Relevant bibliographies by topics / Uranium Thorium

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Academic literature on the topic 'Uranium Thorium'

Author: Grafiati
Published: 4 June 2021
Last updated: 6 February 2022

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Journal articles on the topic "Uranium Thorium"

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Anggraini, Mutia, Budi Sarono, Sugeng Waluyo, Rusydi Rusydi, and Sujono Sujono. "Pengendapan Uranium dan Thorium Hasil Pelarutan Slag II." EKSPLORIUM 36, no. 2 (November 30, 2015): 125. http://dx.doi.org/10.17146/eksplorium.2015.36.2.2776.

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Proses peleburan timah menghasilkan limbah berupa slag II dalam jumlah besar. Slag II sebagai terak pada proses peleburan timah masih mengandung beberapa unsur utama antara lain 0,0619% uranium, 0,530% thorium, 0,179% P2O5, dan 6,194% logam tanah jarang (LTJ) oksida total. Berdasarkan fakta tersebut, maka sangat menarik untuk meneliti pengolahan slag II, terutama untuk memisahkan uranium dan thorium yang terkandung di dalamnya. Uranium dan thorium dilarutkan dengan pelarut asam (H2SO4). Recovery pelarutan slag II dari hasil peleburan timah pada kondisi optimum adalah 98,52% uranium, 83,16% thorium, 97,22% fosfat, dan 69,62% LTJ. Uranium, thorium, LTJ, dan fosfat yang telah terlarut diendapkan agar masing-masing unsur terpisah. Faktor yang mempengaruhi kesempurnaan reaksi pada pengendapan antara lain reagen yang digunakan, pH reaksi, suhu, dan waktu. NH4OH digunakan sebagai reagen pengendapan dengan kondisi optimum proses pada pH 4. Suhu dan waktu reaksi tidak mempengaruhi proses. Recovery pengendapan yang dihasilkan adalah 93,84% uranium dan 84,33% thorium. Tin smelting process produces waste in the form of large amount of slag II. Slag II still consist of major elements such as 0.0619% uranium, 0.530% thorium, 0.179% P2O5 and 6.194% RE total oxide. Based on that fact, the processing of slag II is interesting to be researched, particularly in separating uranium and thorium which contained in slag II. Uranium and thorium dissolved using acid reagent (H2SO4). Percentage recovery of uranium, thorium, phosphate and RE oxides by dissolution method are 98.52%, 83.16%, 97.22%, and 69.62% respectively. Dissolved uranium, thorium, phosphat, and RE were each precipitated. The factors which considerable affect the precipitation process are reagent, pH, temperature, and time. NH4OH is used as precipitation reagent, optimum condition are pH 4. Temperature and time reaction did not influence this reaction. Percentage recovery of this precipitation process at optimum condition are 93.84% uranium and 84.33% thorium.
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Lidman, F., C. M. Mörth, and H. Laudon. "Landscape control of uranium and thorium in boreal streams – spatiotemporal variability and the role of wetlands." Biogeosciences Discussions 9, no. 3 (March 13, 2012): 2823–49. http://dx.doi.org/10.5194/bgd-9-2823-2012.

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Abstract. The concentrations of uranium and thorium in ten partly nested streams in the boreal forest region were monitored over a two-year period. Considerable spatiotemporal variations were observed, with little or no correlation between streams. The export of both uranium and thorium varied substantially between the subcatchments, ranging from 1.7 to 30 g km−2 a−1 for uranium and from 3.2 to 24 g km−2 a−1 for thorium. Airborne gamma spectrometry was used to measure the concentrations of uranium and thorium in surface soils throughout the catchment, but could not explain the variability in the export. Instead, the extent of lakes and mires within each subcatchment was found to be a stronger predictor for the transport of uranium and thorium. The results indicate that there is a predictable and systematic accumulation of both uranium and thorium in boreal mires. Approximately 65–80 % of uranium and 55–65 % of thorium entering a mire is estimated to be retained in the peat. Overall, accumulation in mires and other types of wetlands is estimated to decrease the fluxes of uranium and thorium from the boreal forest landscape by 30–40 %. The atmospheric deposition of uranium and thorium was also quantified and its contribution to boreal streams was found to be low compared to weathering.
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Lidman, F., C. M. Mörth, and H. Laudon. "Landscape control of uranium and thorium in boreal streams – spatiotemporal variability and the role of wetlands." Biogeosciences 9, no. 11 (November 23, 2012): 4773–85. http://dx.doi.org/10.5194/bg-9-4773-2012.

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Abstract. The concentrations of uranium and thorium in ten partly nested streams in the boreal forest region were monitored over a two-year period. The investigated catchments ranged from small headwaters (0.1 km2) up to a fourth-order stream (67 km2). Considerable spatiotemporal variations were observed, with little or no correlation between streams. The fluxes of both uranium and thorium varied substantially between the subcatchments, ranging from 1.7 to 30 g km−2 a−1 for uranium and from 3.2 to 24 g km−2 a−1 for thorium. Airborne gamma spectrometry was used to measure the concentrations of uranium and thorium in surface soils throughout the catchment, suggesting that the concentrations of uranium and thorium in mineral soils are similar throughout the catchment. The fluxes of uranium and thorium were compared to a wide range of parameters characterising the investigated catchments and the chemistry of the stream water, e.g. soil concentrations of these elements, pH, TOC (total organic carbon), Al, Si and hydrogen carbonate, but it was concluded that the spatial variabilities in the fluxes of both uranium and thorium mainly were controlled by wetlands. The results indicate that there is a predictable and systematic accumulation of both uranium and thorium in boreal wetlands that is large enough to control the transport of these elements. On the landscape scale approximately 65–80% of uranium and 55–65% of thorium entering a wetland were estimated to be retained in the peat. Overall, accumulation in mires and other types of wetlands was estimated to decrease the fluxes of uranium and thorium from the boreal forest landscape by 30–40%, indicating that wetlands play an important role for the biogeochemical cycling of uranium and thorium in the boreal forest landscape. The atmospheric deposition of uranium and thorium was also quantified, and its contribution to boreal streams was found to be low compared to weathering.
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Islami rad, Seyedeh Zahra, and Reza Gholipour Peyvandi. "Determination of uranium and thorium concentrations in thorium ore sample using artificial neural network and comparison with net area peak method." Radiochimica Acta 106, no. 8 (August 28, 2018): 669–74. http://dx.doi.org/10.1515/ract-2017-2880.

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Abstract In order to determine favorable and different elements in soil, the rapid and accurate methods are required. In this research, simultaneous prediction of thorium and uranium in soil samples was performed via gamma spectrometry. Then, the acquired data were analyzed with artificial neural network (ANN) and net area peak (NAP). Natural soil samples obtained from thorium ore consisting of thorium and uranium were used to train models (ANN and NAP). The techniques were evaluated with respect to prediction ability of uranium and thorium concentrations and robustness. Using proposed ANN and NAP methods, the thorium concentration was predicted with mean relative error percentage less than 8.27% and 9.30%, respectively. Also, uranium concentration just was determined with ANN because the NAP method cannot measure uranium concentration. The performance of the neural network model and NAP technique were compared with the acquired empirical data. The results showed that the neural network can more accurately predict the thorium and uranium concentrations in soil samples.
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Ridantami, Vemi, Bangun Wasito, and Prayitno Prayitno. "PENGARUH TEGANGAN DAN WAKTU PADA PENGOLAHAN LIMBAH RADIOAKTIF URANIUM DAN THORIUM DENGAN PROSES ELEKTROKOAGULASI." Jurnal Forum Nuklir 10, no. 2 (June 8, 2017): 102. http://dx.doi.org/10.17146/jfn.2016.10.2.3494.

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PENGARUH TEGANGAN DAN WAKTU PADA PENGOLAHAN LIMBAH RADIOAKTIF URANIUM DAN THORIUM DENGAN PROSES ELEKTROKOAGULASI. Metode pengolahan limbah radioaktif dengan metode fisika dan kimia yang telah dilakukan dinilai kurang efektif, memerlukan waktu yang lama dan biaya yang mahal. Untuk itu perlu dilakukan pengolahan limbah uranium dan thorium dengan proses elektokoagulasi untuk memisahkan uranium dan thorium dalam limbah cair. Limbah yang digunakan memiliki kadar kontaminan Uranium dan Thorium 500 mg/liter. Pengolahan dilakukan dengan tegangan 10V, 12,5V, dan 15 volt dengan waktu 10,20,30,40,50,dan 60 menit dengan elektroda alumunium. Hasil penelitian menunjukkan effisiensi penurunan kontaminan terbaik pada pengolahan ini diperoleh pada kondisi 12,5V dan waktu 60 menit untuk uranium, dengan efisiensi sebesar sebesar 97,2 %, dan thorium pada 12,5 V waktu 30 menit dengan efisiensi penurunan sebesar 99,6 % .
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Ngadenin, Ngadenin, and Adhika Junara Karunianto. "Identifikasi Keterdapatan Mineral Radioaktif pada Granit Muncung Sebagai Tahap Awal untuk Penilaian Prospek Uranium dan Thorium di Pulau Singkep." EKSPLORIUM 37, no. 2 (December 19, 2016): 63. http://dx.doi.org/10.17146/eksplorium.2016.37.2.3101.

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ABSTRAKPulau Singkep adalah bagian dari jalur timah Asia Tenggara, yang salah satu litologinya tersusun oleh granit Muncung. Keberadaan granit tersebut memungkinkan adanya cebakan mineral radioaktif yang prospek terhadap uranium dan thorium. Penelitian ini bertujuan untuk mengidentifikasi keterdapatan mineral radioaktif pada granit Muncung sebagai tahap awal untuk penilaian prospek uranium dan thorium di Pulau Singkep. Metoda yang digunakan adalah pengambilan sampel batuan granit, analisis petrografi sampel granit Muncung, analisis kadar uranium dan thorium serta analisis butir sampel konsentrat dulang yang diambil di wilayah granit Muncung. Mineral radioaktif pada granit Muncung adalah monasit dan zirkon sedangkan pada konsentrat dulang adalah monasit, zirkon, dan senotim. Persentase monasit dalam konsentrat dulang adalah 1,1 – 59,53 %, zirkon 0,68 –55,07 % dan senotim 0,39 – 3,54 %. Kadar uranium dalam konsentrat dulang adalah 30 – 1.346 ppm dan kadar thorium 557 – 13.200 ppm. Disimpulkan bahwa daerah di sekitar granit Muncung dianggap cukup prospek uranium dan thorium dan dapat dikembangkan ke tahapan eksplorasi lebih detail. ABSTRACTSingkep Island is part of Southeast Asia tin belt, which is one of the lithologies, composed of granite Muncung. Existence of granite allows formed deposits of radioactive minerals that prospect of the uranium and thorium. This research goal is to identify radioactive minerals occurrences on granit Muncung in the initial stage for prospect assessment of uranium and thorium in Singkep Island. The Methodologies are granite sampling, petrography analysis of Muncung granite samples, uranium and thorium content analysis and grain size analysis of pan concentrate samples. Radioactive minerals in Muncung granite are monazite and zircon, while in pan concentrate they are monazite, zircon, and xenotime. The percentage of monazite, zircon, and xenotime in the pan concentrate are 1.1–59.53 %, 0.68–55.07 %, and 0.3–3.54 % respectively. The uranium and thorium content in the pan concentrate are 30–1,346 ppm and 557–13,200 ppm respectively. It concluded that the area around the Muncung granite considered prospect for uranium and thorium, and possibly developed into more detailed exploration stage.
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Omnia M., Ali, El-Kashif H.H., Sayed S.A., and Shalabi M.E.H. "The Removal of Uranium and Thorium from Aqueous Solutions Onto by-pass Cement Dust (BCD)." Eurasian Chemico-Technological Journal 11, no. 2 (April 6, 2016): 105. http://dx.doi.org/10.18321/ectj303.

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<p>The adsorption behavior of uranium and thorium from aqueous solutions by By-pass cement dust (BCD) has been investigated by a batch technique. The uranium and thorium adsorption on BCD was studied as a function of initial concentration, weight of BCD, pH, shaking time and temperature. The uptake of uranium and thorium at the determined optimum conditions follows Freundlich isotherm. The adsorption control of both thorium and uranium are first order and uptake energy of activation E<sub>a</sub> =10 and 15 kJ/mol for thorium and uranium respectively. Thermodynamic parameters such as ΔH<sup>o</sup>, ΔS<sup>o</sup> and ΔG<sup>o</sup> were also investigated.</p>
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Mintz Testa, Bridget. "Thunder on the Horizon." Mechanical Engineering 139, no. 02 (February 1, 2017): 38–43. http://dx.doi.org/10.1115/1.2017-feb-2.

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This article discusses the advantageous usage of thorium-based breeder reactors in the nuclear industry. Since thorium is more abundant than uranium and can be turned into fuel without the enrichment process needed to concentrate U-235, experts believe that the thorium fuel cycle could be more sustainable than the uranium cycle. The addition of thorium to the fluid salt helps reduce uranium consumption. ThorCon, a Florida-based nuclear power startup, has developed the ThorCon reactor that will be breeding some of its own fuel by irradiating thorium. Thorium is about three times more abundant than uranium, and all of it can be used to create a fuel source for nuclear reactors. Thor Energy is developing two different families of thorium-based fuels with both U-235 and Pu-239 as the fissile driver material. The interest in thorium suggests that it is going to take an unconventional approach to lead to the much-anticipated Nuclear Renaissance.
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Reda, Sonia M., Ibrahim M. Gomaa, Ibrahim I. Bashter, and Esmat A. Amin. "Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library." Science and Technology of Nuclear Installations 2021 (April 14, 2021): 1–9. http://dx.doi.org/10.1155/2021/8838097.

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In this paper, neutronic calculations and the core analysis of the VVER-1000 reactor were performed using MCNP6 code together with both ENDF/B-VII.1 and ENDF/B-VIII libraries. The effect of thorium introduction on the neutronic parameters of the VVER-1000 reactor was discussed. The reference core was initially filled with enriched uranium oxide fuel and then fueled with uranium-thorium fuel. The calculations determine the delayed neutron fraction βeff, the temperature reactivity coefficients, the fuel consumption, and the production of the transuranic elements during reactor operation. βeff and the Doppler coefficient (DC) are found to be in agreement with the design values. It is found that the core loaded with uranium and thorium has lower delayed neutron fraction than the uranium oxide core. The moderator temperature coefficients of the uranium-thorium core are found to be higher than those of the uranium core. Results indicated that thorium has lower production of minor actinides (MAs) and transuranic elements (mainly plutonium isotopes) compared with the relatively large amounts produced from the uranium-based fuel UO2.
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Said, Moch Iqbal Nur, Mutia Anggraini, Mohammad Zaki Mubarok, and Kurnia Setiawan Widana. "Studi Ekstraksi Bijih Thorit dengan Metode Digesti Asam dan Pemisahan Thorium dari Logam Tanah Jarang dengan Metode Oksidasi-Presipitasi Selektif." EKSPLORIUM 38, no. 2 (November 30, 2017): 109. http://dx.doi.org/10.17146/eksplorium.2017.38.2.3930.

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AbstrakThorium (Th) merupakan logam radioaktif yang dapat terbentuk bersama uranium dan logam tanah jarang (LTJ). Mineral-mineral yang mengandung unsur radioaktif diantaranya monasit ((Ce,La,Y,U/Th)PO4), thorianit ((Th,U)O2), dan thorit (ThSiO4). Daerah Mamuju, Sulawesi Barat diketahui mengandung mineral radioaktif, salah satunya adalah thorit. Untuk memisahkan LTJ dari unsur radioaktif dapat dilakukan dengan cara mengekstraksi thorium dari bijih thorit dengan metode digesti asam menggunakan asam sulfat (H2SO4), kemudian diikuti pelindian dalam air dan rekoveri thorium dalam bentuk thorium hidroksida dengan metode presipitasi kimia menggunakan ammonium hidroksida (NH4OH). Hasil percobaan menunjukkan bahwa kondisi optimum digesti asam yang memberikan persentase ekstraksi paling tinggi didapatkan pada rasio padat/cair 1:2 (g/mL) selama 60 menit dengan persentase ekstraksi Th, besi (Fe), dan LTJ masing-masing sebesar 82,47%, 80,08%, dan 83,31%. Persentase presipitasi Th tertinggi sebesar 95,47% diperoleh pada pH 4,5 dalam suhu ruangan (26±1°C). Pada temperatur yang lebih tinggi, (70°C), diperoleh persentase presipitasi thorium yang lebih rendah sebesar 83,69%. Pre-oksidasi dengan menggunakan larutan H2O2sebanyak dua kali stoikiometri selama 1,5 jam pada suhu kamar meningkatkan persentase presipitasi Fe dari 93,08% menjadi 99,93%. AbstractThorium (Th) is a radioactive metal that can be formed along with uranumand rare earth metals (REM). Minerals contain radioactive elements are monazite ((Ce,La,Y,U/Th)PO4), thorianite ((Th,U)O2), and thorite (ThSiO4). Mamuju Area is containing radioactive minerals, thorite is one of them. To separate REM from radioactive elements can be conducted by exctracting thorium from thorite ore by acid digestion method using sulphuric acid (H2SO4), followed by leaching and thorium recovery in the form of thorium hydroxide by chemical precipitation using ammonium hydroxide (NH4OH). The experimental results showed that the optimum conditions of acid digestion that give the highest Th extraction percentage on solid to liquid ratio are obtained at 1:2 (g/mL) in 60 minutes with extraction percentages of Th, iron (Fe) and REM are 82.47%, 80.08%, and 83.31% respectively. The highest thorium precipitation percentage, as much as 95.47% , was obtained at pH 4.5 on room temperature (26 ± 1°C). At higher temperature (70°C), a lower percentage of thorium precipitation is obtained, as much as 83.69%. Pre-oxidation by using H2O2 solution with two times stoichiometry for 1.5 hours at room temperature is increasing Fe precipitation percentage from 93.08% to 99.93%.
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Dissertations / Theses on the topic "Uranium Thorium"

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Fernandes, Teresa. "Geochemical behaviour of uranium and thorium in the waste of a uranium conversion facility." Doctoral thesis, Universitat Autònoma de Barcelona, 2017. http://hdl.handle.net/10803/460838.

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Los residuos contenidos en las balsas de decantación de la planta de conversión de uranio de Comurhex - Malvési, Francia, han sido caracterizados con el objectivo de investigar el comportamiento de uranio y torio en este entorno específico. El residuo es una sucesión de estratos heterogénea que comprende una mezcla de los efluentes del proceso con el suelo (que han tenido su origen en la re-construcción de los diques de las balsas, el efluente de lodo, y los antiguos desechos de las minas de azufre y de flotación de residuos sobre las que las balsas han sido localizadas. El efluente de lodo original tiene una composición química heterogénea que varía espacialmente y con la profundidad en las balsas debido a la evolución del proceso de conversión con el tiempo y debido a la materia prima recibida de diferentes minas del mundo. En esta tesis, se combinó un examen detallado de los desechos y del agua intersticial, experimentos de batch y en columna, y el modelado geoquímico para caracterizar la composición del material y determinar la especiación geoquímica del uranio y el torio. Los datos presentados en esta tesis han elucidado los mecanismos geoquímicos que controlan la migración de estos elementos y cómo esta migración puede verse afectada en el largo plazo. El uranio en el estrato de los lodos está presente en más de una especiación: como una fase de silicato, como una fase de óxido de uranilo, adsorbido en oxihidróxidos de hierro y asociados a los principales minerales, tales como yeso y calcita. Uranio en los otros estratos de residuos está presente en concentraciones más bajas que las cuantificables mediante técnicas espectroscópicas. La liberación de U (VI) y su transporte dentro de los estratos oxidantes de los lodos está dominado por disolución limitada cinéticamente - y transformación de uranofana, o una fase similar de uranilo - silicato. Las concentraciones de uranio acuoso bajo condiciones experimentales son controladas por una fase mineral. La fase mineral limitante de solubilidad más común en condiciones experimentales ha sido la schoepita (deshidratada). Sin embargo, a escala de campo, y debido a la naturaleza heterogénea de los residuos en las balsas, es posible que, a nivel local, otras fases de uranio pueden ser los principales minerales de solubilidad control. El torio se distribuye homogéneamente en los resíduos, y se encuentra, ocasionalmente correlacionado con el uranio como óxido de U-Th. Las concentraciones de torio en solución son controladas por ThO2. Este trabajo ha puesto en evidencia la importancia de un enfoque que comprenda técnicas complementarias en la caracterización de la especiación sólida de uranio y torio en un material heterogéneo.
The waste contained in the decantation basins of the uranium conversion plant of Comurhex-Malvési, France, was characterised to investigate the behaviour of uranium and thorium in this specific environment. The waste is a succession of heterogeneous strata comprising a mixture of the process effluent with soil (arising from the reconstruction of the basins’ dykes), the sludge effluent, and the former sulphur mine tailings and flotation waste over which the basins have been sited. The original sludge effluent has a heterogeneous chemical composition that varies spatially and with depth in the basins due to the evolution of the conversion process over time and due to the different raw material received from mines around the world. In this thesis, a detailed examination of waste cores and pore waters, static batch and kinetic column test work, and geochemical modelling was combined to characterise the composition of the material and the geochemical speciation of uranium and thorium. The data reported in this thesis have elucidated the geochemical mechanisms that control the migration of these elements and how this migration can be affected in the long term. Uranium in the stratum of sludge is present under more than one speciation: as a silicate phase, as a uranyl-oxide phase, adsorbed to iron oxy-hydroxides and associated with major minerals, such as gypsum and calcite. Uranium in the other strata of waste is present at concentrations that were not quantifiable by spectroscopic techniques. The release of U(VI) and its transport within the oxidising strata of sludge is dominated by kinetically-limited dissolution and transformation of uranophane, or a similar uranylsilicate phase. Aqueous uranium concentrations under experimental conditions are controlled by a mineral phase. schoepite (dehydrated) was found to be the most common solubility limiting mineral. However, at the field scale, and due to the heterogeneous nature of the waste in the basins, it is possible that, locally, other uranium phases may be the main solubility controlling minerals. Thorium is homogeneously distributed in the sludge, and occasionally correlated with uranium, as a U-Th oxide. Thorium concentrations in solution are controlled by ThO2. This work has put in evidence the importance of an approach comprising complementary techniques in the characterisation of the solid speciation of uranium and thorium in a heterogeneous material. The use of multiple techniques is required to identify different phases and in order to establish multiple lines of evidence for the presence of a certain physical form.
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Lee, Kathryn. "Uranium and Thorium: Radioactive Refugees or Simply Irresistible?" Miami University Honors Theses / OhioLINK, 2003. http://rave.ohiolink.edu/etdc/view?acc_num=muhonors1111149868.

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Ahmed, Hayam Mohamed Mahmoud. "Lability and solubility of uranium and thorium in soil." Thesis, University of Nottingham, 2014. http://eprints.nottingham.ac.uk/14492/.

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The approach used in this study tested the application of an isotope dilution technique (ID) as a means of measuring the labile U(VI) and Th pools in soils. Uranium and Th lability and solubility were investigated for two sets of soils. The first set (Field soils) consisted of thirty seven soil samples representing five contrasting local ecosystems; the second dataset (BGSc) included 40 soils sub-sampled from the British Geological Survey (BGS) archive. Field soil pore water samples were taken from soil columns held at close to field capacity to measure U and Th solubility and speciation; the effects of time, temperature and reducing conditions on Th and U speciation were investigated. Soils were extracted with foursingle extractants: CH3COONH4, EDTA, 0.43 M HNO3 and TMAH to determine their ability to solubilize labile U and Th. Solubility of Th and U varied with soil characteristics, influenced by pH, DOC, DIC and phosphate concentrations. The Kd values for Th and U varied by 4 and 3 orders of magnitude respectively over the range of soils studied. The formation of soluble uranyl carbonate complexes give rise to a strong positive correlation between U and DIC concentrations in soil solutions. This was particularly clear under anaerobic conditions and also at high temperatures which encouraged microbial activity and high CO2partial pressures. Isotopically exchangeable 238U(VI) (the ‘E-value’, UE) in the soils studied varied from 2.7 to 39.1% of the total soil U content. On average, over all groups of soils, CH3COONH4, EDTA and TMAH underestimated E-value by factors of 13.7, 9.5 and 1.6, respectively, while extraction with 0.43M HNO3 overestimated E-value by only a factor of 1.04. Thus, on average across a range of soils, dilute nitric acid gave the best estimate of E-value compared to other extractants. Generally, E-values for U(VI) did not correspond consistently with any single chemical extraction procedure although the degree of correspondence was soil-dependent. Using UEand ThTMAH as input parameters in the geochemical speciation model WHAM-VII improved the prediction of U and Th solubility compared to using the total metal content orthe pools extractable by (other) single extraction methods. Finally, preliminary experiments confirmed the validity of ID for measuring labile soil Th without disturbance of soil-solution equilibrium.
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Unsworth, Emily Rachel. "Measurement and modelling of uranium and thorium in natural waters." Thesis, University of Plymouth, 2001. http://hdl.handle.net/10026.1/1145.

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Uranium and thorium are the only elements in the actinide series which naturally occur in the environment in sufficient amounts for practical extraction. They are both radiotoxic and chemotoxic to humans due to the effects of the ionising radiation produced by their radioactive decay, the decay of their daughter products, and due to the chemical toxicity resulting from absorption into the body. Thus it is important to be able to quantitatively determine the levels of uranium and thorium in the environment. Measurement of low levels of uramum and thorium in the presence of high levels of inorganic and organic matrix components has been achieved by coupling on-line solid phase extraction (SPE) with inductively coupled plasma mass spectrometry (ICP-MS) detection. This allowed direct analysis of water samples without any sample pre-treatment offering detection Umits of 0.01 ng ml uranium and 0.006 ng ml thorium. However, in many studies not only do the total levels of uranium and thorium need to be determined, but also their speciation, since this can effect their toxicity and mobility in the environment. An on-line uranium speciation method has successfiilly been developed using a chelating resin micro-column attached to an ICP-MS. This method has been applied to the analysis.pf natural water samples (from Dartmoor, Devon, UK) and the results obtained indicate that the uranium-organic species such as those formed with humic substances are the major species present. A comparison of the pH and level of organic carbon (in a range of natural and synthetic water samples), with the level of uraniumorganic species indicates that the organic carbon concentration is a controlling factor in determining the level of uranium-organic species formed. The kinetics of dissociation of uranium and thorium-humic substance species was also studied. The slow rate of dissociation, observed indicates that once the uranium-humic species have formed these species could remain in the environment for some time. These studies also indicate that even if a change in environmental conditions affected the speciation,it would take time before the uranium and thorium-humic species dissociated and the system equilibrated to a new speciation profile. Two computer programs (WHAM and PHREEQCI) were used to model uranium and thorium speciation in aquatic systems. The Nuclear Energy Agency Thermocheraical Database Project (NEA-TDB) values were incorporated into both programs, as differences in the thermodynamic data provided with the two programs were found to have a major effect on the predicted speciation profiles produced by the two programs. Using the NEATDB values, both programs produced similar inorganic speciation profiles for a given aqueous system but when an organic carbon component was added to the system the two programs produced different predictions for the level of uranium-organic species. This reflected the different organic speciation components utilised within the two programs. WHAM uses a discreet site electrostatic humic substance model and PHREEQCI uses an analogy type model based on a 'model fulvic acid' dataset. A comparison of model predictions with experimental data for the same water sample, indicates that the WHAM program produces closer predictions to the experimental results than the PHREEQCI program. A fiirther study of the WHAM program, using synthetic water solutions with a range of pH, organic carbon and uranium concentrations, indicates that the program has a bias towards low predictions at high pH and low organic carbon concentrations (pH>7, organic carbon < 0.5 ug ml), but wil function satisfactorily within the range of conditions found in the natural (Dartmoor) water samples. The results of these studies should aid environmental investigation based on uranium and thorium where model predictions are to be used.
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Lucas, Frank W. A. A. "The distribution of uranium and thorium in the Cornubian batholith." Thesis, University of Exeter, 1993. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.386120.

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Trivedi, D. P. "The mobility of uranium and thorium series radionuclides in groundwaters." Thesis, University of Bath, 1989. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.277360.

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Van, Wyk Yazeed. "Transport mechanisms of uranium and thorium in fractured rock aquifers." Diss., University of Pretoria, 2010. http://hdl.handle.net/2263/25799.

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The Karoo has been receiving considerable attention since the early 1970’s when uranium mining was at its peak, with numerous research studies being instigated to look at all aspects of uranium mining. It has recently been observed that there seems to be resurgence in uranium exploration in and around the town of Beaufort West. A study on the transport mechanisms of uranium and thorium in fractured-rock aquifers, initiated in the hope of understanding the actual processes controlling radionuclide mobilisation, is reported here. Hydrochemical investigations of the various boreholes were sampled for water quality in June, 2009. The hydrochemical description is typical of shallow fresh groundwater, changing composition to a more sulphate hydrochemical facies along the flow path. While the geochemistry of groundwater in the study area seems to have minimal effects on uranium concentrations, the low levels of uranium in boreholes sampled suggest the importance of hydrological and lithological variability on the measured concentrations. Nevertheless, the uranium concentration is within the recommended levels as specified in the US-EPA, WHO and SA water quality guidelines and thus poses no immediate threat to the general public. Analysis of pumping and tracer tests, reveals that the fractured-rock aquifer can be highly transmissive and that transport can take place via multiple flow paths having different hydraulic properties. Tracer diffusing into stagnant water zones within fracture asperities and the rock matrix are seen as an important retardation mechanism, that has implications for remediation should the aquifer be contaminated by radionuclides. In terms of conceptualising flow at a local scale, aperture sizes ranging from (563-828ìm) along with high flow velocities (1.90E-03m/s), points to the importance of bedding-plane fractures as conduits of groundwater flow. The groundwater flow has been influenced by dolerite dykes creating compartments isolated from each other, suggesting a highly complex aquifer system. Based on the conceptual model, it is shown that these structures can create unique, site specific flow conditions. The integration of all available data into the conceptual model provides an effective research tool that can be built upon as a basis for further research.
Dissertation (MSc)--University of Pretoria, 2011.
Geology
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Rowe, P. J. "Uranium series dating of cave sites in the English Midlands." Thesis, University of East Anglia, 1986. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.376083.

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MARTINS, ELAINE A. J. "Reaproveitamento de valores nos efluentes liquidos das unidades-piloto de uranio e torio." reponame:Repositório Institucional do IPEN, 1990. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10253.

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Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Sullens, Tyler Andrew Albrecht-Schmitt Thomas E. "Hydrothermal synthesis and characterization of novel thorium, uranium, and neptunium solids." Auburn, Ala, 2005. http://repo.lib.auburn.edu/2005%20Summer/doctoral/SULLENS_TYLER_59.pdf.

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Books on the topic "Uranium Thorium"

1

Devraj, T. A. Samuel. Trace analysis of uranium and thorium. Edited by Bhaskara Rao Digumarti 1957-. New Delhi: Discovery Publishing House, 1997.

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Nansha qun dao ji qi lin jin hai yu you tu chen ji te zheng he nian dai yan jiu: Study on uranium thorium sedimentary characteristics and chronology of Nansha Islands and adjacent sea area. Beijing: Hai yang chu ban she, 1996.

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D, Jones Larry. Uranium and thorium occurrences in British Columbia. Victoria, B.C., Canada: Mineral Resources Division, Geological Survey Branch, 1990.

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Kedari, C. S. Studies on the separation and purification of uranium from Thoria irradiated in PHWR. Mumbai: Bhabha Atomic Research Centre, 2005.

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Earle, E. D. Measurements of Th and U in acrylic for the Sudbury Neutrino Observatory (SNO). Chalk River, Ont: Chalk River Laboratories, 1993.

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Jagannathan, V. Trisul, a code for thorium reactor investigations with segregated uranium loading. Mumbai: Bhabha Atomic Research Centre, 2000.

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Institut geologii i geofiziki (Akademii͡a nauk SSSR), ed. Opredelenie mikrosoderzhaniĭ urana i torii͡a v porodakh i mineralakh: Metodicheskie rekomendat͡sii. Novosibirsk: In-t geologii i geofiziki SO AN SSSR, 1986.

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Murray, Andrew. Some investigations of the nickel-uranium-oxygen and nickel-thorium-oxygen systems. Birmingham: University of Birmingham, 1988.

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Parker, Philip M. The 2002 world forecasts of ores and concentrates of uranium and thorium export supplies. San Diego, Calif: Icon Group, 2002.

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Smits, G. Uranium-thorium silicates, with specific reference to the species in the Witwatersrand reefs. Randburg, South Africa: Council for Mineral Technology, 1987.

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Book chapters on the topic "Uranium Thorium"

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Herring, J. Stephen. "Uranium uranium and Thorium thorium Resources uranium resources." In Encyclopedia of Sustainability Science and Technology, 11201–19. New York, NY: Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4419-0851-3_21.

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Dutton, Andrea. "Uranium-thorium dating." In Handbook of Sea-Level Research, 386–403. Chichester, UK: John Wiley & Sons, Ltd, 2015. http://dx.doi.org/10.1002/9781118452547.ch26.

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Kuhns, Roger James, and George H. Shaw. "Uranium and Thorium." In Navigating the Energy Maze, 79–81. Cham: Springer International Publishing, 2018. http://dx.doi.org/10.1007/978-3-319-22783-2_10.

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Herring, J. Stephen. "Uranium and Thorium Resources." In Encyclopedia of Sustainability Science and Technology, 1–22. New York, NY: Springer New York, 2016. http://dx.doi.org/10.1007/978-1-4939-2493-6_21-3.

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Attendorn, H. G., and R. N. C. Bowen. "Uranium-thorium-lead dating." In Radioactive and Stable Isotope Geology, 85–130. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5840-4_4.

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Herring, J. Stephen. "Uranium and Thorium Resources." In Nuclear Energy, 463–90. New York, NY: Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4614-5716-9_18.

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Herring, J. Stephen. "Uranium and Thorium Resources." In Nuclear Energy, 165–85. New York, NY: Springer New York, 2018. http://dx.doi.org/10.1007/978-1-4939-6618-9_21.

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Bowen, Robert. "Uranium, Thorium, Lead Dating." In Isotopes in the Earth Sciences, 115–61. Dordrecht: Springer Netherlands, 1994. http://dx.doi.org/10.1007/978-94-009-2611-0_3.

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Schwarz-Schampera, Ulrich. "The Potential of Thorium Deposits." In Uranium, Mining and Hydrogeology, 53–58. Berlin, Heidelberg: Springer Berlin Heidelberg, 2008. http://dx.doi.org/10.1007/978-3-540-87746-2_7.

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Blundy, Jonathan, and Bernard Wood. "3. Mineral-Melt Partitioning of Uranium, Thorium and Their Daughters." In Uranium-series Geochemistry, edited by Bernard Bourdon, Gideon M. Henderson, Craig C. Lundstrom, and Simon Turner, 59–124. Berlin, Boston: De Gruyter, 2003. http://dx.doi.org/10.1515/9781501509308-008.

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Conference papers on the topic "Uranium Thorium"

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Dodona, Ema. "Determination of Uranium, Thorium and Potassium." In 7th Congress of the Balkan Geophysical Society. Netherlands: EAGE Publications BV, 2013. http://dx.doi.org/10.3997/2214-4609.20131743.

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Kubáň, Jan, and Radek Škoda. "Utilization of Thorium in LWR Fuels Aiming at Thermal Conductivity Improvements." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60300.

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One of the main drawbacks of uranium dioxide, which is used in almost all nuclear power reactors, is its low thermal conductivity. As a consequence, temperature at the center of fuel pellet is relatively high, because heat is poorly conducted away. To reach a higher level of safety, maximal temperature in any fuel pellet is one of the main limiting parameters, which restrict the fuel thermal output. This paper deals with the use of thorium in LWR fuels with the objective of fuel pellet maximal temperature reduction. Research investigating homogenous distribution of thorium dioxide (thoria) in uranium dioxide fuel has already been done and did not lead to considerable thermal conductivity improvements. The aim of this study is to investigate heterogeneous distribution of thorium in commonly used uranium dioxide fuel in the form of uranium and thorium pellets placed together.
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Mihalchenko, I., and A. Andreev. "New (?) calcium-thorium-uranium silicate (calciothorouranite) from thorium-uranium ore albitites from the Novooleksisvka ore occurrence, the Ukrainian Shield." In Geoinformatics: Theoretical and Applied Aspects 2020. European Association of Geoscientists & Engineers, 2020. http://dx.doi.org/10.3997/2214-4609.2020geo039.

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Gerasimov, Aleksander S., Boris R. Bergelson, and Tamara S. Zaritskaya. "Two Periods of Long-Term Storage of Thorium Spent Fuel." 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/icem2001-1219.

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Abstract Radiotoxicity and decay heat power of actinides from spent thorium-uranium nuclear fuel of VVER-1000 type reactor during 100 000 year storage are discussed. Actinide accumulation in thorium fuel cycle is much less than in uranium fuel cycle. The radiotoxicity of actinides of thorium-uranium fuel by air is 5.5 times less and radiotoxicity by water is 3.5 times less than radiotoxicity of actinides of uranium fuel. Extraction of most important nuclides for transmutation permits to reduce radiologic danger of wastes remaining in storage.
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Panda, R. N., M. Bhuyan, and S. K. Patra. "Energy Production from Neutron-rich Uranium and Thorium Isotopes." In 2012 IEEE International Conference on Engineering Education: Innovative Practices and Future Trends (AICERA). IEEE, 2012. http://dx.doi.org/10.1109/aicera.2012.6306720.

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Park, Jungkyu, Eduardo B. Farfán, Christian Enriquez, Nicholas Kinder, and Matthew Greeson. "Thermal Transport in Thorium Dioxide." In ASME 2017 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/imece2017-71614.

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Thorium is more abundant in nature than uranium and thorium fuels can breed fissile U-233 fuel that can be used in various types of nuclear reactors. Moreover, thorium dioxide has drawn interest from researchers due to its relatively superior thermal properties when compared to conventional uranium dioxide fuel pellets. In this study, thermal transport in thorium dioxide is investigated using reverse non-equilibrium molecular dynamics. The thermal conductivity of bulk thorium dioxide was measured to be 20.8 W/m-K and the phonon mean free path was estimated to be between 7 ∼ 8.5 nm at 300 K. It was also observed that the thermal conductivity of thorium dioxide has a strong dependency on temperature; the thermal conductivity decreases with an increase in the temperature. Moreover, by simulating thorium dioxide structures with different lengths at different temperatures, it was also identified that short wavelength phonons dominate thermal transport in thorium dioxide at high temperatures, resulting in decreased intrinsic phonon mean free paths and minimal effect of boundary scattering while long wavelength phonons dominate the thermal transport in thorium dioxide at low temperatures.
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Heisbourg, G., N. Dacheux, G. Lagarde, S. Hubert, and J. Ritt. "Kinetic Study of the Crystallized ThO2 and Solid Solutions Th1−xUxO2 Dissolution." 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/icem2001-1288.

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Abstract Thorium dioxide is an important material for the nuclear industry. In the last decade, there has been a renewal of interest in studying the feasibility of thorium based fuel reactor to decrease the minor actinides production during the burn-up. Furthermore the resistance of the thorium dioxide to aqueous corrosion can make this material attractive for immobilizing tetravalent actinides. Leaching tests of powdered samples of thorium dioxide calcinated at 1300°C showed that the normalized dissolution rate is very low (between 10−6 and 10−7 g/(m2.d) in acidic media, and 10−9–10−10 g/(m2.d) after pH&gt;3 when the formation of colloïdes occurs. Thorium dioxide which is isomorphic with the actinide dioxides such as UO2, PuO2 allows the formation of solid solutions whatever the concentration of the actinide. Several solid solutions Th1−xUxO2 were synthesized with mole-ratios Th/(U+Th) ranging from x = 0 to 1. X-ray powder diffraction data allowed to check that the Vegard’s law is respected in all the range, and specific surface area was also measured. The resistance of the solid-solution to aqueous corrosion was measured as a function of several parameters (leaching time, leachate acidity, uranium concentration) and the kinetics of solid solutions dissolution was determined as a function of the uranium concentration. The stoechiometry of the release of both actinides was verified, however due to the oxidization of U (IV) in U (VI) in contact with the leachate, the dissolution rate of both thorium and uranium increases with the thorium substitution in the solid by uranium (TV).
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Thorum, Aaron, Logan Page, Troy Munro, David Allred, Zilong Hua, and David Hurley. "Thermal Properties of Thin Film Uranium Oxides and Thorium Oxides." In ASME 2019 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/imece2019-11699.

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Abstract Uranium and thorium oxides have critical roles as fuels in existing nuclear power plants, as well as in proposed reactor concepts. The thermal conductivity of these materials determines their ability to transfer heat from the reactor core to the surrounding coolant. Additionally, these actinide compounds are of interest in condensed matter physics because of the 5f orbitals and unique electron interaction, coupling, and scattering events that can occur. Because of the radioactivity of thorium and uranium, thin film measurements of actinide materials are used to limit the amount of operator exposure, but standard thermal characterization methods are not well suited for thin films. This paper presents the process of depositing thin film UOx and ThOx samples of nm-μm thicknesses and the results of thermal property measurements. Thin films were deposited on silicon and glass substrates via dc-magnetron sputtering using an argon/oxygen mixture as the working gas. The thermal properties of the films were measured by the Thermal Conductivity Microscope (TCM). This uses one laser to generate thermal waves and a second laser to measure the magnitude and phases of the thermal waves to obtain the conductivity of materials. The results of the research show that the UOx film properties are lower than bulk values and that the role of the substrate has a considerable effect on determining the measured properties. Future work aims at improving the deposition process. Epitaxial film growth is planned. Additional understanding of thermal property measurements is targeted.
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Russell, G. J., T. O. Brun, E. J. Pitcher, L. L. Daemen, and W. B. Wilson. "800-MeV proton irradiation of thorium and depleted uranium targets." In The international conference on accelerator-driven transmutation technologies and applications. AIP, 1995. http://dx.doi.org/10.1063/1.49102.

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Boczar, Peter G., Bronwyn Hyland, Keith Bradley, and Sermet Kuran. "Achieving Resource Sustainability in China Through the Thorium Fuel Cycle in the Candu Reactor." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29664.

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The CANDU® reactor is the most resource-efficient reactor commercially available. The features that enable the CANDU reactor to utilize natural uranium facilitate the use of a wide variety of thorium fuel cycles. In the short term, the initial fissile material would be provided in a “mixed bundle”, in which low-enriched uranium (LEU) would comprise the outer two rings of a CANFLEX® bundle, with ThO2 in the central 8 elements. This cycle is economical, both in terms of fuel utilization and fuel cycle costs. The medium term strategy would be defined by the availability of plutonium and recovered uranium from reprocessed used LWR fuel. The plutonium could be used in Pu/Th bundles in the CANDU reactor, further increasing the energy derived from the thorium. Recovered uranium could also be effectively utilized in CANDU reactors. In the long term, the full energy potential from thorium could be realized through the recycle of the U-233 (and thorium) in the used CANDU fuel. Plutonium would only be required to top up the fissile content to achieve the desired burnup. Further improvements to the CANDU neutron economy could make possible a very close approach to the Self-Sufficient Equilibrium Thorium (SSET) cycle with a conversion ratio of unity, which would be completely self-sufficient in fissile material (recycled U-233).
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Reports on the topic "Uranium Thorium"

1

Carson, J. M., P. B. Holman, R. B. K. Shives, K. L. Ford, K. Ashton, and W. Slimmon. Uranium/Thorium map, Uranium City, Saskatchewan, NTS 74N/10. Natural Resources Canada/ESS/Scientific and Technical Publishing Services, 2001. http://dx.doi.org/10.4095/212526.

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Buckle, J. L., J. M. Carson, K. L. Ford, R. Fortin, and W F Miles. Radioactivity map of Canada, uranium/thorium. Natural Resources Canada/ESS/Scientific and Technical Publishing Services, 2014. http://dx.doi.org/10.4095/293357.

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Smith, A. B., and S. Chiba. Neutron scattering from elemental uranium and thorium. Office of Scientific and Technical Information (OSTI), January 1995. http://dx.doi.org/10.2172/125101.

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Carson, J. M., P. B. Holman, R. B. K. Shives, K. L. Ford, K. Ashton, and W. Slimmon. Uranium/Thorium map, Saskatchewan, NTS 74N/6. Natural Resources Canada/ESS/Scientific and Technical Publishing Services, 2001. http://dx.doi.org/10.4095/212474.

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Carson, J. M., P. B. Holman, R. B. K. Shives, K. L. Ford, K. Ashton, and W. Slimmon. Uranium/Thorium map, Goldfields, Saskatchewan, NTS 74N/8. Natural Resources Canada/ESS/Scientific and Technical Publishing Services, 2001. http://dx.doi.org/10.4095/212524.

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Carson, J. M., P. B. Holman, and K. L. Ford. Equivalent Uranium/equivalent Thorium radioactivity map of Manitoba, Manitoba. Natural Resources Canada/ESS/Scientific and Technical Publishing Services, 2008. http://dx.doi.org/10.4095/224858.

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Kaplan, D. I. Quantification of thorium and uranium sorption to contaminated sediments. Office of Scientific and Technical Information (OSTI), August 2000. http://dx.doi.org/10.2172/759386.

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Carson, J. M., P. B. Holman, R. B. K. Shives, K. L. Ford, C T Harper, and W. Slimmon. Uranium/Thorium map, Hara Lake, Saskatchewan, NTS 64M/1. Natural Resources Canada/ESS/Scientific and Technical Publishing Services, 2001. http://dx.doi.org/10.4095/212306.

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Carson, J. M., P. B. Holman, R. B. K. Shives, K. L. Ford, C T Harper, and W. Slimmon. Uranium/Thorium map, Eyinew Lake, Saskatchewan, NTS 64M/2. Natural Resources Canada/ESS/Scientific and Technical Publishing Services, 2001. http://dx.doi.org/10.4095/212372.

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Carson, J. M., P. B. Holman, R. B. K. Shives, K. L. Ford, C T Harper, and W. Slimmon. Uranium/Thorium map, Bickerton Lake, Saskatchewan, NTS 64M/3. Natural Resources Canada/ESS/Scientific and Technical Publishing Services, 2001. http://dx.doi.org/10.4095/212373.

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