Relevant bibliographies by topics / Thorium iv oxides

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  1. Journal articles
  2. Dissertations / Theses
  3. Conference papers

Academic literature on the topic 'Thorium iv oxides'

Author: Grafiati
Published: 4 June 2021
Last updated: 3 February 2022

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Journal articles on the topic "Thorium iv oxides"

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Reiller, Pascal, Valérie Moulin, Florence Casanova, and Christian Dautel. "Retention behaviour of humic substances onto mineral surfaces and consequences upon thorium (IV) mobility: case of iron oxides." Applied Geochemistry 17, no. 12 (December 2002): 1551–62. http://dx.doi.org/10.1016/s0883-2927(02)00045-8.

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Casellato, U., D. Fregona, S. Tamburini, P. A. Vigato, and R. Graziani. "Synthesis and characterization of uranyl(VI) and thorium(IV) complexes with phosphine oxides. The crystal structure of UO2(NO3)2(NO2-C6H4Ph2PO)2." Inorganica Chimica Acta 110, no. 1 (July 1985): 41–46. http://dx.doi.org/10.1016/s0020-1693(00)81351-1.

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Lyczko, Krzysztof, Monika Lyczko, Marta Walo, and Janusz Lipkowski. "Conversion of thorium(IV) oxide into thorium(IV) trifluoromethanesulfonate: Crystal structure of thorium(IV) trifluoromethanesulfonate dihydrate." Inorganic Chemistry Communications 24 (October 2012): 234–36. http://dx.doi.org/10.1016/j.inoche.2012.07.024.

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Ryan, Jack L., and Dhanpat Rai. "Thorium(IV) hydrous oxide solubility." Inorganic Chemistry 26, no. 24 (December 1987): 4140–42. http://dx.doi.org/10.1021/ic00271a038.

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Van den Bossche, G., J. Rebizant, M. R. Spirlet, and J. Goffart. "Structure of tetrachlorotris(triphenylphosphine oxide)thorium(IV)." Acta Crystallographica Section C Crystal Structure Communications 44, no. 6 (June 15, 1988): 994–96. http://dx.doi.org/10.1107/s0108270188001313.

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6

Bhilare, N. G., and V. M. Shinde. "Extraction studies of thorium(IV) with triphenylphosphine oxide." Journal of Radioanalytical and Nuclear Chemistry Articles 185, no. 2 (December 1994): 243–50. http://dx.doi.org/10.1007/bf02041297.

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Rothe, J., M. A. Denecke, V. Neck, R. Müller, and J. I. Kim. "XAFS Investigation of the Structure of Aqueous Thorium(IV) Species, Colloids, and Solid Thorium(IV) Oxide/Hydroxide." Inorganic Chemistry 41, no. 2 (January 2002): 249–58. http://dx.doi.org/10.1021/ic010579h.

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Knope, Karah E., Monica Vasiliu, David A. Dixon, and L. Soderholm. "Thorium(IV)–Selenate Clusters Containing an Octanuclear Th(IV) Hydroxide/Oxide Core." Inorganic Chemistry 51, no. 7 (March 12, 2012): 4239–49. http://dx.doi.org/10.1021/ic202706s.

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Rothe, J., M. A. Denecke, V. Neck, R. Mueller, and J. I. Kim. "ChemInform Abstract: XAFS Investigation of the Structure of Aqueous Thorium(IV) Species, Colloids, and Solid Thorium(IV) Oxide/Hydroxide." ChemInform 33, no. 14 (May 22, 2010): no. http://dx.doi.org/10.1002/chin.200214007.

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10

Li, Yan, Chunli Wang, Zhijun Guo, Chunli Liu, and Wangsuo Wu. "Sorption of thorium(IV) from aqueous solutions by graphene oxide." Journal of Radioanalytical and Nuclear Chemistry 299, no. 3 (January 23, 2014): 1683–91. http://dx.doi.org/10.1007/s10967-014-2956-x.

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Dissertations / Theses on the topic "Thorium iv oxides"

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Button, Zoe Emily. "The activation of carbon oxides by low valent group IV and thorium complexes." Thesis, University of Sussex, 2012. http://sro.sussex.ac.uk/id/eprint/39489/.

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Following discoveries in our laboratory that mixed-ring uranium(III) complexes reductively couple CO to produce new C-C bonds and transform this small molecule into potentially useful small organic things, further research has taken place into the synthesis, characterisation and reactivity of the zirconium, hafnium and thorium analogues. The first part of this thesis describes the preparation of the novel zirconium(IV) and hafnium(IV) mixed-sandwich chloride complexes using sterically demanding cyclopentadienyl and cyclooctatetraenyl ligands, and their subsequent reduction into the desired low valent M(III) compounds. The second part considers the reaction between carbon oxides and three different zirconium(III) complexes in which differently substituted cyclopentadienyl ligands are employed. Reaction with CO generated two novel complexes that displayed C-C bond formation, with the products influenced by the sterics of the systems. Reaction with CO2 produced products resulting from reduction and/or reductive disproportionation of CO2, which were independent of the steric bulk of the cyclopentadienyl ligand. The third and final part of the thesis considers the synthesis of two novel mixed-ring thorium(IV) halide species, before a description of their in situ reduction in the presence of CO2 to yield products different to those previously described in this work. The reactivity illustrated here demonstrates a new approach to the reductive coupling of CO via characterised zirconium(III) complexes and provides insight into the reactivity of a transient thorium(III) sandwich complex.
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Lamotte, Jean. "Etude par spectroscopie infrarouge des proprietes superficielles de la thorine et des especes adsorbees resultant de l'interaction co + h : :(2)." Caen, 1987. http://www.theses.fr/1987CAEN2047.

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Conference papers on the topic "Thorium iv oxides"

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Villamere, Bryan, Leyland J. Allison, Lisa Grande, Sally Mikhael, Adrianexy Rodriguez-Prado, and Igor Pioro. "Thermal Aspects for Uranium Carbide and Uranium Dicarbide Fuels in Supercritical Water-Cooled Nuclear Reactors." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75990.

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SuperCritical Water-cooled Reactors (SCWRs) are a Generation IV nuclear reactor concept. Two main SCWR design concepts are Pressure-Vessel (PV) type and Pressure-Tube (PT) type reactors. SCWRs would use light-water coolant at operating parameters set above the critical point of water (22.1 MPa and 374°C). A reason for moving from current Nuclear Power Plant (NPP) designs to SCW NPP designs is that a SCW NPP will have a thermal efficiency of 45 to 50%, a remarkable improvement from the current 30–35%. SCWRs have another added benefits such as a simplified flow circuit in which steam generators, steam dryers, steam separators, etc. can be eliminated. Canada is in the process of conceptualizing an SCW CANDU reactor. This concept refers to a 1200-MWel horizontal pressure-tube type reactor with the following operating parameters: a pressure of 25 MPa, an inlet temperature of 350°C and an outlet temperature of 625°C. Materials and nuclear fuel must be able to withstand these extreme conditions. In general, the primary choice for a fuel is an enriched Uranium Dioxide (UO2). The industry accepted limit for fuel centreline temperature is 1850°C, and previous studies have shown that the fuel centreline temperature of UO2 pellet might exceed this value at certain conditions. Therefore, a thermal conductivity of the fuel must be sufficiently high to transfer large heat flux within a fuel pellet. Also, a sheath material must withstand supercritical pressures and temperatures inside aggressive medium such as supercritical water, so it should be corrosion-resistant, high-temperature and high-yield strength alloy. In general, sheath materials in various SCWR concepts have a temperature design limit up to 850°C. Uranium Carbide and Uranium Dicarbide are excellent fuel choices as they both have higher thermal conductivities compared to conventional nuclear fuels such as uranium oxide, MOX and Thoria. UC and UC2 are high-temperature ceramics. The sheath material being considered is Inconel 600. This Ni-based alloy has high-yield strength and maintains its integrity beyond the design limit of 850°C. To model a generic SCWR fuel channel, a 43-element bundle string was used. In this paper, bulk-fluid, sheath and fuel centreline temperature profiles together with heat transfer coefficient (HTC) profile were calculated along the heated length of a fuel channel. Also, selected thermophysical properties of various nuclear fuels are listed in the present paper.
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Pascoe, Caleb, Ashley Milner, Hemal Patel, Wargha Peiman, Graham Richards, Lisa Grande, and Igor Pioro. "Thermal Aspects of Using Uranium Dicarbide Fuel in an SCWR at Maximum Heat-Flux Conditions." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29974.

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There are 6 prospective Generation-IV nuclear reactor conceptual designs. SuperCritical Water-cooled nuclear Reactors (SCWRs) are one of these design options. The reactor coolant in SCWRs will be light water operating at 25 MPa and up to 625°C, actually at conditions above the critical point of water (22.1 MPa and 374°C, respectively). Current Nuclear Power Plants (NPPs) around the world operate at sub-critical pressures and temperatures achieving thermal efficiencies within the range of 30–35%. One of the major advantages of SCWRs is increased thermal efficiency up to 45–50% by utilizing the elevated temperatures and pressures. SuperCritical Water (SCW) behaves as a single-phase fluid. This prevents the occurrence of “dryout” phenomena. Additionally, operating at SCW conditions allows for a direct cycle to be utilized, thus simplifying the steam-flow circuit. The components required for steam generation and drying can be eliminated. Also, SCWRs have the ability to support hydrogen co-generation through thermochemical cycles. There are two main types of SCWR concepts being investigated, Pressure-Vessel (PV) and Pressure-Tube (PT) or Pressure-Channel (PCh) reactors. The current study models a single fuel channel from a 1200-MWel generic PT-type reactor with a pressure of 25 MPa, an inlet temperature of 350°C and an outlet temperature of 625°C. Since, SCWRs are presently in the design phase there are many efforts in determining fuel and sheath combinations suited for SCWRs. The design criterion to determine feasible material combinations is restricted by the following constraints: 1) The industry accepted limit for fuel centreline temperature is 1850°C, and 2) sheath-material-temperature design limit is 850°C. The primary candidate fuel is uranium dioxide. However; previous studies have shown that the fuel centreline temperature of an UO2 pellet might exceed the industry accepted limit for the fuel centreline temperature. Therefore, investigation on alternative fuels with higher thermal conductivities is required to respect the fuel centreline temperature limit. Sheath (clad) materials must be able to withstand the aggressive SCW conditions. Ideal sheath properties are a high-corrosion resistance and high-temperature mechanical strength. Uranium dicarbide (UC2) is selected as a choice fuel, because of its high thermal conductivity compared to that of conventional nuclear fuels such as UO2, Mixed OXide (MOX) and Thoria (ThO2). The chosen sheath material is Inconel-600. This Ni-based alloy has high-yield strength and maintains its integrity beyond the design limit of 850°C. This paper utilizes a generic SCWR fuel channel containing a continuous 43-element bundle string. The bulk-fluid, sheath and fuel-centreline temperature profiles together with Heat Transfer Coefficient (HTC) profile were calculated along the heated length of a fuel channel at the maximum Axial Heat Flux Profiles (AHFPs).
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