Relevant bibliographies by topics / Uranium hexafluoride

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Uranium hexafluoride'

Author: Grafiati
Published: 4 June 2021
Last updated: 17 June 2025

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Journal articles on the topic "Uranium hexafluoride"

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Nadezhdin, Igor S., and Nikolay S. Krinitsyn. "Harmonization Values of Downloads and Operating Modes of Interconnected Devices Production of Uranium Hexafluoride." Advanced Materials Research 1084 (January 2015): 655–60. http://dx.doi.org/10.4028/www.scientific.net/amr.1084.655.

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The article is devoted to the problem of load agreement of solid-phase components into the fluorination and capture apparatus of two technological of uranium hexafluoride production lines. The article describes the process of developing a model of the horizontal part of the combined type apparatus which was included in the dynamic mathematical model of uranium hexafluoride production. The developed algorithm of load agreement was studied on dynamic mathematical model of uranium hexafluoride production.
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Ezhov, V. K. "Solubility of Uranium Hexafluoride in Liquid Metal Penta- and Hexafluorides." Atomic Energy 123, no. 3 (2018): 173–76. http://dx.doi.org/10.1007/s10512-018-0320-x.

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YATO, Yumio, Osamu SUTO, and Hideyuki FUNASAKA. "Uranium Isotope Exchange between Uranium Hexafluoride and Uranium Pentafluoride." Journal of Nuclear Science and Technology 32, no. 5 (1995): 430–38. http://dx.doi.org/10.1080/18811248.1995.9731728.

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4

Babenko, S., and A. Bad'in. "On the Dose Coefficient of Uranium Hexafluoride." Medical Radiology and radiation safety 66, no. 5 (2021): 11–17. http://dx.doi.org/10.12737/1024-6177-2021-66-5-11-17.

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Introduction: Uranium hexafluoride (UF6, UHF) is a gaseous product containing uranium and fluorine. Once in the air, it interacts with water vapor and produces hydrolysis products that can penetrate the human body and lead to the chemical effects of uranium and fluorine, as well as the radiation effects of uranium on the body. This action can be very strong and therefore serious attention has been paid to its study for a long time.
 Purpose: Quantitative calculation of the radiation effects of uranium on humans and their analysis in the conditions of daily work at nuclear power plants, as well as in emergency situations.
 Material and methods: We consider uranium hexafluoride that appears under certain conditions in the air of the working rooms of some enterprises and describes methods for describing the distribution of UHF hydrolysis products to objects that can sense their effects. All these methods are combined into a single integrated model. The analytical expressions obtained in the framework of this model at various stages are given, which make it possible to calculate the radiation effect of UHF.
 Results: The calculated values of the characteristics of the radiation exposure are given, their analysis is carried out. The conditions are formulated under which there is a danger of serious radiation exposure of uranium hexafluoride to employees of nuclear power plants during everyday work and in emergency situations.
 Conclusion: Based on all the material presented, it is concluded that the constructed mathematical model reliably describes the event in question and allows us to calculate the radiation effect of uranium on humans.
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Vlasov, A. A., E. A. Filippov, L. L. Fadeev, and A. I. Vinnikov. "Safe shipment of uranium hexafluoride." Soviet Atomic Energy 72, no. 2 (1992): 163–64. http://dx.doi.org/10.1007/bf01121092.

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Orlov, Аleksey A., and Roman V. Malyugin. "Way to Obtain Uranium Hexafluoride." Advanced Materials Research 1084 (January 2015): 338–41. http://dx.doi.org/10.4028/www.scientific.net/amr.1084.338.

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The article contains an analytical overview of technologies used for obtaining UF6. The structures of devices for obtaining UF6 have been considered. Their advantages and drawbacks have been outlined. It has been shown that plasma reactors using uranium tetrafluoride as a raw material are the most efficient in obtaining UF6.
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Orlov, Aleksey A., and Roman V. Malyugin. "Methods of Uranium Hexafluoride Purification." Advanced Materials Research 1084 (January 2015): 46–49. http://dx.doi.org/10.4028/www.scientific.net/amr.1084.46.

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The article contains an analytical overview of techniques used for UF6 purification. Structures of respective devices have been considered. Their advantages and drawbacks have been outlined. It has been shown that heat discharge desublimators and multi-chamber devices with two heated walls are the most efficient in UF6 purification.
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Armstrong, D. P., D. A. Harkins, R. N. Compton, and D. Ding. "Multiphoton ionization of uranium hexafluoride." Journal of Chemical Physics 100, no. 1 (1994): 28–43. http://dx.doi.org/10.1063/1.467270.

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Lubnin, S. S., E. V. Maslyukov, and V. A. Palkin. "Optimization of double cascades by the bee colony algorithm for purification of regenerated uranium hexafluoride from isotopes232, 234, 236U." Izvestiya vysshikh uchebnykh zavedenii. Fizika, no. 5 (2022): 56–62. http://dx.doi.org/10.17223/00213411/65/5/56.

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We propose a double cascade scheme for reducing the concentration of232, 234, 236U isotopes in regenerated uranium hexafluoride. In the product of the first ordinary cascade the greatest decrease in the236U /235U mass ratio with enrichment in235U to a concentration of less than 20% is provided. To ensure the required concentrations, a special mode of operation of the stages. In the second ordinary cascade, which is fed by the product of the first, enrichment in isotopes232,234U is performed. The waste flow, purified from232, 234U, is diluted to a concentration of235U less than 5%. A method for calculating the parameters of cascades with stage separation factors corresponding to gas centrifuges is presented. A computational experiment was carried out on its basis. It was shown that the product obtained after dilution with respect to isotopes232, 234U meets the requirements of the ASTM C996-20 specification for the low-enriched commercial grade of uranium hexafluoride. The content of236U in it is several times lower than in the case of direct enrichment of regenerated uranium hexafluoride.
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Semenov, Evgeny V., and Vladimir V. Kharitonov. "Calculation of the cost of enriched uranium products in multi-stream cascades of enrichment process." Nuclear Energy and Technology 9, no. 1 (2023): 19–25. http://dx.doi.org/10.3897/nucet.9.100752.

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Modern uranium enrichment facilities can simultaneously use several raw materials as feed, including natural uranium, regenerated uranium obtained as a result of SNF reprocessing, or depleted uranium (all in the form of uranium hexafluoride). As the output of the separating cascade, several types of enriched uranium product with different levels of enrichment can be fabricated simultaneously. The paper proposes a methodology, absent in literature, for calculating the cost of each enriched uranium product in multi-stream separating cascades. The proposed methodology uses standard definitions of the isotopic value of feed and product stream and the Peierls-Dirac separation potential. Numerical calculations of the cost of enriched uranium products for three production problems are provided as examples of the methodology effectiveness: 1) involvement of depleted uranium hexafluoride (DUHF) in fabrication of enriched uranium product; 2) simultaneous fabrication of two enriched products; 3) use of depleted uranium to reduce the cost of the product with a higher enrichment level out of two (as applied, e.g., to advanced tolerant fuel). It has been shown that partial additions of DUHF as feed for a multi-product separating cascade make it possible to reduce the cost of a product with a higher level of enrichment; with the current market prices for natural uranium and separative work, there is a range of tails assays in which it is more profitable to enrich DUHF rather than natural uranium.
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Dissertations / Theses on the topic "Uranium hexafluoride"

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Freestone, Nigel Phillip. "Purification of uranium hexafluoride by non-aqueous means." Thesis, University of Leicester, 1987. http://hdl.handle.net/2381/33682.

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This work has shown that nitrogen dioxide will selectively remove uranium hexafluoride from a mixture containing the hexafluorides of uranium, molybdenum and tungsten via the formation of nitrylium hexafluorouranate(V). The production of lower uranium fluorides and elemental sulphur or sulphur fluorides from many of the attempted preparations of uranium(VI) thiofluorides was predicted from a thermodynamic study of the stabilities of MC1nF6-n (M = U, Mo, W; n = 1-5), MOnF6-2n' MSnF6-2n (M = U, Mo, W; n = 1 or 2) with respect to decomposition and disproportionation. Sorption of the liquid hexafluorides on various potential sorbents was investigated. Encouraging results were obtained for cryolite. Salts such as ARuF6 (A = K, Rb, NH4) were synthesised by direct interactions between AF and RuF5 in AHF. These reactions were found to require the presence of a polar solvent. It was found that ruthenium pentafluoride in liquid uranium hexafluoride could be removed by the Introduction of trace quantities of water.
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ARAUJO, ENEAS F. de. "Purificacao de hexafluoreto de uranio." reponame:Repositório Institucional do IPEN, 1986. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9876.

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Achour, Mickaël. "Mécanisme de corrosion du fer par UF₆ liquide à 80°C." Thesis, Université Paris-Saclay (ComUE), 2018. http://www.theses.fr/2018SACLS064.

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Le combustible nucléaire utilisé dans les réacteurs actuels doit répondre à une spécification de composition en ²³⁵U différente de celle de l’uranium naturel. Il est alors nécessaire de procéder à un enrichissement en part fissile avant de fabriquer le combustible utilisé en réacteur. Cet enrichissement est réalisé par centrifugation en phase gaz en utilisant l’uranium sous forme d’hexafluorure d’uranium UF₆. Ce composé clé est fabriqué par l’usine COMHUREX à partir de UF₄, et doit répondre à des exigences de pureté, et sa manipulation, à des exigences de sécurité. Cette molécule est très réactive sous forme gazeuse ou liquide et une corrosion du dispositif industriel métallique est constatée. Cette corrosion doit être étudiée afin d’envisager la pollution causée par les produits de corrosion ou encore la durée de vie de l’installation. L’enjeu de cette thèse est de combler les insuffisances de la littérature sur la question de la corrosion par UF₆ liquide à 80°C, qui n’a jusqu’alors pas fait l’objet de recherches publiées. Des équipements adaptés à la réalisation d’essais de corrosion en milieu nucléaire, à 80°C et 3 bars de pression, et des procédures anoxiques d’analyses de ces essais ont dû être mis en place. La réalisation d’essais de corrosion du fer, matériau modèle, par UF₆ liquide à 80°C a ensuite pu être entreprise afin de déterminer la nature des produits de corrosion, la structure de la couche de corrosion et la cinétique de la réaction entre le fer et UF₆ liquide à 80°C. Ces informations ont pu permettre une réflexion sur le mécanisme de corrosion. Ce manuscrit présente le dispositif et la procédure d’essai mise en place permettant la réalisation d’essais de corrosion puis les résultats obtenus. La nature et la structure de la couche de corrosion ont été obtenues grâce aux précautions anoxiques utilisées tout au long des essais réalisés. Deux comportements distincts sont observés. L’origine expérimentale de cette divergence est discutée. La réflexion sur les observations expérimentales, telles que la nature ou les rapports d’épaisseurs des différentes couches, permet de proposer différentes hypothèses sur le mécanisme de corrosion. Un mécanisme de corrosion du fer par UF₆ liquide à 80°C est donc proposé<br>The nuclear fuel used in today’s power plants requires a precise uranium isotope composition which is different from natural uranium. Thus, an enrichment process is required, for which gaseous centrifugation is employed using uranium hexafluoride (UF₆). This compound is obtained by fluorination of UF₄ and its handling is submitted to security issues. This compound is highly reactive, in gaseous or liquid state, and the metallic industrial production setup is corroded, leading to solid residues at process temperatures. This corrosion has to be considered in order to predict both the process efficiency (purity, output) and the resulting industrial issues (setup lifetime, corking). This study aims at understanding liquid uranium hexafluoride corrosion at 80°C, which remains unstudied to this day. A dedicated novel test setup along with adapted analysis precautions have been developed in order to perform reliable experiments and corrosion products identification, since those products and UF₆ are moisture sensitive. This study mostly focused on the corrosion of iron as a model material in liquid UF₆. The experimental results obtained, allowed us to follow the evolution of the structure and the nature of the corrosion layer. Two different kinds of layer have been observed and the experimental origin of this divergence is discussed. With those experimental results, a corrosion mechanism is suggested for the corrosion of iron in liquid uranium hexafluoride at 80°C
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KOMATSU, CINTIA N. "Diretrizes para avaliação do gasto ambiental no ciclo do combustivel nuclear." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11712.

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Harris, Joseph B. "Evacuation and Shelter in Place Modeling for a Release of Uranium Hexafluoride." Digital Commons @ East Tennessee State University, 2014. https://dc.etsu.edu/etd/2351.

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Evacuation and sheltering behaviors were modeled for a hypothetical release of uranium hexafluoride (UF6) from Nuclear Fuel Services (NFS) in Erwin, Tennessee. NFS down-blends weapons grade Cold War-era nuclear fuel material and processes highly-enriched uranium occasionally using UF6 onsite. Risk associated with a chemical release to the surrounding residential population was assessed by running 2 scenarios involving an airborne release of UF6 to compare evacuation and sheltering in place actions as effective survival strategies. Risk is minimal and evacuation is recommended for people within a 2-mile radius of the release point. Shelter in place actions are recommended for all critical facilities that have the potential to be affected by a chemical release plume. Oak Ridge National Laboratory’s Radiological Assessment System for Consequence Analysis and Capacity-Aware Shortest Path Evacuation Routing in conjunction with a geographic information system proved to be valuable technological tools in determining evacuation routing and exposure zones.
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MARCHESINI, PAULO R. de A. "Diagnóstico e sugestões para a gestão do conhecimento aplicada a uma instalação nuclear: a unidade de produção de hexafluoreto de urânio." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11684.

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Downing, Edward Nicolas. "Surface studies of the adsorption and heterogeneous decomposition of UF←6 on well characterised surfaces with reference to U CVD." Thesis, University of Oxford, 1998. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.298233.

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MATTIOLO, SANDRA R. "Diretrizes para implantação de um sistema de gestão ambiental no ciclo do combustível nuclear: estudo de caso da USEXA-CEA." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10169.

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SANTOS, IVAN. "Descomissionamento de uma usina de producao de hexafluoreto de uranio." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11758.

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SANTOS, LAURO R. dos. "Unidade piloto de obtencao do tricarbonato de amonio e uranilo." reponame:Repositório Institucional do IPEN, 1989. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10220.

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Books on the topic "Uranium hexafluoride"

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Board, United States Defense Nuclear Facilities Safety. Integrity of uranium hexafluoride cylinders. Defense Nuclear Facilities Safety Board, 1995.

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Board, United States Defense Nuclear Facilities Safety. Integrity of uranium hexafluoride cylinders. Defense Nuclear Facilities Safety Board, 1995.

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United States. Defense Nuclear Facilities Safety Board. Integrity of uranium hexafluoride cylinders. Defense Nuclear Facilities Safety Board, 1995.

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United States. Defense Nuclear Facilities Safety Board. Integrity of uranium hexafluoride cylinders. Defense Nuclear Facilities Safety Board, 1995.

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Goldstick, Miles. The hex connection: Some problems and hazards associated with the transportation of uranium hexafluoride. Swedish University of Agricultural Sciences, Dept. of Ecology and Environmental Research, 1991.

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Brodsky, Allen. Radiation protection training at uranium hexafluoride and fuel fabrication plants. Division of Radiation Programs and Earth Sciences, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1985.

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McGuire, Stephen A. Chemical toxicity of uranium hexafluoride compared to acute effects of radiation: Final report. Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1991.

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Fisher, D. R. Evaluation of health effects in Sequoyah Fuels Corporation workers from accidental exposure to uranium hexafluoride. Division of Industrial and Medical Nuclear Safety, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 1990.

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Yamate, Kazuki. Rokufukka uran rōei jikoji no kagakuteki eikyō to sono hyōka hōhō: Chemical effects and their evaluation methods for accidental release of Uranium hexafluoride. Genshiryoku Anzen Kiban Kikō, 2013.

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US GOVERNMENT. An Act to Require the Secretary of Energy to Submit to Congress a Plan to Ensure that All Amounts Accrued on the Books of the United States Enrichment Corporation for the Disposition of Depleted Uranium Hexafluoride Will Be Used to Treat and Recycle Depleted Uranium Hexafluoride. U.S. G.P.O., 1998.

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Book chapters on the topic "Uranium hexafluoride"

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Winkelmann, J. "Diffusion of uranium hexafluoride." In Gases in Gases, Liquids and their Mixtures. Springer Berlin Heidelberg, 2007. http://dx.doi.org/10.1007/978-3-540-49718-9_26.

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Hutchinson, J. D., K. Amundson, H. Kistle, et al. "Principles of Singles Neutron Counting." In Nondestructive Assay of Nuclear Materials for Safeguards and Security. Springer International Publishing, 2024. http://dx.doi.org/10.1007/978-3-031-58277-6_16.

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AbstractThis chapter describes the principles of method used in total neutron counting (as distinct from correlated neutron counting described in Chaps. 17 and 18). In this method only the number of neutrons detected is used to make measurements of uranium and plutonium. The chapter describes the typical chain of electronics from the detector to the recording device. There is a discussion of important practical issues in neutron counting such as neutron detector design and efficiency, and background and room return effects. The chapter gives the neutron emission values from spontaneous fission and (α,n) reactions for plutonium oxide and plutonium fluoride of different isotopic compositions as well as the neutron emission from uranium metal, uranium oxide, uranyl fluoride and uranium hexafluoride for depleted, natural and low enriched uranium. The effect of impurities on neutron production is discussed. The neutron transport in the item is discussed with respect to leakage multiplication and spectrum.
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Klapötke, Thomas M. "Laboratory-Scale Synthesis of Gold Trifluoride and Uranium Hexafluoride." In Efficient Preparations of Fluorine Compounds. John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118409466.ch17.

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Fessler, K. Alicia Strange, Patrick E. O’Rourke, Nicholas F. DeRoller, Darrell Simmons, and Steven M. Serkiz. "Use of an Infrared Spectroscopic Method for Isotopic Analysis of Gaseous Uranium Hexafluoride." In The Minerals, Metals & Materials Series. Springer International Publishing, 2021. http://dx.doi.org/10.1007/978-3-030-65249-4_12.

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Goodman, David, Kelly Rowland, Sheriden Smith, Karen Miller, and Eric Flynn. "Non-destructive Examination of Multiphase Material Distribution in Uranium Hexafluoride Cylinders Using Steady-State Laser Doppler Vibrometery." In Structural Health Monitoring, Volume 5. Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-04570-2_9.

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"Uranium Hexafluoride." In Nuclear Juggernaut. Routledge, 2013. http://dx.doi.org/10.4324/9781315066424-10.

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"Uranium Hexafluoride (UF6)." In Gaseous Electronics. CRC Press, 2011. http://dx.doi.org/10.1201/b11492-100.

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"Production of Uranium Hexafluoride." In The History of the Soviet Atomic Industry. CRC Press, 2002. http://dx.doi.org/10.1201/9781482264869-30.

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Hooton, Brian. "The Nuclear Fuel Cycle." In Understanding Nuclear Reactors. Oxford University PressOxford, 2024. http://dx.doi.org/10.1093/oso/9780198902652.003.0009.

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Abstract The nuclear fuel cycle is described, including the distinction between the open cycle and the closed cycle. Mining to create yellow cake, and enrichment by gas centrifuge using uranium hexafluoride (HEX), are explained. Fuel fabrication of uranium oxide pellets completes the front-end of the fuel cycle. The benefits and disadvantages of MAGNOX as a fuel pin cladding are explained. The back-end of the fuel cycle covers spent fuel management, fuel pond storage with the visibility of Cherenkov radiation. A flow sheet covering the plutonium-uranium extraction (PUREX) reprocessing method with mixer settlers is explained. The methods for dealing with high-level waste (HLW), by vitrification, are described. It treats the management of intermediate-level waste (ILW) and low-level waste (LLW).
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Charette, M. A. "Packaging, transport and storage of uranium ore concentrates and uranium hexafluoride." In Safe and Secure Transport and Storage of Radioactive Materials. Elsevier, 2015. http://dx.doi.org/10.1016/b978-1-78242-309-6.00012-5.

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Conference papers on the topic "Uranium hexafluoride"

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Rao, Mukund. "Atmospheric Corrosion Monitoring at the U.S. Department of Energy’s Oak Ridge K-25 Site." In CORROSION 1995. NACE International, 1995. https://doi.org/10.5006/c1995-95239.

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Abstract Depleted uranium hexafluoride (UF6) at the U.S. Department of Energy’s K-25 Site at Oak Ridge, TN has been stored in large steel cylinders which have undergone significant atmospheric corrosion damage over the last 35 years. A detailed experimental program to characterize and monitor the corrosion damage was initiated in 1992. Large amounts of corrosion scale and deep pits are found to cover cylinder surfaces. Ultrasonic wall thickness measurements have shown uniform corrosion losses up to 20 mils (0.5 mm) and pits up to 100 mils (2.5 mm) deep. Electrical resistance corrosion probes, time-of-wetness sensors and thermocouples have been attached to cylinder bodies. Atmospheric conditions are monitored using rain gauges, relative humidity sensors and thermocouples. Long-term (16 years) data are being obtained from mild steel corrosion coupons on test racks as well as attached directly to cylinder surfaces. Corrosion rates have been found to be intimately related to the times-of-wetness, both tending to be higher on cylinder tops due to apparent sheltering effects. Data from the various tests are compared, discrepancies are discussed and a pattern of cylinder corrosion as a function of cylinder position and location is described.
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Lei, Chen, and Wang Ning. "The Evaluation Method of Uranium Hexafluoride Leakage Accident Release Source Term." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67143.

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Uranium hexafluoride is the intermediate material of uranium fuel enrichment process, which is widely used in uranium conversion plant, uranium enrichment plant and nuclear fuel element plant[1]. Because of its active chemical properties and its radioactive and chemical toxicity, great importance should be attached to the uranium hexafluoride release accident. This paper describes the possible leakage scenarios for uranium hexafluoride accident. And the general step of the evaluation for uranium hexafluoride leakage accident release source term is given, as well as an application example for the feed facility of a gaseous diffusion plant.
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Jetter, Heinz, and Linus Werner. "Laser isotope separation of uranium hexafluoride." In Conference on Lasers and Electro-Optics. OSA, 1986. http://dx.doi.org/10.1364/cleo.1986.tui2.

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Lei, Chen, Zhang JianGang, Li GuoQiang, Sun ShuTang, Meng DongYuan, and Wang Ning. "Preliminary Hazard Analysis of Uranium Hexafluoride Accident." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81956.

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Uranium hexafluoride (UF6) accident is a typical accident in the nuclear fuel cycle. It combine radioactive and chemical hazards, so it is necessary to attach great importance to the UF6 accident. This paper analyzed and summarized the possible accident scenarios, causes and consequences, and classified the UF6 accident risk factors, and put forward corresponding preventive and emergency measures. Preliminary hazard analysis of the accident can help us better understand the accident process, so we can takes steps for corresponding risk factors in advance, and prevent it will not be developed into an accident, so than we can obtain the effect of nip in the bud.
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Allison, S. W., D. W. Magnuson, M. R. Cates, et al. "Remote measurement of uranium hexafluoride via fiber optics." In Optical Fiber Sensors. OSA, 1985. http://dx.doi.org/10.1364/ofs.1985.thgg7.

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Shayeganrad, Gholamreza, and Leila Mashhadi. "Remote leak monitoring of gaseous uranium hexafluoride by UVDIAL." In Ultraviolet and Visible Ground- and Space-based Measurements, Trace Gases, Aerosols and Effects VI. SPIE, 2009. http://dx.doi.org/10.1117/12.829585.

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Lutz, Jesse, Daniel Jensen, Joshua Hubbard, and Judit Zador. "Hydrolysis of uranium hexafluoride: mechanism, spectroscopy, and thermochemical kinetics." In Proposed for presentation at the American Chemical Society National Meeting held August 22-26, 2022 in Chicago, IL United States. US DOE, 2022. http://dx.doi.org/10.2172/2004484.

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Zaima, Naoki, Yasuyuki Morimoto, Noritake Sugitsue, and Kazumi Kado. "Uranium Refining and Conversion Plant Decommissioning Project." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40068.

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The uranium refining and conversion plant (URCP) at Ningyo-toge was constructed in 1981 for the purpose of demonstrating on refining and conversion process from yellow cake (or uranium trioxide) to uranium hexafluoride by way of uranium tetrafluoride. For 20 years, 385 tons of natural uranium hexafluoride and 336 tons of reprocessed uranium hexafluoride (approximately) was produced. There are two different type of refining processes in the URCP. One is the wet process by convertig the natural uranium and the other is the dry conversion process for the reprocessed uranium. The dismantling of the dry process facilities began in March, 2008. It was found the large amount of uranium residuals such as wet slurry and powder uranium inside the vessels and pipes. Therefore, we have to take care of the spread of the contamination during dismantling works. The basic strategy concerning plant dismantling were the optimization of the total labor costs and the minimization of the radioactive wastes generated. The dismantling procedure is shown below; i) measuring doserate by using high sensitivity surveymeters, and nuclide identification by using gamma ray spectrometry, ii) estimating uranium mass inventory, iii) planning work force distributions with radiological survey staffs, iv) deciding dismantling methods concretely, v) decontaminating schematically if required, vi) collecting detailed data of working conditions, vi) measuring and classifying contaminated materials, vii) managements of radioactive waste drum and non-contaminated equipment, viii) control for personal exposures. Almost all equipment will be decontaminated except building decontamination it by around 2013FY. In addition, the secondary wastes were also yielded. Few thousands man-days were necessary for this project. The measurement data have not showed the high environmental radiation doserate, generally less than 0.3μSv/h. However, by the trace of the reprocessed uranium, the trans-uranium nuclides such as uranium-232 progenies, Th-228 and Tl-208 were observed. The accumulation of the nuclides which emit high energy gamma rays such as Tl-208 caused radiation exposure. As for the waste disposal, the determination of uranium content must be necessary. We have been now developing the uranium measuring systems with better accuracy. The further tasks imposed by our experiences are summarized the followings; i) minimization and reduction of radioactive wastes, ii) decontamination for the buildings and utilities, iii) wastes disposal. We have to work hard toward the final decommissioning.
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Hongchao, Sun, Li Guoqiang, Zhuang Dajie, et al. "Tests of the Package for the Transport of Natural Uranium Hexafluoride." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82151.

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Several tests has been conducted to illustrating the safety performance of a type of package for the transport of natural uranium hexafluoride meet the requirements of GB11806-2004 (Regulations for the safe transport of radioactive material). The requirements of GB11806-2004 are same with the requirements of IAEA SSR6 (Regulations for the safe transport of radioactive material). These tests include heat, cold, reduced external pressure, increased external pressure, free drop, thermal test. Certification testing was performed on full-scale model and a test plan was developed that identified the specific free drop necessary to evaluate both GB11806 and SSR-6 requirements. A total of two 0.6-m free drops were performed. The leaks were detected after each free drop test. The accelerations were recorded for use in finite element structural analyses. This paper reviews the test planning and results with a discussion of how the test and finite element structural analyses were combined.
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Gerin, I. I., S. T. Penin, and L. K. Chistyakova. "Optical methods for research of uranium hexafluoride under conditions imitating the atmosphere." In SPIE Proceedings, edited by Gelii A. Zherebtsov and Gennadii G. Matvienko. SPIE, 2006. http://dx.doi.org/10.1117/12.675809.

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Reports on the topic "Uranium hexafluoride"

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Fisher, D. R., T. E. Hui, M. Yurconic, and J. R. Johnson. Uranium hexafluoride public risk. Office of Scientific and Technical Information (OSTI), 1994. http://dx.doi.org/10.2172/10182632.

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Armstrong, D. The multiphoton ionization of uranium hexafluoride. Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/5296034.

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Author, Not Given. Uranium hexafluoride: Handling procedures and container descriptions. Office of Scientific and Technical Information (OSTI), 1987. http://dx.doi.org/10.2172/6304596.

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Richards, Jason, Lee Trowbridge, Hal Jennings, Tara Davis, Glenn Fugate, and Michael Singleton. Studies of helium behavior in uranium hexafluoride. Office of Scientific and Technical Information (OSTI), 2024. https://doi.org/10.2172/2498446.

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Armstrong, Donald P. The multiphoton ionization of uranium hexafluoride. Revision 1. Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/10142145.

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Zoller, J. N., R. S. Rosen, and M. A. Holliday. Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 1. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/93560.

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Zoller, J. N., R. S. Rosen, and M. A. Holliday. Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 2. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/93562.

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Dorning, R. E. II. A review of the Model 5A uranium hexafluoride cylinder. Office of Scientific and Technical Information (OSTI), 1989. http://dx.doi.org/10.2172/6076252.

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Barlow, C. R., J. H. Alderson, S. C. Blue, et al. Containment and storage of uranium hexafluoride at US Department of Energy uranium enrichment plants. Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/10174616.

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Bayne, C. K., and W. D. Bostick. Particle size distributions formed by atmospheric hydrolysis of uranium hexafluoride. Office of Scientific and Technical Information (OSTI), 1985. http://dx.doi.org/10.2172/5977560.

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