 303:1, s. 979-983
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Tidskriftsartikel (refereegranskat)abstract
- Targeted alpha therapy is especially interesting for therapy of microscopic cancer tumors due to short path length and high linear energy transfer of the alpha particles. One of the most promising nuclides for targeted alpha therapy is At-211. To facilitate larger clinical studies using At-211, the current manual synthesis of radiolabeled antibodies would benefit from being transferred into an automated method. In this work, successful modifications of the manual synthesis have been performed in order to adapt it to automation. The automatic synthesis has also been tested using the modified synthesis method.
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| 8. |
- Aneheim, Emma, 1982, et al.
(författare)
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Automated astatination of biomolecules--a stepping stone towards multicenter clinical trials.
- 2015
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Ingår i: Scientific reports. - : Springer Science and Business Media LLC. - 2045-2322. ; 5
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Tidskriftsartikel (refereegranskat)abstract
- To facilitate multicentre clinical studies on targeted alpha therapy, it is necessary to develop an automated, on-site procedure for conjugating rare, short-lived, alpha-emitting radionuclides to biomolecules. Astatine-211 is one of the few alpha-emitting nuclides with appropriate chemical and physical properties for use in targeted therapies for cancer. Due to the very short range of the emitted α-particles, this therapy is particularly suited to treating occult, disseminated cancers. Astatine is not intrinsically tumour-specific; therefore, it requires an appropriate tumour-specific targeting vector, which can guide the radiation to the cancer cells. Consequently, an appropriate method is required for coupling the nuclide to the vector. To increase the availability of astatine-211 radiopharmaceuticals for targeted alpha therapy, their production should be automated. Here, we present a method that combines dry distillation of astatine-211 and a synthesis module for producing radiopharmaceuticals into a process platform. This platform will standardize production of astatinated radiopharmaceuticals, and hence, it will facilitate large clinical studies focused on this promising, but chemically challenging, alpha-emitting radionuclide. In this work, we describe the process platform, and we demonstrate the production of both astaine-211, for preclinical use, and astatine-211 labelled antibodies.
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| 9. |
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| 10. |
- 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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