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Development of the Chalmers Grouped Actinide Extraction Process

References 1. Madic, C., Testard, F., Hudson, M., Liljenzin, J. -O., Christiansen, B., Ferrando, M., Facchini, A., Geist, A., Modolo, G., Gonzalez-Espartero, A., & De Mendoza, J. (2004). PARTNEW New solvent extraction processes for minor actinides. Final report. CEA. (Report CEA-R-6066). 2. Aoki, S. (2002). Research and development in Japan on long-lived nuclide partitioning and transmutation technology. Prog. Nucl. Energy, 40, 343-348. 3. Salvatores, M., Slessarev, I., Ritter, G., Fougeras, P., Tchistiakov, A

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The IOERT IntraLine accelerator – the development, current state, and future plans

Abstract

Intraoperative electron radiation therapy (IOERT) is a cancer treatment method that combines oncologic surgery with electron beam radiotherapy. This method can reduce the duration of entire tumor treatment and increase its effectiveness. Moreover, shortening the treatment time significantly reduces the cost and accessibility of the therapy. As a result of interdisciplinary research, an innovative accelerator for IOERT, the IntraLine, was developed. In the course of this work, four patent applications were filed. Today, the work is half way through. In the near future, the device will be optimized. New mechanical design solutions will be developed. Mechanical optimization will significantly reduce the weight of the device. Accelerators control system, which today is in the demo phase, will also be significantly upgraded. This paper describes the stages of the IntraLine accelerator development, its current state and plans for the future R&D work, within the scope of our new Intra-Dose project.

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The experimental and theoretical investigations of damage development and distribution in double-forged tungsten under plasma irradiation-initiated extreme heat loads

., Kukushkin, A., Merola, M., Mitteau, R., Pitts, R. A., Shu, W., Sugihara, M., Riccardi, B., Suzuki, S., & Villari, R. (2013). ITER tungsten divertor design development and qualification program. Fusion Eng. Des., 88, 1798-180. 4. Pitts, R. A., Carpentier, S., Escourbiac, F., Hirai, T., Komarov, V., Kukushkin, A. S., Lisgo, S., Loarte, A., Merola, M., Mitteau, R., Raffray, A. R., Shimada, M., & Stangeby, P. C. (2011). Physics basis and design of the ITER plasma-facing components. J. Nucl. Mater., 415, S957-S964. 5. Cicuttin, A., Crespo, M. L

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Development of the irradiation facility SIBO INRA/Tangier, Morocco by upgrading cobalt-60 in a temporary pool and enhancing safety and control features

Abstract

An automatic control system is one of the most important parts of an irradiation facility. The level of this control is always maintained to comply with safety procedures during routine work in this field. Also sometimes it is limited to the minimum level of regulation required due to economical aspects; some commercial systems are generally made by manufacturers of industrial facilities and considered affordable by irradiators. In some cases specific irradiation facilities tailor their control systems to their needs. For this kind of irradiator the control system can be developed and upgraded according to personal and industrial experiences. These upgrading procedures are also used by others to develop their systems. The objective of this paper is to share a local experience in upgrading security, safety systems and the use of cobalt-60 for the irradiator. It is a composite experiment at SIBO INRA/Tangier, Morocco and concerns the: (i) upgrade of cobalt-60 in a temporary pool in the SIBO irradiator in Tangier. This operation was conducted in collaboration with the International Atomic Energy Agency (IAEA) and was a success story of 2014 according to the general conference of IAEA; (ii) safety and technical upgrade of the system in the SIBO irradiator made in collaboration with IAEA; (iii) installation and upgrade of the security system in accordance with the Global Threat Reduction Programme (GTRP) to reduce the threat of a Radiological Dispersal Device (RDD) in collaboration with The United States Department of Energy’s National Nuclear Security Administration (NNSA).

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Accelerator and detector physics at the Bern medical cyclotron and its beam transport line

References 1. Braccini, S., Ereditato, A., Scampoli, P., & von Bremen, K. (2011). The new Bern cyclotron laboratory for radioisotope production and research. In Proceedings of the Second International Particle Accelerator Conference – IPAC2011 (3618). San Sebastian, Spain. 2. Braccini, S. (2012). The new Bern PET cyclotron, its research beam line, and the development of an innovative beam monitor detector. In Proceedings of the 22nd International Conference on the Application of Accelerators in Research and Industry – CAARI 2012. ForthWorth, Texas

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Studies on magnetron-sputtered zirconium-silicide coatings deposited on zirconium alloy for the enhancement of their high-temperature oxidation resistance

accident tolerant fuel cladding. Metall. Mater. Trans. E , 2 (3), 190–196. DOI: 10.1007/s40553-015-0056-7. 8. Kim, H., Yang, J., Kim, W., & Koo, Y. (2016). Development status of accident-tolerant fuel for light water reactors in Korea. Nucl. Eng. Technol. , 48 , 1–15. https://doi.org/10.1016/j.net.2015.11.011 . 9. Koo, Y., Yang, J., Park, J., Kim, K., Kim, H., Kim, D., Jung, Y., & Song, K. (2014). KAERI’s development of LWR accident-tolerant fuel. Nucl. Technol. , 186 (2), 295–304. http://dx.doi.org/10.13182/NT13-89 . 10. Barrett, K., Bragg

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R&D on divertor plasma facing components at the Institute for Plasma Research

References 1. Merola, M., Danner, W., Pick, M., & the UE ITER Participating Team. (2005). EU R&D on divertor components. Fusion Eng. Des ., 75/79 , 325–331. 2. Linke, J. (2006). Plasma facing materials and components for future fusion devices – development, characterization and performance under fusion specific loading conditions. Phys. Scripta , T123 , 45–53. DOI: 10.1088/0031-8949/2006/T123/006. 3. Merola, M., Palmer, J., & the UE ITER Participating Team. (2006). EU acitivities in preparation of the procurement of the ITER divertor

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SACSESS – the EURATOM FP7 project on actinide separation from spent nuclear fuels

., & Hudson, M. J. (2013). Direct selective extraction of actinides(III) from PUREX raffi nate using a mixture of CyMe4BTBP and TODGA as 1-cycle SANEX solvent. Part III: Demonstration of a laboratory-scale counter-current centrifugal contactor process. Solvent Extr. Ion Exch., 31, 519-537. DOI: 10.1080/07366299.2013.775890. 6. Modolo, G., Asp, H., Schreinemachers, C., & Vijgen, H. (2007). Development of a TODGA based process for partitioning of actinides from a PUREX raffinate. Part I: Batch extraction optimization studies and stability tests. Solvent Extr

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Structure and separation quality of various N- and O-donor ligands from quantum-chemical calculations

-triazine- -bipyridine (BTBP) ligands in actinide/lanthanide complexation and solvent extraction separation - a theoretical approach. Dalton Trans., 44, 2657-2666. DOI: 10.1039/c4dt02657h. 14. Becke, A. D. (1993). A new mixing of Hartree-Fock and local density-functional theories. J. Chem. Phys., 98, 1372-1377. DOI: 10.1063/1.464304. 15. TURBOMOLE V6.4. (2012). A development of University of Karlsruhe and Forschungszentrum Karlsruhe GmbH, 1989-2007, TURBOMOLE GmbH, since 2007. Available from http://www.turbomole.com. 16. Küchle, W., Dolg

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Studies on hydrometallurgical processes using nuclear techniques to be applied in copper industry. I. Application of 64Cu radiotracer for investigation of copper ore leaching

). Leaching of pyrite with hydrogen peroxide in sulphuric acid. Hydrometallurgy, 46, 71-83. 10. Marsden, J., Brewer, B., & Hazen, N. (2003). Copper concentrate leaching developments by Phelps Dodge Corporation. In C. Young, C. Anderson, D. Dreisinger, A. Alfantazi, A. James, & B. Harris (Eds.), Hydrometallurgy 2002. Proceedings of the 5th International Symposium honouring Professor Ian M. Ritchie (Vol. 2, pp. 1429-1446). Warrendale, PA: The Minerals, Metals and Materials Society. 11. Dreisinger, D. (2004). New developments in

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