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Bhattacharjee, S.; Broczkowski, M.E.; Kryst, K.; Ioffe, M.S.; Murchie, M.P., E-mail: Subir_Bhattacharjee@cameco.com
Uranium 2010: The Future is U. Proceedings Volume 1 and 22010
Uranium 2010: The Future is U. Proceedings Volume 1 and 22010
AbstractAbstract
[en] Particle size and specific surface area measurements are conventional characterization techniques for ceramic powders to predict sintering behaviour. Dilatometry is one of the most popular techniques in ceramics to study the sintering characteristics for optimization of firing processes. Uranium dioxide (UO_2) powders from different sources were characterized by conventional techniques and these characteristics were correlated with sintering behaviour, as measured with a dilatometer. The suitability of dilatometry to correlate the sintering characteristics of UO_2 powder with variations in the O/U ratio, particle size and green density was discussed. Explanations of features in the sintering profiles for UO_2 powders have been presented. (author)
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Lam, E.K. (Cameco, Port Hope, Ontario (Canada)); Rowson, J.W. (AREVA Resources, Saskatoon, Saskatchewan (Canada)); Ozberk, E. (Cameco, Saskatoon, Saskatchewan (Canada)) (eds.); The Canadian Inst. of Mining, Metallurgy and Petroleum, Westmount, Quebec (Canada); 2 v; ISBN 1-894475-97-6;
; 2010; (v.2) p. 167-176; Uranium 2010 The Future is U: 3. International Conference on Uranium; Saskatoon, Saskatchewan (Canada); 15-18 Aug 2010; 40. Annual Hydrometallurgy Meeting; Saskatoon, Saskatchewan (Canada); 15-18 Aug 2010; Available from The Canadian Inst. of Mining, Metallurgy and Petroleum, Westmount, Quebec (Canada); 12 refs., 4 tabs. , 10 figs.

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Vargasov, D.D.
Working management in the division on development of equipment for radiochemical industry, fuel fabrication and manipulations with radioactive wastes of spent nuclear fuel reprocessing. Out-of-town meeting of the sections 2, 3 of NTS-4 of FAAEh. Collection of reports2005
Working management in the division on development of equipment for radiochemical industry, fuel fabrication and manipulations with radioactive wastes of spent nuclear fuel reprocessing. Out-of-town meeting of the sections 2, 3 of NTS-4 of FAAEh. Collection of reports2005
AbstractAbstract
[en] In SverdNIIkhimmash series of units are created for reprocessing of different materials initial particle sizes of which reach 1.5 m and finished product sizes are some micrometers. Realized on the basis of hydraulic presses, jaw, knife, roller and cone crushers, abrasive discs, ball, vibratory, vapart, and jet-type mills with equipping of part of them by screen or pneumatic classifiers these units are combined into one ore some stages and work in open or closed cycle
[ru]
В СвердНИИхиммаше создан ряд установок, позволяющих перерабатывать различные материалы, первоначальный размер кусков которых достигает 1.5 м, а крупность частиц конечных продуктов не превышает нескольких микрометров. Выполненные на базе гидравлических прессов, щековых, ножевых, валковых, конусных дробилок, истирающих дисков, шаровых, вибрационных, центробежных и струйных мельниц, с оснащением части из них ситовыми или воздушными классификаторами, эти установки компануются в одну или несколько ступеней и работают в открытом или замкнутом циклеOriginal Title
Droblenie, izmel'chenie i klassifikatsiya materialov v oborudovanii SverdNIIkhimmasha dlya proizvodstv Rosatoma
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Federal'noe Agentstvo po Atomnoj Ehnergii, Moscow (Russian Federation); Sverdlovskij Nauchno-Issledovatel'skij Institut Khimicheskogo Mashinostroeniya, Ekaterinburg (Russian Federation); 447 p; ISBN 5-900700-12-7;
; 2005; p. 220-228; Working management in the division on development of equipment for radiochemical industry, fuel fabrication and manipulations with radioactive wastes of spent nuclear fuel reprocessing; Organizatsiya rabot v otrasli po sozdaniyu oborudovaniya radiokhimicheskikh proizvodstv, izgotovleniyu topliva i obrashcheniya s RAO ot pererabotki OYaT; Ekaterinburg (Russian Federation); 7-9 Dec 2004; 7 figs.

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AbstractAbstract
[en] Mathematical simulation on basis of Stock law has been done for wet sizing process on cylinder equipment of laboratory and semi-industrial scale. The model consists of mathematical equations describing relations between variables, such as: - Resident time distribution function of emulsion particles in the separating zone of the equipment depending on flow-rate, height, diameter and structure of the equipment. - Size-distribution function in the fine and coarse parts depending on resident time distribution function of emulsion particles, characteristics of the material being processed, such as specific density, shapes, and characteristics of the environment of classification, such as specific density, viscosity. - Experimental model was developed on data collected from an experimental cylindrical equipment with diameter x height of sedimentation chamber equal to 50 x 40 cm for an emulsion of zirconium silicate in water. - Using this experimental model allows to determine optimal flow-rate in order to obtain product with desired grain size in term of average size or size distribution function. (author)
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Vuong Huu Tan; Le Van Hong; Nguyen Hoang Anh; Trinh Dang Hieu; Nguyen Trong Trang; Dang Thi Hong (eds.); Vietnam Atomic Energy Commission, Hanoi (Viet Nam); 244 p; Aug 2004; p. 217-220; VAEC-AR--03-35; Also available from Information Centre, VAEC; 3 refs.
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Report
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Husein, Y.N.; Budyka, A.K.; Pripachkin, D.A.
Innovative nuclear reactors of small and ultra-small power. III International conference of young scientists, specialists, postgraduates and students. Theses2018
Innovative nuclear reactors of small and ultra-small power. III International conference of young scientists, specialists, postgraduates and students. Theses2018
AbstractAbstract
No abstract available
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Ministerstvo Obrazovaniya i Nauki Rossijskoj Federatsii, Moscow (Russian Federation); Gosudarstvennaya Korporatsiya po Atomnoj Ehnergii «Rosatom», Moscow (Russian Federation); Natsional'nyj Issledovatel'skij Yadernyj Univ. «MIFI», Moscow (Russian Federation); Obninskij Inst. Atomnoj Ehnergetiki, Obninsk (Russian Federation); 72 p; 2018; p. 7-9; Innovative nuclear reactors of small and ultra-small power. III International conference of young scientists, specialists, postgraduates and students; Innovatsionnye yadernye reaktory maloj i sverkhmaloj moshchnosti. III Mezhdunarodnaya konferentsiya molodykh uchenykh, spetsialistov, aspirantov i studentov; Obninsk (Russian Federation); 15-16 May 2018; 3 refs., 2 figs.
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AbstractAbstract
[en] The composition of Semi-dry Flue Gas Desulfurization ash was as follows: CaSO3 · 0.5H2O and Ca(OH)2. Most of the particle size was about 8 µm; particles were irregular and small, while the other part was rough and globular. CaSO3 strongly oxidized at about 466°C and Ca(OH)2 decomposed at ∼ 662°C. The maximum amount of phosphorus removal in Semi-dry Flue Gas Desulfurization ash was 79.898 mg/g. (paper)
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International Conference on Computer Information and Automation Engineering; Yichang (China); 17-19 Nov 2017; Available from http://dx.doi.org/10.1088/1757-899X/359/1/012021; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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IOP Conference Series. Materials Science and Engineering (Online); ISSN 1757-899X;
; v. 359(1); [7 p.]

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Vaidyanathan, Ramanathan; Curtis, Adam; Mullin, Margaret; Reid, Stuart, E-mail: 0905695P@student.gla.ac.uk, E-mail: A.Curtis@bio.gla.ac.uk, E-mail: Margaret.mullin@bio.gla.ac.uk2012
AbstractAbstract
No abstract available
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Copyright (c) 2012 Springer Science+Business Media Dordrecht; Article Copyright (c) 2012 Springer Science+Business Media B.V.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
Journal
Journal of Nanoparticle Research; ISSN 1388-0764;
; v. 14(11); p. 1

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Noshkin, V. E.; Eagle, R.J.; Robison, W.L.
Lawrence Livermore National Lab., CA (United States). Funding organisation: USDOE, Washington, DC (United States)1997
Lawrence Livermore National Lab., CA (United States). Funding organisation: USDOE, Washington, DC (United States)1997
AbstractAbstract
[en] In 1979, 21 years after the moratorium on nuclear testing in the Marshall Islands, surface sediment samples (to depths of 2 and 4 cm) were collected from 87 locations over the floor of Bikini lagoon. The main purpose for the collections was to map the distribution of long- lived man-made radionuclides associated with the bottom material. In addition the samples were processed to estimate the fraction of fine and coarse components to show what modifications occurred since the sediment composition was first described in samples collected before testing in 1946. In this report a comparison is made of the amount and distribution of fine material associated with the lagoon surface sediment before and after the testing of nuclear devices. Nuclear testing produced more finely divided material in-the surface sediment layer over large areas of the lagoon and especially in regions of the lagoon and reef adjacent to test sites. Five cratering events at Bikini Atoll generated sufficient material to account for the inventory of new fine material found over the bottom surface of the lagoon. Although the fraction of fine material in the bottom sediments was altered by the nuclear events, the combined processes of formation, transport and deposition were not sufficiently dynamic to alter the geographical features of the major sedimentary components over most of the lagoon floor
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1 Jan 1997; 27 p; CONTRACT W-7405-ENG-48; ALSO AVAILABLE FROM OSTI AS DE98050670; NTIS; US GOVT. PRINTING OFFICE DEP
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Report
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Dehghani, A.; Gochin, R.J.; Monhemius, A.J.
Proceedings of the international symposium on control and optimization in minerals, metals and materials processing1999
Proceedings of the international symposium on control and optimization in minerals, metals and materials processing1999
AbstractAbstract
[en] The shapes of particles and apertures have significant effects on the screening process. Experiments employing slotted screens were performed to determine the influence of screening parameters on mass recovery and flakiness index of the oversize particles. Response surface methodology was employed for modelling and analysis of data. It was shown that the mass recovery and flakiness index of the screen oversize could be predicted from the operating parameters. This study should provide a basis for optimising the screening conditions to obtain maximum mass recovery at low flakiness index. (author)
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Hodouin, D.; Bazin, C.; Desbiens, A. (Laval Univ., Quebec City, Quebec (Canada)) (eds.); Canadian Inst. of Mining, Metallurgy and Petroleum, Montreal, Quebec (Canada); 523 p; ISBN 0-919086-88-8;
; 1999; p. 489-499; Control and optimization in minerals, metals and materials processing - 38. annual conference of metallurgists of CIM. Gateway to the 21st Century; Quebec City, Quebec (Canada); 22-26 Aug 1999; 12 refs., 4 tabs., 4 figs.

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Schebarchov, D.; Wales, D. J., E-mail: Dmitri.Schebarchov@gmail.com, E-mail: dw34@cam.ac.uk2013
AbstractAbstract
[en] We analyse the combinatorial aspect of global optimisation for multicomponent systems, which involves searching for the optimal chemical ordering by permuting particles corresponding to different species. The overall composition is presumed fixed, and the geometry is relaxed after each permutation in order to relieve local strain. From ideas used to solve graph partitioning problems we devise a deterministic search scheme that outperforms (by orders of magnitude) conventional and self-guided basin-hopping global optimisation. The search is guided by the energy gain from either swapping particles i and j (ΔEij) or changing the identity of particles i (ΔEi). These quantities are derived from the underlying (arbitrary) energy function, hence not constituting external bias, and for site-separable force fields each ΔEi can be approximated simply and efficiently. In our self-guided variant of basin-hopping, particles are weighted by an approximate ΔEi when randomly selected for an exchange, yielding a significant improvement for segregated multicomponent systems with modest particle size mismatch
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(c) 2013 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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External URLExternal URL
AbstractAbstract
[en] Measurements of mass transfer rates in open bubble columns; studies of oxidation of tritium as it permeates fusion reactor containment, flooding studies in columns filled with Goodloe packing, studies of mass transfer rates between water and mercury, preparation of small particles, and development of equipment are reported. (MCG)
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Oak Ridge National Lab., Tenn. (USA); p. 72-78; Oct 1975
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Progress Report
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