1988
DOI: 10.1007/bf02744653
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Mineral processing in the Indian nuclear energy programme

Abstract: Uranium is the basic raw material for a nuclear energy programme. Uranium ore is processed in India by the well-known method of sulphuric acid, ion-exchange concentration and its final precipitation as magnesium diuranate-'yellow cake'. We have established a process for uranium recovery from the tailings of copper concentrators which also enables recovery of small amounts of copper, nickel and molybdenum present in the uranium ore. Another major activity of this centre has been the exploitation of mineral-rich… Show more

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Cited by 4 publications
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“…This has been amended to include monazite by using the weightings for monazitic beach sands from India from Ref. [25] and weighting these in relation to their economic value (using 2011 US $ values provided in Ref. [26]).…”
Section: Methodsmentioning
confidence: 99%
“…This has been amended to include monazite by using the weightings for monazitic beach sands from India from Ref. [25] and weighting these in relation to their economic value (using 2011 US $ values provided in Ref. [26]).…”
Section: Methodsmentioning
confidence: 99%
“…NUCLEAR R&D BUDGET: India's budget forFY 1989FY -1990 billion rupees (about $1.28 billion U.S.), which is a 29% increase over the prior year; this funding also includes plant operations and design (NW 3/16/89) in total CANDU-type reactors and LWR reactors and the associated fuel cycles: uranium mining, milling and conversion; uranium enrichment; fuel fabrication; heavy water production; reprocessing in small plants adjacent to nuclear power stations; this strategy has been achieved(Murthy 1988); if enriched UF 6 supply for India's BWRs is cut off, it may fuel with U0 2 -Pu0 2 2.2 POLICY ON THE FRONT END OF THE NUCLEAR FUEL CYCLE:The stra1egy is to be independent in all capabilities on the front end of the fuel cycle; this includes uranium mining, milling and conversion, uranium enrichment, fuel fabrication, and heavy water production (NE11/87); India also plans to develop the FBR system, starting with a uranium-plutonium fuel system, then using mixed carbide fuels, andThe Nuclear Power Corporation reports to DAE; it is responsible for design, construction, and operation/maintenance of nuclear power stations Bhabha Atomic Research Center) at Trombay, Bombay, carries out fuel cycle, waste vitrification and disposal R&D, and R&D on uranium ore processing {Murthy 1988); BARC also carries out isotope production and processing; it has five test reactors, a number of pilot-scale facilities for fuel reprocessing, isotope production and processing, fuel materials production {heavy water, zirconium, titanium, thorium) and related R&D; it has facilities for treatment of alpha-emitting wastes (incineration, wet oxidation), immobilization of fuel cladding hulls, and decommissioning R&D; the budget for BAAC for FY-1989-90 is1.8 billion rupees (about $120 million U.S.The Indira Ghandi Centre for Atomic Research) at Kalpak~am carries out fuel cycle R&D, including FBR fuel reprocessing and waste management; it has an interim storage facility for vitrified HLW; it has a fast breeder test reactor and a thorium-fueled test reactor {Kamini reactor, 30 kW); it carries out major R&D on FBA power reactors (NEI 1/90; Leigh and Mitchell 1990); a nuclear science center was established at the University of Madras in 1989 with linkage to IGCAA; the All steps in the production of fuel for nuclear reactors are…”
mentioning
confidence: 99%