Bidaye, A.C.; Sharma, I.G.
Proceedings of the international seminar on mineral processing technology with focus on industrial minerals and their processing for value addition2007
Proceedings of the international seminar on mineral processing technology with focus on industrial minerals and their processing for value addition2007
AbstractAbstract
[en] Zircon is an important industrial mineral and apart from its own applications, serves as the primary raw material for the production of a series of technologically significant zirconium and hafnium chemicals. However, due to its high melting point and chemical inertness, processing of zircon is a major technological challenge and very aggressive methods have to be adopted to open up zircon. This paper will review some these methods and attempt to determine the trends in the processing of zircon. Along with some of the other techniques, the carbo-chlorination of zircon in an electro-thermal fluidized bed reactor, which constituted a part of the pyro-chemical process for preparing nuclear grade zirconium, was extensively investigated in our laboratory. The technological challenges and the environmental and economic benefits of this technique vis-a-vis the other established practices will be discussed, with emphasis on production of nuclear grade zirconium. (author)
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Khosla, N.K.; Jadhav, G.N. (Indian Institute of Technology, Bombay, Mumbai (India)) (eds.); Indian Institute of Technology, Bombay, Mumbai (India); Indian Institute of Mineral Engineers (India); Ashapura Group, Mumbai (India); 788 p; ISBN 81-8424-177-1; ; 2007; p. 359-363; MPT-2007: mineral processing technology; Mumbai (India); 22-24 Feb 2007; 9 refs., 1 fig.
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BUTYL PHOSPHATES, ELEMENTS, ESTERS, FUEL DISPERSION REACTORS, HOMOGENEOUS REACTORS, METALS, MINERALS, ORGANIC COMPOUNDS, ORGANIC PHOSPHORUS COMPOUNDS, PHOSPHORIC ACID ESTERS, PHYSICAL PROPERTIES, PROCESSING, REACTORS, REPROCESSING, SEPARATION PROCESSES, SILICATE MINERALS, THERMODYNAMIC PROPERTIES, TRANSITION ELEMENTS, TRANSITION TEMPERATURE
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Krishnan, T.S.; Bidaye, A.C.
Proceedings of the symposium on metallothermic processes in metal and alloy extraction (held at) Nagpur (during) December 28-30, 19831987
Proceedings of the symposium on metallothermic processes in metal and alloy extraction (held at) Nagpur (during) December 28-30, 19831987
AbstractAbstract
[en] The paper discusses the essential details of metallothermy and presents an overview of the process as applied to rare earth metal and alloy (particularly Sm-Co) production technology. The paper also highlights the major advantages of metallothermy over the conventional melting and casting processes. 15 refs. (author)
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Bose, D.K.; Krishnamurthy, N.; Mehra, O.K. (Bhabha Atomic Research Centre, Bombay (India). Metallurgy Div.) (eds.); Department of Atomic Energy, Bombay (India); 421 p; 1987; p. 249-258; Department of Atomic Energy; Bombay (India); Symposium on metallothermic processes in metal and alloy extraction; Nagpur (India); 28-30 Dec 1983
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Paul, Bhaskar; Alex, Pamela; Bidaye, A.C.; Sharma, I.G.
Proceedings of the two day seminar on microtexture and microstructure: program and abstracts2009
Proceedings of the two day seminar on microtexture and microstructure: program and abstracts2009
AbstractAbstract
[en] The major use of cobalt metal continues to be in super alloys followed by its use in hard materials, pigments, magnets, batteries, orthopedic alloys, catalysts and coloring agents, etc. Besides this, extensive usage of its radioisotope 60Co, as a Gamma radiation source for a variety of industrial and medical applications, Self Powered Neutron Detectors (SPND's), flux mapping, fuel management, etc. makes it a material of immense interest for the researchers. Powder metallurgy (PM) routes are being increasingly investigated because it provides much finer microstructures with uniform distribution of micro-constituents with attractive properties. PM route is more than an option where the primary source of matrix metal of an alloy is scarce or the matrix metal has to be recovered from secondary resources. Cobalt is an example of the latter case and it is generally recovered in powder form, from various secondary resources (e.g. spent ammonia cracker catalyst, tool steel etc.) This paper reports on studies conducted on sintering of cobalt powder for radioisotope production. Cobalt powder was prepared by thermal decomposition of cobalt oxalate and reduction of cobalt sulfate using hydrazine as a reducing agent in alkaline medium. The Co powder was characterized by SEM, TEM and XRD for size, shape, phase and morphology prior to sintering. The optimum parameters for preparing and scaling up of cobalt powder with suitable morphology were established. The influence of compacting pressure and sintering temperature were studied on cobalt metal powder of different characteristics to obtain sintered density greater than 95 % theoretical. The sintered microstructures were characterized by optical microscope as well as SEM. The findings of characterization studies were utilized to adjust judiciously the process parameters like temperature, time and compaction pressure to control the grain growth during sintering. (author)
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Materials Research Society of India, Mumbai Chapter, Mumbai (India); Bhabha Atomic Research Centre, Mumbai (India); Board of Research in Nuclear Sciences, Department of Atomic Energy, Mumbai (India); 124 p; Nov 2009; p. 78; Microstructure 2009: seminar on microtexture and microstructure; Mumbai (India); 27-28 Nov 2009
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Book
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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, COBALT ISOTOPES, ELECTROMAGNETIC RADIATION, ELECTRON MICROSCOPY, FABRICATION, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, IONIZING RADIATIONS, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MICROSCOPY, MINUTES LIVING RADIOISOTOPES, NUCLEI, ODD-ODD NUCLEI, RADIATIONS, RADIOISOTOPES, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] Partitioning of plutonium from uranium is an important step in the reprocessing of spent fuel by PUREX process of solvent extraction using 30% TBP-dodecane. This is achieved by selectively reducing the Pu in solution to least extractable trivalent state by uranous nitrate as the reductant. The latter is conventionally produced by electrolytic reduction of uranyl ion in presence of hydrazine nitrate as uranous nitrate stabilizer using Pt-coated titanium as the anode. The anode plating wears out after period of operation thus affecting the process efficiency and hence the quality control testing of platinum plated electrode becomes important. This article describes the use of Beta backscattering method with strontium-90 radioisotope as non-destructive testing tool for measuring the coating thickness of the sample Ti electrode. The surface characteristics and coating morphology were also examined by scanning electron microscope and the micrographs are presented. (author)
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NAC-IV: 4. International Symposium on Nuclear Analytical Chemistry. Part 1; Mumbai (India); 15-19 Nov 2010; 4 refs.
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Journal Article
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Conference
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Journal of Radioanalytical and Nuclear Chemistry; ISSN 0236-5731; ; CODEN JRNCDM; v. 294(1); p. 49-52
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Singh, Kulwant; Bidaye, A.C.; Suri, A. K.
Proceedings of the international symposium for research scholars on metallurgy, materials science and engineering2010
Proceedings of the international symposium for research scholars on metallurgy, materials science and engineering2010
AbstractAbstract
[en] Reactive magnetron sputtering, a physical vapor deposition (PVD) technique, is used widely for deposition of compound and composite coatings. Ternary compound or multi component compound coatings are increasingly being researched due to their exotic properties. The properties of these coatings depend strongly on the composition of the films. A mathematical model has been developed to predict the composition of the metallic constituents of the coatings deposited by reactive magnetron sputtering using two metals composite target in the presence of a reactive gas (nitrogen) environment. In the model, composition of the metallic constituents of the coating and percentage of covered areas of the target (target poisoning) vis-a-vis partial pressure of nitrogen can be predicted. The model has been experimentally tested on titanium-niobium system. (author)
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Dept. of Metallurgical and Materials Engineering, Indian Institute of Technology Madras, Chennai (India); Indian Institute of Metals Chennai Chapter, Chennai (India); 205 p; 2010; p. 47; ISRS-2010: 4. international symposium for research scholars on metallurgy, materials science and engineering; Chennai (India); 20-22 Dec 2010
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Bidaye, A.C.; Sharma, I.G.; Dulera, I.V., E-mail: acbidaye@barc.gov.in
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.12006
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.12006
AbstractAbstract
[en] The compact high temperature reactor (CHTR) is being developed to serve as a compact power pack in remote areas not connected to the electrical grid. It is a mainly 233U-thorium fuelled, lead-bismuth cooled and beryllium oxide moderated reactor. This reactor is being designed to operate at 1000 °C to generate about 100 kWTh power, with a core life of 15 years and will incorporate several advanced passive safety features. The reactor also facilitate demonstration of technologies for high temperature process heat applications such as hydrogen production from water
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Bhabha Atomic Research Centre, Mumbai (India); 179 p; 2006; p. 168; ANM 2006: international conference on advances in nuclear materials processing, performance and phenomena; Mumbai (India); 12-16 Dec 2006; MBFE 2006: satellite conference on materials behaviour- far from equilibrium; Mumbai (India); 12-16 Dec 2006; This record replaces 50063263
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Book
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Conference
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ACTINIDE NUCLEI, ALLOYS, ALPHA DECAY RADIOISOTOPES, ENRICHED URANIUM REACTORS, EVEN-ODD NUCLEI, EXPERIMENTAL REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HEAVY ION DECAY RADIOISOTOPES, HEAVY NUCLEI, HELIUM COOLED REACTORS, HTGR TYPE REACTORS, ISOTOPES, NEON 24 DECAY RADIOISOTOPES, NUCLEI, RADIOISOTOPES, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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[en] The present article highlights the developments made in the field of indigenization of the technology for preparation of cobalt shapes for radioisotope applications from a secondary resource. In the first step, the process of extraction of cobalt in the form of metal powder from a secondary indigenous resource as spent ammonia cracker catalyst is described. In the second step, the processes of conversion of cobalt metal powder into the desired shapes followed by coating over the finished products have been presented. (author)
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4 refs., 7 figs.
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Journal Article
Journal
BARC Newsletter; ISSN 0976-2108; ; (337); p. 24-28
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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, COBALT ISOTOPES, DIAGNOSTIC TECHNIQUES, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MATERIALS TESTING, MEDICINE, MINUTES LIVING RADIOISOTOPES, NUCLEAR MEDICINE, NUCLEI, ODD-ODD NUCLEI, RADIOISOTOPES, RADIOLOGY, TESTING, YEARS LIVING RADIOISOTOPES
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