Nuclear fuel , spent reprocessing

Bond, W. Leuze, R. "Feasibility Studies of the Partitioning of Commercial High-Level Wastes Generated in Spent Nuclear Fuel Reprocessing Annual Progress Report for FY-1974," ORNL-5012, Oak Ridge, Tennesse, January 1975. 

RADIATION EFFECTS IN SPENT NUCLEAR FUEL REPROCESSING 2.1. Purex Process... 

Cougar, M. L. D., Siemer, D. D. Sheetz B. E. 1996. Vitrifiable concrete for disposal of spent nuclear fuel reprocessing waste at I.N.E.L. Materials Research Society Symposium Proceedings, 412, 395-402. 

Pathak, P.N. Prabhu, D.R. Kanekar, A.S. Manchanda, V.K. Recent R D Studies Related to Spent Nuclear Fuel Reprocessing. Presented in Plutonium Futures The Science 2008 Conference held at Dijon, France, July 7-11, 2008. 

The disposition of the radioactive waste resulting from spent nuclear-fuel reprocessing is one of the major problems of nuclear technology. Many of these wastes are high-level (HLW) and present a potential environmental hazard. Because of the expense associated with long-term storage, it is desirable to minimize the volume of radioactive waste and store it as material with maximal chemical stability to avoid the dissipation of radionuclides in the environment. 

Lamouroux, C., Moulin, C., Tabet, J.C., Jankowki, C.K. 2000. Characterization of zirconium complexes of interest in spent nuclear fuel reprocessing by electrospray ionization mass spectrometry. Rapid Commun. Mass Spectrom. 14 1869-1877. 

Takeuchi, M., T. Washiya, H. Nakabayashi, et al. 2005. Engineering Test of Stripping Performance by Multi-Centrifugal Contactor System for Spent Nuclear Fuel Reprocessing. 13th International Conference on Nuclear Engineering, May 16-20, Beijing, China. 

In fact, the first description of such a scheme, involving the application of SFE to spent nuclear fuel reprocessing, appeared shortly after publication of these results. Specifically, Smart et al.43 outlined two possible approaches to SC-C02-based reprocessing. In the first, dubbed the wet SF-PUREX process, SC-C02 merely serves as a replacement for the organic solvent (i.e., a normal paraffinic hydrocarbon) used in... 

A notable exception to the above is the airborne effluent from spent nuclear fuel reprocessing and from tritium production. In this case, iodine-131 volatilizes from fuel reprocessing and must be removed by passing the... 

Nuclear fuel cycle for Russian ship spent nuclear fuel reprocessing or direct disposal... 

Nuclear reactor waste and accidental releases such as the Chernobyl accident in the Ukraine lelease some cesium-137 to the environment. Spent nuclear fuel reprocessing plant wastes may introduce small amounts to the environment. However, the U.S. does not currently reprocess spent nuclear fuel. 

Ryazanov, B.G. (1996) Basic Principles and Nuclear Criticality Safety System in Facilities of Nuclear Industry of MINATOM, Russia, Russian-Chinese workshop on nuclear safety in spent nuclear fuel reprocessing, Beijing Nuclear Design Institute, Beijing, May 24-31. 

The scope of the thesis is to study and develop small-scale processes for ionic liquid-based extractions that can intensify the liquid-liquid separations of the spent nuclear fuel reprocessing cycle. In addition, modeUing methodologies are proposed to evaluate the applicability of the small-scale extractors in reprocessing large volumes of nuclear waste in industrial scale. 

Springer International Publishing Switzerland 2015 D.A. Tsaoulidis, Studies of Intensified Small-scale Processes for Liquid-Liquid Separations in Spent Nuclear Fuel Reprocessing, Springer Theses, DOI 10.1007/978-3-319-22587-6 2... 

Hydrodynamics, pressure drop, and mass transfer during liquid-liquid flows were investigated in two different systems, viz. in glass microchannels with circular cross section of 0.2 mm ID (Fig. 3.3a, b) using an ionic liquid and deionised water, and in Teflon channels of different sizes, i.e. 0.2-2 mm ID (Fig. 3.3c) using either different TBP/ionic liquid mixtures (30 %, v/v) (Table 3.2) and aqueous nitric acid solutions, relevant to spent nuclear fuel reprocessing, or ionic Uquid and deionised water. The internal diameter of the microchannels was measured using a microscope (Nikon Eclipse ME 600). 

In this chapter the mass transfer during liquid-liquid plug flow in small channels is presented. The extraction of dioxom-anium(Vl) ions from nitric acid solutions into TBP/IL mixtures (Table 3.2), relevant to spent nuclear fuel reprocessing was investigated. A schematic of the experimental set-up used for the extraction of dioxouranium(VI) ions from nitric acid solutions by TBP dissolved in ionic hquids is depicted in Fig. 3.2 (Sect. 3.4). 

The last stage of the experimental part of this research involved extractions of dioxouranium(VI) ions from nitric acid solutions into TBP/IL mixtures (30 %, v/v), relevant to spent nuclear fuel reprocessing. The effects of channel size, ionic liquid type, initial nitric acid concentration, mixture velocity, flow rate ratio, and residence time on the extraction performance of the contactor were studied. The extraction experiments were carried out in Teflon capillaries with internal diameter ranging from 0.5 to 2 mm. The results were also compared to those obtained from equilibrium experiments. 

Tsaoulidis D., Dore V., Angeli, P., 2012. MicroChannel extractions using ionic liquids for spent nuclear fuel reprocessing. In proceedings of the 12th International Conference on Microreaction Technology, 20-22 February, Lyon, France... 

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