Relevant bibliographies by topics / Reactor fuel reprocessing. Transuranium elements

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Academic literature on the topic 'Reactor fuel reprocessing. Transuranium elements'

Author: Grafiati
Published: 4 June 2021
Last updated: 10 February 2022

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Journal articles on the topic "Reactor fuel reprocessing. Transuranium elements"

1

Schwenk-Ferrero, A. "German Spent Nuclear Fuel Legacy: Characteristics and High-Level Waste Management Issues." Science and Technology of Nuclear Installations 2013 (2013): 1–11. http://dx.doi.org/10.1155/2013/293792.

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Germany is phasing-out the utilization of nuclear energy until 2022. Currently, nine light water reactors of originally nineteen are still connected to the grid. All power plants generate high-level nuclear waste like spent uranium or mixed uranium-plutonium dioxide fuel which has to be properly managed. Moreover, vitrified high-level waste containing minor actinides, fission products, and traces of plutonium reprocessing loses produced by reprocessing facilities has to be disposed of. In the paper, the assessments of German spent fuel legacy (heavy metal content) and the nuclide composition o
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2

Hunter, Regina L. "Some Materials Concerns in Nuclear Waste Management." MRS Bulletin 17, no. 3 (1992): 43–45. http://dx.doi.org/10.1557/s0883769400040847.

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The U.S. Environmental Protection Agency (EPA) has determined that deep geologic disposal is appropriate for three types of radioactive waste generated in the United States: spent fuel, high-level waste, and transuranic waste. Spent fuel is nuclear fuel that has been discharged from a reactor after irradiation. High-level waste (HLW) is the highly radioactive material that remains after the reprocessing of spent fuel to recover uranium or plutonium. Transuranic (TRU) waste is any waste material contaminated with more than 100 nCi/g of elements having atomic numbers greater than 92 and half-liv
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3

Rodrigues, Davide, Gabriela Durán-Klie, and Sylvie Delpech. "Pyrochemical reprocessing of molten salt fast reactor fuel: focus on the reductive extraction step." Nukleonika 60, no. 4 (2015): 907–14. http://dx.doi.org/10.1515/nuka-2015-0153.

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Abstract The nuclear fuel reprocessing is a prerequisite for nuclear energy to be a clean and sustainable energy. In the case of the molten salt reactor containing a liquid fuel, pyrometallurgical way is an obvious way. The method for treatment of the liquid fuel is divided into two parts. In-situ injection of helium gas into the fuel leads to extract the gaseous fission products and a part of the noble metals. The second part of the reprocessing is performed by ‘batch’. It aims to recover the fissile material and to separate the minor actinides from fission products. The reprocessing involves
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4

Malmbeck, Rikard, Daniel Magnusson, Stéphane Bourg, et al. "Homogenous recycling of transuranium elements from irradiated fast reactor fuel by the EURO-GANEX solvent extraction process." Radiochimica Acta 107, no. 9-11 (2019): 917–29. http://dx.doi.org/10.1515/ract-2018-3089.

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Abstract The EURO-GANEX process was developed for co-separating transuranium elements from irradiated nuclear fuels. A hot flow-sheet trial was performed in a counter-current centrifugal contactor setup, using a genuine high active feed solution. Irradiated mixed (carbide, nitride) U80Pu20 fast reactor fuel containing 20 % Pu was thermally treated to oxidise it to the oxide form which was then dissolved in HNO3. From this solution uranium was separated to >99.9 % in a primary solvent extraction cycle using 1.0 mol/L DEHiBA (N,N-di(2-ethylhexyl)isobutyramide in TPH (hydrogenated tetrapropene
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Hudgens, Claude R. "Sampling and Data-Taking Strategies in X-Ray Fluorescence Assay of Low S/N Solutions." Advances in X-ray Analysis 29 (1985): 485–92. http://dx.doi.org/10.1154/s0376030800010612.

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This project was Initiated for the purpose of demonstrating the feasibility of on-line x-ray fluorescence (XRF) analysis for the nondestructive assay of fissile elements (SNM) in reactor fuel reprocessing (dlssolver) solutions, using wavelength dispersive x-ray fluorescence analysis because of its high immunity to the intense gamma emissions of the solutions. A prime objective of this project was the identification and dimensioning of.the parameters critical to XRF assays of high accuracy. The concepts presented herein, though directed primarily to assay of solutions with emphasis on low signa
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Hakobyan, David A., and Victor I. Slobodchuk. "Temperature conditions in the RBMK spent fuel pool in the event of disturbances in its cooling mode." Nuclear Energy and Technology 7, no. 1 (2021): 9–13. http://dx.doi.org/10.3897/nucet.7.64363.

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The problems of reprocessing and long-term storage of spent nuclear fuel (SNF) at nuclear power plants with RBMK reactors have not been fully resolved so far. For this reason, nuclear power plants are forced to search for new options for the disposal of spent fuel, which can provide at least temporary SNF storage. One of the possible solutions to this problem is to switch to compacted SNF storage in reactor spent fuel pools (SFPs). As the number of spent fuel assemblies (SFAs) in SFPs increases, a greater amount of heat is released. In addition, no less important is the fact that a place for e
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Freis, D., D. Bottomley, J. Ejton, W. de Weerd, H. Kostecka, and E. H. Toscano. "Postirradiation Testing of High Temperature Reactor Spherical Fuel Elements Under Accident Conditions." Journal of Engineering for Gas Turbines and Power 132, no. 4 (2010). http://dx.doi.org/10.1115/1.3094020.

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A new furnace for accident condition testing of spherical high temperature reactor fuel elements has been installed and now operates in the hot cells of the Institute for Transuranium Elements (ITU) Karlsruhe. The recent apparatus was constructed on the basis of a former development by Forschungszentrum Jülich (Schenk, Pitzer, and Nabielek, 1988, “Fission Product Release Profiles From Spherical HTR Fuel Elements at Accident Temperatures,” Jülich Report No. 2234), where it was named KüFA, the German acronym for cold finger apparatus. In a preceding publication (Kostecka, Ejton, de Weerd, and To
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Serrano-Purroy, Daniel, Birgit Christiansen, J. P. Glatz, R. Malmbeck, and G. Modolo. "Towards a DIAMEX process using high active concentrate. Production of genuine solutions." Radiochimica Acta 93, no. 6 (2005). http://dx.doi.org/10.1524/ract.93.6.357.65645.

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SummaryThe efficiency of Minor Actinides (MA) recovery in the DIAMEX process has already been demonstrated using High Active Raffinate (HAR). The next step aims at the demonstration of reprocessing from High Active Concentrate (HAC) as feed, in view of an industrial application. The volume reduction would reduce the size of the installation to be used and thereby the costs of the process. The first step towards the demonstration of a DIAMEX process using HAC is the production of the genuine solutions. In the hot cell facility of ITU (Institute for Transuranium Elements), a HAR solution has bee
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Dissertations / Theses on the topic "Reactor fuel reprocessing. Transuranium elements"

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Brown, M. Alex. "Aqueous complexation of citric acid and DTPA with selected trivalent and tetravalent f-elements." Thesis, 2012. http://hdl.handle.net/1957/35947.

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Carboxylic acids have played an important role in the field of actinide (An) and lanthanide (Ln) separations and the reprocessing of irradiated nuclear fuel. Recent bench-scale experiments have demonstrated that 3-carboxy-3-hydroxypentanedioic acid (citric acid) is a promising aqueous complexant that can effectively aid in the separation of transition metals from f-element mixtures. Furthermore, citric acid was found to be a suitable buffer for the nitrogen donating ligand diethylenetriamine-N,N,N',N'',N''-pentaacetic acid (DTPA) which has a higher complexation affinity for An over Ln. The com
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Books on the topic "Reactor fuel reprocessing. Transuranium elements"

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Office, General Accounting. Nuclear waste: DOE's Hanford spent nuclear fuel storage project : cost, schedule, and management issues : report to the Chairman, Committee on Commerce, House of Representatives. U.S. General Accounting Office, 1999.

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Office, General Accounting. Nuclear waste: Challenges to achieving potential savings in DOE's high-level waste cleanup program : report to the chairman, Subcommittee on Oversight and Investigations, Committee on Energy and Commerce, House of Representatives. U.S. General Accounting Office, 2003.

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Office, General Accounting. Nuclear waste: Uncertainties about opening Waste Isolation Pilot Plant : report to Congressional requesters. The Office, 1996.

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4

Office, General Accounting. Nuclear waste: Unresolved issues concerning Hanford's waste management practices : report to Congressional requesters. The Office, 1987.

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Office, General Accounting. Nuclear waste: Department of Energy's Hanford Tank Waste Project-- schedule, cost, and management issues : report to Congressional requesters. The Office, 1998.

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Office, General Accounting. Nuclear waste: Impediments to completing the Yucca Mountain repository project : report to Congressional committees. The Office, 1997.

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7

Office, General Accounting. Nuclear waste: Foreign countries' appproaches to high-level waste storage and disposal : report to the Honorable Richard H. Bryan, U.S. Senate. The Office, 1994.

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Office, General Accounting. Nuclear waste: DOE's management and organization of the Nevada Repository Project : report to the Chairman, Subcommittee on Investigations and Oversight, Committee on Science, Space, and Technology, House of Representatives. The Office, 1994.

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9

Office, General Accounting. Nuclear waste: Department of Energy's project to clean up Pit 9 at Idaho Falls is experiencing problems : report to the Committee on Commerce, House of Representatives. The Office, 1997.

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10

Office, General Accounting. Nuclear waste: Comprehensive review of the disposal program is needed : report to the Congress. U.S. General Accounting Office, 1994.

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Book chapters on the topic "Reactor fuel reprocessing. Transuranium elements"

1

Goldstein, Inge F., and Martin Goldstein. "Childhood Leukemia Near Nuclear Plants." In How Much Risk? Oxford University Press, 2002. http://dx.doi.org/10.1093/oso/9780195139945.003.0009.

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In 1983 a television crew was making a documentary film about the health of the employees of a nuclear fuels reprocessing plant in England on the coast of the Irish Sea. This plant had previously been the site of a facility for the production of plutonium for nuclear weapons until it was converted to fuels processing after a fire in the reactor in 1957, during which there had been some release of radioactive material to the environment. The crew, filming in a town called Seascale 3 kilometers from the plant, where a number of the employees lived, was shocked to learn from the townspeople that there had been a surprising number of cases of leukemia among their children. Childhood leukemia is a rare disease, but in this small town there had been five cases in the preceding few years, ten times the number of cases that would have been expected from the average rate elsewhere in Great Britain. The focus of the film was changed from the health of the staff of the nuclear facility to the childhood leukemia in Seascale. Shown on television later that year, it aroused national attention and concern, making its points forcefully with shots of rapidly clicking Geiger counters in the neighborhood of the plant, claims that the coastline there is “the most radioactive environment on earth,” interviews with the anguished parents of sick or deceased children, reports of cows on neighboring farms born with malformations, and scenes of children playing on the beach with the smokestacks of the plant in the immediate background. It also reported that there had been some 300 other accidents at the plant in which radiation had been released, though the amounts were all of lesser magnitude than in the 1957 fire. The process for recovering plutonium from spent fuel from power plants does not recover all the plutonium, and some has to be disposed of as waste, along with other radioactive elements. Those responsible for the design of the plant had made the decision, based on both economic considerations and what was then known about the health hazards of radiation, to discharge much of this radioactive waste into the Irish Sea.
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Conference papers on the topic "Reactor fuel reprocessing. Transuranium elements"

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Freis, D., D. Bottomley, J. Ejton, W. de Weerd, H. Kostecka, and E. H. Toscano. "Post Irradiation Testing of High Temperature Reactor Spherical Fuel Elements Under Accident Conditions." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58203.

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A new furnace for accident condition testing of spherical High Temperature Reactor (HTR) fuel elements has been installed and is now operating in the Hot Cells of the Institute for Transuranium Elements (ITU) Karlsruhe. The recent apparatus was constructed on the basis of a former development by Forschungszentrum Ju¨lich (FzJ) [Schenk 1988] where it was named Ku¨FA, the German acronym for cold finger apparatus. In a preceding publication [Toscano 2004] the general concept and details of the device were described. The present paper reports on the first operation under hot conditions, the calibr
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Freis, D., P. D. Bottomley, J. P. Hiernaut, J. Y. Colle, J. Ejton, and W. de Weerd. "Post Irradiation Examination of HTR Fuel at ITU Karlruhe." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58329.

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In the last years considerable efforts have been made at the Institute for Transuranium Elements (ITU) in order to reestablish European knowledge and ability in safety testing of irradiated high temperature reactor (HTR) Fuel Elements. In the framework of the 6th European framework programme a cold finger apparatus (Ku¨FA) furnace, formerly installed at FZ-Ju¨lich (FzJ), has been installed in a hot cell at ITU [Freis 2008] in order to test fission product release under high temperature and non-oxidising conditions. Several analytical methods (e.g. Gamma-spectrometry, mass-spectrometry) have be
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Pokhitonov, Yu, V. Romanovski, and P. Rance. "Distribution of Palladium During Spent Fuel Reprocessing." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4766.

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The principal purpose of spent fuel reprocessing consists in the recovery of the uranium and plutonium and the separation of fission products so as to allow re-use of fissile and fertile isotopes and facilitate disposal of waste elements. Amongst the fission products present in spent nuclear fuel of Nuclear Power Plants (NPPs,) there are considerable quantities of platinum group metals (PGMs): ruthenium, rhodium and palladium. Given current predictions for nuclear power generation, it is predicted that the quantities of palladium to be accumulated by the middle of this century will be comparab
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Aoshima, Atsushi, Shigehiko Miyachi, Takashi Suganuma, and Shinichi Nemoto. "Renovation of Chemical Processing Facility for Development of Advanced Fast Reactor Fuel Cycle System in JNC." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22512.

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The CPF had 4 laboratories (operation room A, laboratory A, laboratory C and analysis laboratory) in connection with reprocessing technology. The main laboratory, operation room A, has 5 hot cells. Since equipments in the main cell had been designed for small-scale verification of existing reprocessing steps, it was hardly able to respond flexibly to experimental studies on advanced technology. It was decided to remodel the cell according to the design that was newly laid out in order to ensure the function and space to conduct various basic tests. The other laboratories had no glove boxes for
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Chen, Guang Jun, Yu Lin Cui, Guo Guo Zhang, and Hong Jun Yao. "The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29632.

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With an increased population and an increasing demand for power, nuclear power has attracted an increasing attention and mass nuclear power plant have been built in different countries in the past several decades. At present, about ten thousands ton spent fuels are discharged from nuclear power plant every year and the estimated capacity will approximately add up to 5×105 ton. Therefore, spent fuel reprocessing, by which the co-extraction and separation as well as purification of Uranium and Plutonium could be realized and ensure the recycle of uranium resources and the management of nuclear w
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Guittonneau, Fabrice, Abdesselam Abdelouas, Bernd Grambow, Manoe¨l Dialinas, and Franc¸ois Cellier. "New Methods for HTR Fuel Waste Management." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58112.

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Considering the need to reduce waste production and greenhouse emissions by still keeping high energy efficiency, various 4th generation nuclear energy systems have been proposed. As far as graphite moderated reactors are concerned, one of the key issues is the large volumes of irradiated graphite encountered (1770 m3 for fuel elements and 840 m3 for reflector elements during the lifetime (60 years) of a single reactor module [1]). With the objective to reduce volume of waste in the HTR concept, it is very important to be able to separate the fuel from low level activity graphite. This require
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Sach, Udo, Goswin Schreck, Max Ritter, and Jean-Pierre Wenger. "High-Level-Waste and Spent Fuel Storage in Switzerland." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1173.

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Abstract At present, Switzerland has no final repository for radioactive wastes. Very early, the Swiss nuclear power plant operators were aware of the necessity to expand interim storage capacity for spent fuel elements and operational wastes. Already in 1991, Nordostschweizerische Kraftwerke AG (NOK) therefore started building a reactor-site interim storage facility (ZWIBEZ) at its Beznau power plant site. Moreover, as early as in 1990, “ZWILAG Zwischenlager Würenlingen AG”, a company established by the nuclear power plant operators had initiated the licensing procedure for a central interim
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Andrello, Concettina, Daniel Freis, Rosa Lo Frano, Dimitri Papaioannou, and Fabienne Delage. "Characterization of FUTURIX-FTA Irradiated Nuclear Fuel Samples." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67252.

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The amount of spent fuel and high-level waste already available, and which will be produced by the future NPPs operation, calls for the evaluation of any possible technological solution that could minimize the burden of their disposal: reduction of Minor Actinide (MA) content, in addition to the radiotoxicity and radioactivity, and of the generated thermal load (decay heat). In this context, R&D efforts currently focus on the development of methodologies and technical solutions for Partitioning and Transmutation. MAs and long-lived fission products are in fact the main contributors to the
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Morris, Jenny, Stephen Wickham, Phil Richardson, Colin Rhodes, and Mike Newland. "Contingency Options for the Dry Storage of Magnox Spent Fuel in the UK." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16330.

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The UK Nuclear Decommissioning Authority (NDA) is responsible for safe and secure management of spent nuclear fuel. Magnox fuel is held at some Magnox reactor sites and at Sellafield where it is reprocessed using a number of facilities. It is intended that all Magnox fuel will be reprocessed as described in the published Magnox Operating Programme (MOP) [1]. In the event, however, that a failure occurs within the reprocessing plant, the NDA has initiated a programme of activities to explore alternative contingency options for the management of wetted Magnox spent fuel. Magnox fuel comprises me
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