The uranium production cycle and the environment. Proceedings

International Nuclear Information System (INIS)

2002-01-01

Within the international community it is widely recognized that the responsibility for management of uranium production and all related activities should be independent of the organizations providing for the oversight and regulatory function. An important role of the IAEA is establishing international safety standards for protection of health and environment against exposure to ionizing radiation. Once legally binding laws, regulations and standards are established,either through national and international programmes, it becomes the responsibility of the management and operators of uranium production projects for carrying our all activities to meet these requirements. The major emphasis of the IAEA's Project on Raw Materials for Reactor Fuels is to improve and strengthen the practice of preventive measures by establishing guidelines for environmental impact assessment and mitigation and the recognition and promotion of good practice and modern technology. The Waste Technology programme provides advice on the cleanup and remediation of old production sites and wastes. One important mechanism for recognizing and promoting best practice in environmental management of uranium production is fostering information exchange among specialists. The IAEA exercises this mechanism, for examples though publications, electronic information exchange and, particularly, through large gatherings of specialists and decision makers at international conferences, symposia and seminars. The topics covered at the symposium were: Energy needs and challenges for the 21 st Century; uranium supply for the short and long term; sustainable development, energy resources and nuclear energy's role in greenhouse gas abatement; economic impact of world mining; impacts of mining on developed and developing countries; environmental and social impacts of uranium mining in several countries; examples of positive and negative impacts of uranium mining projects on local communities; environmental issues

50 years of uranium metal production in Uranium Metal Plant, BARC, Trombay

International Nuclear Information System (INIS)

2009-01-01

The Atomic Energy Programme in India, from the very beginning, has laid emphasis on indigenous capabilities in all aspects of nuclear technology. This meant keeping pace with developments abroad and recognizing the potentials of indigenous technologies. With the development of nuclear programme in India, the importance of uranium was growing at a rapid pace. The production of reactor grade uranium in India started in January 1959 when the first ingot of nuclear pure uranium was discharged using CTR process at Trombay. The decision to set up a uranium refinery to purify the crude uranium fluoride, obtained as a by-product of the DAE's Thorium Plant at Trombay, and to produce nuclear grade pure uranium metal was taken at the end of 1956. The task was assigned to the 'Project Fire Wood Group'. The main objective of the plant was to produce pure uranium metal for use in the Canada India Reactor and Zerlina. Besides this, it was to function as a pilot plant to collect operational data and to train personnel for larger plants to be set up in future. The plant designing and erection work was entrusted to Messrs. Indian Rare Earths Ltd.

Production of uranium in Navoi Mining and Metallurgy Combinat, Uzbekistan

International Nuclear Information System (INIS)

Kuchersky, N.; Tolstov, E.A.; Mazurkevich, A.P.; Inozemzev, S.B.

2001-01-01

Full text: Under the conditions of constantly increasing level of development of the nuclear power, it is inevitable that the uranium stockpiles accumulated to 1985 will soon be depleted. This consideration underlies the development concept of uranium production in the Navoi Mining and Metallurgy Combinat, Uzbekistan. Because this product has become a source of hard currency revenues for the Republic, there will be a significant increase in the processed ore and output of uranium oxide within the next few years. Uranium production in the Navoi Mining and Metallurgy Combinat represents a full-cycle operations ranging from geological survey through hydrometallurgical processing resulting in the output of uranium concentrate in the form of uranium protoxide-oxide (U 3 O 8 ). The NMMC uranium operations include the Hydrometallurgical Plant and three facilities accomplishing ISL mining facilities. A successful start on the development of the Uchkuduk deposit by ISL method in the 1960s gave rise to scientific and production approach for development of other uranium deposits of the infiltration bedded (sandstone) type. Uranium recovery by ISL has become a separate mining branch within the 30-year period of its history and the contribution of this branch in uranium production has steadily grown. Since 1995 all uranium produced by Navoi Mining and Metallurgy Combinat is attributed to ISL. During this evolution period of the ISL method, a whole range of systematic scientific research and practical works were carried out covering improvement of process flowsheets, equipment, operational methods and techniques for particular mining conditions at those specific sites. In co-operation with design and scientific research institutions, a significant number of scientific researches, test works, design and engineering projects were achieved in order to create optimal conditions for ISL mining and further processing of pregnant solutions by sorption as well as to appropriately equip

Decommissioning of U.S. uranium production facilities

Energy Technology Data Exchange (ETDEWEB)

1995-02-01

From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington.

Decommissioning of U.S. uranium production facilities

International Nuclear Information System (INIS)

1995-02-01

From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U 3 O 8 to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington

Uranium Exploration, Resources and Production in South Africa 2009

Energy Technology Data Exchange (ETDEWEB)

Ainslie, L.C., E-mail: lee.ainslie@necsa.co.za [South African Nuclear Energy Agency (Necsa), Pretoria (South Africa)

2014-05-15

The paper gives a brief history of uranium mining in South Africa. The types of uranium deposits in South Africa are described and their distribution given. The majority of uranium is hosted as a by-product in the quartz-pebble conglomerates of the Witwatersrand Basin with lesser amounts in tabular sandstone and coal hosted deposits. The exploration activities of companies operating in South Africa are discussed and the reserves and resources identified are presented. A substantial increase in reserves has been recorded over the last two years because of intensive investigation of known deposits. Only a marginal increase in total resources was reported because of a lack of “greenfield” exploration. Production is far down from the levels achieved in the 1970s and 1980s. The surge in the uranium market resulted in a number of companies investigating their production options. The recent decline in the market has slowed down some of these activities and forced the closure of an operating mine. However a new mine has come into production and feasibility studies are being carried out on other deposits. The recently promulgated Nuclear Energy Policy for the Republic of South Africa defines Necsa’s role in nuclear fuel cycle and the uranium mining industry emphasizing security of supply. South African uranium resources will be able to supply all local needs for the foreseeable future. (author)

Uranium rich granite and uranium productive granite in south China

Energy Technology Data Exchange (ETDEWEB)

Mingyue, Feng; Debao, He [CNNC Key Laboratory of Uranium Resource Exploration and Evaluation Technology, Beijing Research Institute of Uranium Geology (China)

2012-07-15

The paper briefly introduces the differences between uranium rich granite and uranium productive granite in the 5 provinces of South China, and discusses their main characteristics in 4 aspects, the uranium productive granite is highly developed in fracture, very strong in alteration, often occurred as two-mica granite and regularly developed with intermediate-basic and acid dikes. The above characteristics distinguish the uranium productive granite from the uranium rich granite. (authors)

Uranium rich granite and uranium productive granite in south China

International Nuclear Information System (INIS)

Feng Mingyue; He Debao

2012-01-01

The paper briefly introduces the differences between uranium rich granite and uranium productive granite in the 5 provinces of South China, and discusses their main characteristics in 4 aspects, the uranium productive granite is highly developed in fracture, very strong in alteration, often occurred as two-mica granite and regularly developed with intermediate-basic and acid dikes. The above characteristics distinguish the uranium productive granite from the uranium rich granite. (authors)

Uranium production, exploration and mine development in Canada

International Nuclear Information System (INIS)

Vance, R. E

2006-01-01

Full text: Full text: Canada has been the world leader in uranium production since the early 1990's and production in 2005 was 11,629 te U. The Elliott Lake region of Ontario was once the centre of production, but after the last facilities closed in 1996, all production now comes from the Athabasca Basin in northern Saskatchewan. Average grades of the world's two largest high grade deposits at McArthur River and Cigar Lake are 10 to 100 times the grade of deposits mined elsewhere. McArthur River has been in production since late 1999 and first production from Cigar Lake is expected in 2007. If all expansion and probable mine openings come to fruition, annual Canadian production could amount to 16,000 te U by 2011. All currently operating uranium mines have been the subject of a comprehensive environmental assessment and review process. Uranium mining brings significant benefits to local area residents in northern Saskatchewan. Residents of northern Saskatchewan are active participants in Environmental Quality Committees. Recent survey results show the majority of Saskatchewan residents support the continuation of uranium mining in the province. The closed uranium mines in Canada have been successfully decommissioned and rehabilitated in particular in the Elliott Lake region of Ontario. The principle exploration target in Canada remains the Athabasca Basin, but activity has also been reported in several of the other territories and provinces. Natural Resources Canada estimates that some $CAN81M was spent on exploration in Canada in 2005. Under the Canadian Constitution, natural resources are owned by the provinces or by the federal government if they are on federal lands north of 60 0 C latitude. The provinces have jurisdiction over exploration activities within their borders and for most commodities have jurisdiction over mine development and production, operations, health and safety and environmental matters. Once a company starts to develop a deposit into a mine

Uranium production in Sweden

International Nuclear Information System (INIS)

Bergh, S.

1994-01-01

The history of uranium production in Sweden is reviewed in the article. The World War II led to an exploitation of the Swedish alum shale on a large scale. In the last phase of the war it also became obvious that the shale might be used for energy production of quite another kind than oil. In 1947 AB Atom energy was founded, an enterprise with one of its purposes to extract uranium for peaceful use. A plant with a yearly capacity of 120 tons of uranium was erected at Ranstad and ready for production by 1965. From the start in Ranstad and for many years to come there was hardly any interest in an immediate large uranium production. It was decided to use the plant for studies on its more effective exploitation in case of an expansion in the future, bearing in mind the reactor programme. In the course of time economical reasons began to speak against the project. The shale seemed to have a future neither as oil nor as uranium resource. The complete termination of the work on uranium production from shale occurred in 1989

Production of uranium dioxide

International Nuclear Information System (INIS)

Hart, J.E.; Shuck, D.L.; Lyon, W.L.

1977-01-01

A continuous, four stage fluidized bed process for converting uranium hexafluoride (UF 6 ) to ceramic-grade uranium dioxide (UO 2 ) powder suitable for use in the manufacture of fuel pellets for nuclear reactors is disclosed. The process comprises the steps of first reacting UF 6 with steam in a first fluidized bed, preferably at about 550 0 C, to form solid intermediate reaction products UO 2 F 2 , U 3 O 8 and an off-gas including hydrogen fluoride (HF). The solid intermediate reaction products are conveyed to a second fluidized bed reactor at which the mol fraction of HF is controlled at low levels in order to prevent the formation of uranium tetrafluoride (UF 4 ). The first intermediate reaction products are reacted in the second fluidized bed with steam and hydrogen at a temperature of about 630 0 C. The second intermediate reaction product including uranium dioxide (UO 2 ) is conveyed to a third fluidized bed reactor and reacted with additional steam and hydrogen at a temperature of about 650 0 C producing a reaction product consisting essentially of uranium dioxide having an oxygen-uranium ratio of about 2 and a low residual fluoride content. This product is then conveyed to a fourth fluidized bed wherein a mixture of air and preheated nitrogen is introduced in order to further reduce the fluoride content of the UO 2 and increase the oxygen-uranium ratio to about 2.25

Experience of on-site disposal of production uranium-graphite nuclear reactor.

Science.gov (United States)

Pavliuk, Alexander O; Kotlyarevskiy, Sergey G; Bespala, Evgeny V; Zakharova, Elena V; Ermolaev, Vyacheslav M; Volkova, Anna G

2018-04-01

The paper reported the experience gained in the course of decommissioning EI-2 Production Uranium-Graphite Nuclear Reactor. EI-2 was a production Uranium-Graphite Nuclear Reactor located on the Production and Demonstration Center for Uranium-Graphite Reactors JSC (PDC UGR JSC) site of Seversk City, Tomsk Region, Russia. EI-2 commenced its operation in 1958, and was shut down on December 28, 1990, having operated for the period of 33 years all together. The extra pure grade graphite for the moderator, water for the coolant, and uranium metal for the fuel were used in the reactor. During the operation nitrogen gas was passed through the graphite stack of the reactor. In the process of decommissioning the PDC UGR JSC site the cavities in the reactor space were filled with clay-based materials. A specific composite barrier material based on clays and minerals of Siberian Region was developed for the purpose. Numerical modeling demonstrated the developed clay composite would make efficient geological barriers preventing release of radionuclides into the environment. Copyright © 2018 Elsevier Ltd. All rights reserved.

Uranium production economics in Australia

International Nuclear Information System (INIS)

Sorentino, C.M.R.; Butler, R.D.; Thomas, C.M.; McIlveen, G.R.; Huxlin, M.E.

1990-02-01

This review of the economics of production of uranium in Australia provides a detailed description of eleven important uranium deposits including capital and production costs estimates and supply curves. For each mine a detailed assessment has been made of its potential production capacity to the year 2000. Socio-economic factors that play an all-too-important role in the Australian uranium industry are extensively reviewed to provide an insight into the factors affecting Australia's ability to supply. The study is based on a detailed computer-based economic engineering model where all major costs such as labor, consumables and capital recovery charges are analyzed for each mine, and levellised break-even prices determined. It is argued that at the present low market prices, the three on-going operations are profitable, and at least three other deposits could be brought to viable production, given the necessary Government approval. Several other deposits appear to be marginal at the set Australian export floor price of US$26 per pound. Annual production could be raised from about 6,000 tonnes of U 3 O 8 to 16,000 tonnes by the turn of century, with the development of three additional deposits. It is concluded that, if Australian producers were allowed to compete freely on the international market, annual production would pass the 10,000 tonne/annum mark between 1995 and 2000. 35 figs., 38 tabs., 81 refs

Eldorado Port Hope refinery - uranium production (1933-1951)

International Nuclear Information System (INIS)

Arsenault, J.E.

2008-01-01

Since the discovery of pitchblende in 1930 by Gilbert LaBine at Great Bear Lake (GBL), North West Territories, uranium has played a central role in the growth of the Canadian mining sector and it in turn has propelled the country into it's present position as the world's top uranium producer. The rich ore mined there was used originally by Eldorado Gold Mines Limited to build a business based on the extraction of radium, which was selling at $70,000 a gram at the time, and silver which was present in the ore in commercial amounts. The mine site on GBL became known as Port Radium. In 1933 Eldorado brought a refinery on-line at Port Hope, Ontario nearly 4,000 miles away from the mine, and began to produce radium, silver and uranium products. Initially uranium played a minor role in the business and the products were sold into the ceramics industry to manufacture a variety of crockery with long-lasting colours. In addition, there were sales and loans of uranium products to research laboratories that were exploring nuclear energy for possible use in weapons and power generation, as the potential for this was clearly understood from 1939 onwards. These laboratories included the National Research Council (George Laurence), Columbia University (Enrico Fermi) and International Chemical Industries (J.P. Baxter). With the beginning of World War II the radium business suffered from poor sales and by 1940 the mine was closed but the refinery continued operation, using accumulated stockpiles. By 1942 uranium had become a strategic material, the mine was reopened, and the refinery began to produce large quantities of uranium oxide destined for The Manhattan Project. As events unfolded Eldorado was unable to produce sufficient ore from GBL so that a large quantity of ore from the Belgian Congo was also processed at Port Hope. Ultimately, as a result of the efforts of this enterprise, World War II was finally ended by use of atomic weapons. After World War II the refinery

Eldorado Port Hope refinery - uranium production (1933-1951)

Energy Technology Data Exchange (ETDEWEB)

Arsenault, J.E

2008-03-15

Since the discovery of pitchblende in 1930 by Gilbert LaBine at Great Bear Lake (GBL), North West Territories, uranium has played a central role in the growth of the Canadian mining sector and it in turn has propelled the country into it's present position as the world's top uranium producer. The rich ore mined there was used originally by Eldorado Gold Mines Limited to build a business based on the extraction of radium, which was selling at $70,000 a gram at the time, and silver which was present in the ore in commercial amounts. The mine site on GBL became known as Port Radium. In 1933 Eldorado brought a refinery on-line at Port Hope, Ontario nearly 4,000 miles away from the mine, and began to produce radium, silver and uranium products. Initially uranium played a minor role in the business and the products were sold into the ceramics industry to manufacture a variety of crockery with long-lasting colours. In addition, there were sales and loans of uranium products to research laboratories that were exploring nuclear energy for possible use in weapons and power generation, as the potential for this was clearly understood from 1939 onwards. These laboratories included the National Research Council (George Laurence), Columbia University (Enrico Fermi) and International Chemical Industries (J.P. Baxter). With the beginning of World War II the radium business suffered from poor sales and by 1940 the mine was closed but the refinery continued operation, using accumulated stockpiles. By 1942 uranium had become a strategic material, the mine was reopened, and the refinery began to produce large quantities of uranium oxide destined for The Manhattan Project. As events unfolded Eldorado was unable to produce sufficient ore from GBL so that a large quantity of ore from the Belgian Congo was also processed at Port Hope. Ultimately, as a result of the efforts of this enterprise, World War II was finally ended by use of atomic weapons. After World War II the

The IAEA network on environmental management and remediation (ENVIRONET) - promoting sustainable uranium production operations by taking environmental remediation under a life-cycle perspective

International Nuclear Information System (INIS)

Monken-Fernandes, H.

2010-01-01

Some of the past uranium production operations have caused extensive environmental problems. The lack of appropriate regulatory framework in addition to the fact that environmental issues were not conveniently addressed in the operations contributed to this situation. Nowadays, this situation has changed dramatically and lessons learned from the past have led to the implementation of responsible operations from both environmental and social perspectives. Involvement of different stakeholders in the decision making process turned out to be a mandatory issue in many countries. With the so called 'Renascence of Nuclear Power' new production sites will come into play. The sustainability of the uranium industry will depend on the adoption of good practices in these operations under a life-cycle perspective. The recently launched IAEA initiative - the ENVIRONET is aimed at contributing to expedite the transfer of experience amongst its members. It brings together private and state-owned companies, research institutes, and governmental organizations providing a forum for information and experience exchange. Sharing of practical experience is to be addressed by means of training courses and workshops. In addition to this long distance training and educational material will be made available. This paper will present the ENVIRONET and describe how networking can contribute to the implementation of sustainable and responsible uranium production operations worldwide. (author)

Solvent extraction of uranium: Towards good practice in design, operation and management

International Nuclear Information System (INIS)

Bartsch, P.; Hall, S.; Ballestrin, S.; Hunt, A.

2014-01-01

Uranium solvent extraction, USX has been applied commercially for recovery and concentration for over 60 years. Uranium in acidic liquor, which is prepared following ore leaching, solid/liquid separation and clarification, can be treated through a sequence of operations; extraction-scrubbing-stripping, to obtain purified liquor, and hence precipitation of marketable products. USX has dominated the primary uranium industry as the preferred technological route for recovery of uranium into converter grade yellowcake or Uranium Ore Concentrate. The practices of design and operation of USX facilities has found renewed interest as new mines are developed following decades of industry dormancy. Development of the Olympic Dam and Honeymoon operations in Australia has lead to innovative design and operation of pulsed columns technology in applications of solvent extraction. This article seeks to outline principles of design and operation from the practitioner’s perspective. The discussion also reviews historical developments of USX applications and highlights recent innovations. This review is hoped to provide guidance for technical personnel who wish to learn more about good practices that leads to reliable USX performance. (author)

Uranium 2014: Resources, Production and Demand - Executive Summary

International Nuclear Information System (INIS)

2014-01-01

Uranium is the raw material used to fuel over 400 operational nuclear reactors around the world that produce large amounts of electricity and benefit from life cycle carbon emissions as low as renewable energy sources. Although a valuable commodity, declining market prices for uranium since the Fukushima Daiichi nuclear power plant accident in 2011, driven by uncertainties concerning the future of nuclear power, have led to the postponement of mine development plans in a number of countries and raised questions about continued uranium supply. This 25. edition of the 'Red Book', a recognised world reference on uranium jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, provides analyses and information from 45 producing and consuming countries in order to address these and other questions. It includes data on global uranium exploration, resources, production and reactor-related requirements. It offers updated information on established uranium production centres and mine development plans, as well as projections of nuclear generating capacity and reactor-related requirements through 2035, incorporating policy changes following the Fukushima accident, in order to address long-term uranium supply and demand issues. (authors)

Uranium production

International Nuclear Information System (INIS)

Jones, J.Q.

1981-01-01

The domestic uranium industry is in a state of stagflation. Costs continue to rise while the market for the product remains stagnant. During the last 12 months, curtailments and closures of mines and mills have eliminated over 5000 jobs in the industry, plus many more in those industries that furnish supplies and services. By January 1982, operations at four mills and the mines that furnish them ore will have been terminated. Other closures may follow, depending on cost trends, duration of current contracts, the degree to which mills have been amortized, the feasibility of placing mines on standby, the grade of the ore, and many other factors. Open-pit mines can be placed on standby without much difficulty, other than the possible cost of restoration before all the ore has been removed. There are a few small, dry, underground mines that could be mothballed; however, the major underground producers are wet sandstone mines that in most cases could not be reopened after a prolonged shutdown; mills can be mothballed for several years. Figure 8 shows the location of all the production centers in operation, as well as those that have operated or are on standby. Table 1 lists the same production centers plus those that have been deferred, showing nominal capacity of conventional mills in tons of ore per calendar day, and the industry production rate for those mills as of October 1, 1981

World uranium production in 1995

International Nuclear Information System (INIS)

Anon.

1996-01-01

For the first time since the political and economic opening of the former Soviet Union and Eastern Europe, world uranium production actually increased in 1995. Preliminary estimates for 1996 continue this trend, indicating additional (if slight) production increases over 1995 levels. Natural uranium production increased by about 5% in 1995 to 34,218 tons uranium or 89 Mlbs U3O8. This is an increase of approximately 1700 tons of uranium or 4.3 Mlbs of U3O8 over the updated 1994 quantities. Data is presented for each of the major uranium producing countries, for each of the world's largest uranium mines, for each of the world's largest corporate producers, and for major regions of the world

Enabling sustainable uranium production: The Inter-regional Technical Cooperation experience

International Nuclear Information System (INIS)

Tulsidas, H.; Zhang, J.

2014-01-01

Uranium production cycle activities are increasing worldwide, often in countries with little or no previous experience in such activities. Initial efforts in uranium exploration and mining were limited to a few countries, which progressed through a painful learning curve often associated with high socioeconomic costs. With time, good practices for the sustainable conduct of operations became well established, but new projects in different regional contexts continue to face challenges. Moreover, there have been highs and lows in the levels of activities and operations in the uranium industry, which has disrupted the stabilizing of the experiences and lessons learned, into a coherent body of knowledge. This collective experience, assimilated over time, has to be transferred to a new generation of experts, who have to be enabled to use this knowledge effectively in their local contexts in order to increase efficiency and reduce the footprint of the operations. This makes it sustainable and socially acceptable to local communities, as well as in the global context. IAEA has implemented several projects in the last five years to address gaps in transferring a coherent body of knowledge on sustainable uranium production from a well experienced generation of experts to a new generation facing similar challenges in different geographical, technological, economic and social contexts. These projects focused on enabling the new practitioners in the uranium production industry to avoid the mistakes of the past and to apply good practices established elsewhere, adapted to local needs. The approach was intended to bring considerable cost savings while attracting elevated levels of social acceptance. These projects were effective in introducing experts from different areas of the uranium production cycle and with different levels of experience to the availability of advanced tools that can make operations more efficient and productive, reduce footprint, increase competencies in

Uranium in South Africa: 1983 assessment of resources and production

International Nuclear Information System (INIS)

1984-06-01

NUCOR assesses South Africa's uranium resource and production capabilities on an ongoing basis. Assessments are carried out in close co-operation with the mining companies and the Government Mining Engineer. In carrying out this evaluation, the classification recommended by the NEA/IAEA Working Party on Uranium Resources is followed. In order to preserve company confidentiality, the details of the findings are released in summary form only. Within South Africa, uranium occurrences are found in Precambrian quartz-pebble conglomerates, Precambrian alkaline complexes, Cambrian to Precambrian granite gneisses, Permo-Triassic sandstones and coal, and Recent to Tertiary surficial formations. South Africa's uranium resources were reassessed during 1983 and the total recoverable resources in the Reasonably Assured and Estimated Additional Resource categories recoverable at less than $130/kg U were estimated to be 460 000 t U. This represents a decrease of 13,4% when compared with the 1981 assessment. South Africa's uranium production for 1983 amounted to 6 060 t U, a 4,21 % increase over the 1982 production of 5 816 t U. Ninety-seven percent of the production is derived from the Witwatersrand quartz-pebble conglomerates, the rest being produced as a by-product of copper mining at Palabora. South Africa maintained its position as a major low-cost uranium producer, holding 14% of the WOCA uranium resources, and during 1982 it produced 14% of WOCA's uranium. In making future production capability projections it may be safely concluded that South Africa would be able to produce uranium at substantial levels well into the next century

Uranium. Resources, production and demand

International Nuclear Information System (INIS)

1997-01-01

The events characterising the world uranium market in the last several years illustrate the persistent uncertainly faced by uranium producers and consumers worldwide. With world nuclear capacity expanding and uranium production satisfying only about 60 per cent of demand, uranium stockpiles continue to be depleted at a high rate. The uncertainty related to the remaining levels of world uranium stockpiles and to the amount of surplus defence material that will be entering the market makes it difficult to determine when a closer balance between uranium supply and demand will be reached. Information in this report provides insights into changes expected in uranium supply and demand until well into the next century. The 'Red Book', jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, is the foremost reference on uranium. This world report is based on official information from 59 countries and includes compilations of statistics on resources, exploration, production and demand as of 1 January 1997. It provides substantial new information from all of the major uranium producing centres in Africa, Australia, Eastern Europe, North America and the New Independent States, including the first-ever official reports on uranium production in Estonia, Mongolia, the Russian Federation and Uzbekistan. It also contains an international expert analysis of industry statistics and worldwide projections of nuclear energy growth, uranium requirements and uranium supply

Uranium 2009: Resources, Production and Demand

International Nuclear Information System (INIS)

2010-01-01

With several countries currently building nuclear power plants and planning the construction of more to meet long-term increases in electricity demand, uranium resources, production and demand remain topics of notable interest. In response to the projected growth in demand for uranium and declining inventories, the uranium industry - the first critical link in the fuel supply chain for nuclear reactors - is boosting production and developing plans for further increases in the near future. Strong market conditions will, however, be necessary to trigger the investments required to meet projected demand. The 'Red Book', jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, is a recognised world reference on uranium. It is based on information compiled in 40 countries, including those that are major producers and consumers of uranium. This 23. edition provides a comprehensive review of world uranium supply and demand as of 1 January 2009, as well as data on global uranium exploration, resources, production and reactor-related requirements. It provides substantive new information from major uranium production centres around the world, as well as from countries developing production centres for the first time. Projections of nuclear generating capacity and reactor-related uranium requirements through 2035 are also featured, along with an analysis of long-term uranium supply and demand issues

Uranium 2003 resources, production and demand

CERN Document Server

Organisation for Economic Cooperation and Development. Paris

2004-01-01

Uranium 2003: Resources, Production and Demand paints a detailed statistical profile of the world uranium industry in the areas of exploration, resource estimates, production and reactor-related requirements. It provides substantial new information from all major uranium production centres in Africa, Australia, Eastern Europe and North America and for the first time, a report for Turkmenistan. Also included are international expert analyses and projections of nuclear generating capacity and reactor-related uranium requirements through 2020.

International overview of ISL uranium mining operations

International Nuclear Information System (INIS)

Woods, P.; Slezak, J.; Pool, T.; Beneš, V.; Gorbatenko, O.; Jones, B.; Märten, H.; Solodov, I.

2014-01-01

In situ leach (ISL; also called in situ leaching or in situ recovery, ISR) mining has become one of the standard uranium production methods, following early experimentation and production in the 1960s. Its application to amenable uranium deposits (in certain sedimentary formations) has been growing in view of its competitive production costs and low surface impacts. In 1997 the ISL share in total uranium production was 13%; by 2009 it had grown to over 30%, reaching 46% in 2011. In the past, ISL technology was applied mainly in Ukraine, the Czech Republic, Uzbekistan, Kazakhstan, Bulgaria and the United States of America (USA). Recently it has been used in Kazakhstan, Uzbekistan, the USA, Australia, China and the Russian Federation, with small operations or experiments elsewhere. ISL mining is gaining widespread acceptance. The IAEA is preparing an overview document to show how ISL experience around the world can be used to direct the development of technical activities, taking into account environmental considerations and an emphasis on the economics of the process, including responsible mine closure. With this document Member States and interested parties will have more information to design and efficiently and safely regulate current and future projects, with a view to maximize economic performance and minimize negative environmental impact. Highlights of the report’s findings will be provided here with a summary of the IAEA’s involvement in ISL over recent decades. Many reference links are provided to allow access to voluminous additional information. (author)

Uranium 2005 Resources, Production and Demand

CERN Document Server

Organisation for Economic Cooperation and Development. Paris. Nuclear Energy Agency

2006-01-01

Published every other year, Uranium Resources, Production, and Demand, or the "Red Book" as it is commonly known, is jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency. It is the recognised world reference on uranium and is based on official information received from 43 countries. This 21st edition presents the results of a thorough review of world uranium supplies and demand as of 1st January 2005 and provides a statistical profile of the world uranium industry in the areas of exploration, resource estimates, production and reactor-related requirements. It provides substantial new information from all major uranium production centres in Africa, Australia, Central Asia, Eastern Europe and North America. Projections of nuclear generating capacity and reactor-related uranium requirements through 2025 are provided as well as a discussion of long-term uranium supply and demand issues. This edition focuses on recent price and production increases that could signal major c...

Uranium 2014 resources, production and demand

CERN Document Server

Organisation for Economic Cooperation and Development. Paris

2014-01-01

Published every other year, Uranium Resources, Production, and Demand, or the "Red Book" as it is commonly known, is jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency. It is the recognised world reference on uranium and is based on official information received from 43 countries. It presents the results of a thorough review of world uranium supplies and demand and provides a statistical profile of the world uranium industry in the areas of exploration, resource estimates, production and reactor-related requirements. It provides substantial new information from all major uranium production centres in Africa, Australia, Central Asia, Eastern Europe and North America. Long-term projections of nuclear generating capacity and reactor-related uranium requirements are provided as well as a discussion of long-term uranium supply and demand issues. This edition focuses on recent price and production increases that could signal major changes in the industry.

The US uranium industry's operations and financial performance during 1988

International Nuclear Information System (INIS)

Walton, H.

1989-01-01

This paper presents the operating and financial statistics collected from the U.S. uranium industry by the Energy Information Administration (EIA). Uranium concentrate production probably is the most important indicator of overall activity in the domestic raw materials industry. Production in 1988 of 13.1 million pounds U 3 O 8 was only slightly higher than 1987 production, however it was about 70 percent less than the peak production level of 43.7 million pounds recorded in 1980. Production in 1988 from conventional milling was 7.0 million pounds, a decrease of 18 percent from the 8.5 million pounds produced in 1987. Production from nonconventional facilities in 1988 was 6.1 million pounds U 3 O 8 , and increase of 37 percent above the level for 1987. This is the highest level for production from nonconventional facilities since 1981

Uranium 2003: resources, production and demand

International Nuclear Information System (INIS)

2004-01-01

The 'Red Book', jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, is a recognised world reference on uranium. This edition, the 20., presents the results of a thorough review of world uranium supplies and demand as of 1 January 2003 based on official information received from 43 countries. Uranium 2003: Resources, Production and Demand paints a statistical profile of the world uranium industry in the areas of exploration, resource estimates, production and reactor related requirements. It provides substantial new information from all major uranium production centres in Africa, Australia, Eastern Europe and North America and for the first time, a report for Turkmenistan. Also included are international expert analyses and projections of nuclear generating capacity and reactor-related uranium requirements through 2020. The long lead times required to bring resources into production underscore the importance of making timely decisions to pursue production capability well in advance of any supply shortfall. (author)

Uranium tetrafluoride production via dioxide by wet process

International Nuclear Information System (INIS)

Aquino, A.R. de.

1988-01-01

The study for the wet way obtention of uranium tetrafluoride by the reaction of hydrofluoric acid and powder uranium dioxide, is presented. From the results obtained at laboratory scale a pilot plant was planned and erected. It is presently in operation for experimental data aquisition. Time of reaction, temperature, excess of reagents and the hydrofluoric acid / uranium dioxide ratio were the main parameters studied to obtain a product with the following characteristics: - density greater than 1 g/cm 3 , conversion rate greater than 96%, and water content equal to 0,2% that allows its application to heaxafluoride convertion or to magnesiothermic process. (author) [pt

The assisting system for uranium enrichment plant operation

International Nuclear Information System (INIS)

Nakazawa, Hiroaki; Yamamoto, Fumio

1990-01-01

We have been developing an operation assisting system, partially supported by AI system, for uranium enrichment plant. The AI system is a proto-type system aiming a final one which can be applied to any future large uranium enrichment plant and also not only to specific operational area but also to complex and multi-phenomenon operational area. An existing AI system, for example facility diagnostic system that utilizes the result of CCT analysis as knowledge base, has weakness in flexibility and potentiality. To build AI system, we have developed the most suitable knowledge representations using deep knowledge for each facility or operation of uranium enrichment plant. This paper describes our AI proto-type system adopting several knowledge representations that can represent an uranium enrichment plant's operation with deep knowledge. (author)

Uranium 2007 resources, production and demand

CERN Document Server

Organisation for Economic Cooperation and Development. Paris

2008-01-01

Based on official information received from 40 countries, Uranium 2007 provides a comprehensive review of world uranium supply and demand as of 1st January 2007, as well as data on global uranium exploration, resources, production and reactor-related requirements. It provides substantive new information from major uranium production centres in Africa, Australia, Central Asia, Eastern Europe and North America. Projections of nuclear generating capacity and reactor-related uranium requirements through 2030 are also featured, along with an analysis of long-term uranium supply and demand issues. It finds that with rising demand and declining inventories, uranium prices have increased dramatically in recent years. As a result, the uranium industry is undergoing a significant revival, bringing to an end a period of over 20 years of underinvestment.

Felder uranium project--renewed operations

International Nuclear Information System (INIS)

Anon.

1979-01-01

Exxon owns a uranium mill and holds two mining leases in Live Oak County, Texas, about halfway between San Antonio and Corpus Christi. The properties made up the Felder Uranium Operations which was reopened earlier this year. The feasibility study for reopening the Felder Project began in late 1975 and was not completed until late 1976. This paper discusses several areas of the feasibility study that required additional work prior to making the decision to renew operations. Mine planning evaluation and the actual mine planning are described briefly

URANIUM 1991 resources, production and demand

International Nuclear Information System (INIS)

1992-01-01

The uranium supply aspects of the nuclear fuel cycle have undergone considerable change during the last few years. Nuclear power generating capacity can continue to expand only if there is confidence in the final supply of uranium. This report presents governmental compilations of uranium resource and production data, as established in 1991. It also presents short-term projections of the nuclear industry future natural uranium requirements and reviews the status of uranium exploration, resources and production throughout the world. 10 refs., 14 figs., 15 tabs., 6 appendices

Operating and life-cycle costs for uranium-contaminated soil treatment technologies

International Nuclear Information System (INIS)

Douthat, D.M.; Armstrong, A.Q.

1995-09-01

The development of a nuclear industry in the US required mining, milling, and fabricating a large variety of uranium products. One of these products was purified uranium metal which was used in the Savannah River and Hanford Site reactors. Most of this feed material was produced at the US Department of Energy (DOE) facility formerly called the Feed Materials Production Center at Fernald, Ohio. During operation of this facility, soils became contaminated with uranium from a variety of sources. To avoid disposal of these soils in low-level radioactive waste burial sites, increasing emphasis has been placed on the remediating soils contaminated with uranium and other radionuclides. To address remediation and management of uranium-contaminated soils at sites owned by DOE, the DOE Office of Technology Development (OTD) evaluates and compares the versatility, efficiency, and economics of various technologies that may be combined into systems designed to characterize and remediate uranium-contaminated soils. Each technology must be able to (1) characterize the uranium in soil, (2) decontaminate or remove uranium from soil, (3) treat or dispose of resulting waste streams, (4) meet necessary state and federal regulations, and (5) meet performance assessment objectives. The role of the performance assessment objectives is to provide the information necessary to conduct evaluations of the technologies. These performance assessments provide the basis for selecting the optimum system for remediation of large areas contaminated with uranium. One of the performance assessment tasks is to address the economics of full-scale implementation of soil treatment technologies. The cost of treating contaminated soil is one of the criteria used in the decision-making process for selecting remedial alternatives

Human Resource Development for Uranium Production Cycle

International Nuclear Information System (INIS)

Ganguly, C.

2014-01-01

Concluding Remarks & Suggestions: • HRD will be one of the major challenges in the expanding nuclear power program in countries like China and India. • China and India get uranium raw material from domestic mines and international market. In addition, China has overseas uranium property. India is also exploring the possibility of overseas Joint Venture and uranium properties. For uranium production cycle there is a need for trained geologist, mining engineers, chemical and mechanical engineers. • There is a need for introducing specialization course on “uranium production cycle” at post graduate levels in government and private universities. Overseas Utilities and private firms in India engaged in nuclear power and fuel cycle activities may like to sponsor MTech students with assurance of employment after the successful completion of the course. • The IAEA may consider to extend Technical Assistance to universities in HRD in nuclear power and fuel cycle in general and uranium production cycle in particular - IAEA workshops, with participation of international experts, on uranium geology, mining, milling and safety and best practices in uranium production cycle will be of great help. • The IAEA – UPSAT could play an important role in HRD in uranium production cycle

The uranium resources and production of Namibia

International Nuclear Information System (INIS)

Palfi, A.G.

1997-01-01

The promulgation of the Minerals (Prospecting and Mining) Act, 1992, on 1 April 1994 and the simultaneous repeal of restrictive South African legislation on reporting uranium exploration and production results, allowed the Namibian Government for the first time to present information for publication of the report ''Uranium 1995 - Resource, Production and Demand'', by the OECD Nuclear Energy Agency and the IAEA. Namibia, one of the youngest independent nations in Africa, has a large number of uranium occurrences and deposits in several geological environments. The total estimated uranium resource amounts to about 299 thousand tonnes recoverable uranium at a cost of less than US$ 130/kg U, within the known conventional resources category. The most prominent geological type of these is the unique, granite-related uranium occurrences located in the central part of the Namib Desert. Permo-Triassic age Karoo sandstone-hosted uranium deposits were subject to only limited exploration due to the down-turn of uranium prices in the latter part of 1980s, despite they very encouraging exploration results. As only limited Karoo sandstone-covered areas were tested there is still great potential for further discoveries. The planned output of Roessing Uranium Mine at 40,000 tonnes of ore per day which results in an annual production of 4536 tonnes of uranium oxide, was achieved in 1979. In case of improved uranium market conditions, Namibia is in a strong position to increase uranium production and open up new production centres to strengthen the country's position as an important uranium producer in the world. 6 figs, 2 tabs

Recent developments in uranium exploration, production and environmental issues. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2005-09-01

The uranium industry is in a period of transition. In Europe, the industry is in transition from uranium production to site rehabilitation. The WISMUT project in Germany, which is featured in this publication, is the largest and one of the most advanced rehabilitation projects in the world. By contrast, other countries such as China, India and Argentina are expanding their industries to meet growing uranium demand. Activities in these countries, which are also described in this publication, range from new project licensing to application of new technology to increase productivity and lower costs at existing operations. Changes within the uranium industry are nowhere more evident than in the marketplace, where the price of uranium has more than doubled in the past two years. There is a discussion of the reasons for this price rise and the adequacy of production capacity to meet reactor uranium requirements. Many developing countries are striving for self-sufficiency in their uranium production capabilities. Accordingly, the papers deal with a range of topics including uranium exploration, project licensing, and research directed towards improving uranium production efficiency and costs. European papers emphasize uranium site rehabilitation, reflecting the fact that uranium production has all but ceased in Europe. These papers describe site remediation technology that is being utilized at a variety of sites ranging from tailings ponds to mine water treatment plants. The recent rapid increase in the uranium market price has dominated discussions among uranium producers and users alike. Not surprisingly the price increase was also a much-discussed topic at this Technical Meeting. One paper reviewed the reasons for the rapid price increase and the relationship between market price and uranium supply-demand relationships. Uranium production is likely to become more important to Niger's economy if the recent price increase is sustainable. Accordingly, Niger's uranium

Uranium 2011: Resources, Production and Demand

International Nuclear Information System (INIS)

2012-01-01

In the wake of the Fukushima Daiichi nuclear power plant accident, questions are being raised about the future of the uranium market, including as regards the number of reactors expected to be built in the coming years, the amount of uranium required to meet forward demand, the adequacy of identified uranium resources to meet that demand and the ability of the sector to meet reactor requirements in a challenging investment climate. This 24. edition of the 'Red Book', a recognised world reference on uranium jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, provides analyses and information from 42 producing and consuming countries in order to address these and other questions. It offers a comprehensive review of world uranium supply and demand as well as data on global uranium exploration, resources, production and reactor-related requirements. It also provides substantive new information on established uranium production centres around the world and in countries developing production centres for the first time. Projections of nuclear generating capacity and reactor-related requirements through 2035, incorporating policy changes following the Fukushima accident, are also featured, along with an analysis of long-term uranium supply and demand issues

Uranium production

International Nuclear Information System (INIS)

Spriggs, M.

1980-01-01

The balance between uranium supply and demand is examined. Should new resources become necessary, some unconventional sources which could be considered include low-grade extensions to conventional deposits, certain types of intrusive rock, tuffs, and lake and sea-bed sediments. In addition there are large but very low grade deposits in carbonaceous shales, granites, and seawater. The possibility of recovery is discussed. Programmes of research into the feasibility of extraction of uranium from seawater, as a by-product from phosphoric acid production, and from copper leach solutions, are briefly discussed. Other possible sources are coal, old mine dumps and tailings, the latter being successfully exploited commercially in South Africa. The greatest constraints on increased development of U from lower grade sources are economics and environmental impact. It is concluded that apart from U as a by-product from phosphate, other sources are unlikely to contribute much to world requirements in the foreseeable future. (U.K.)

Uranium 2014: Resources, Production and Demand

International Nuclear Information System (INIS)

Vance, Robert

2014-01-01

Since the mid-1960's, with the co-operation of their member countries and states, the OECD Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA) have jointly prepared periodic updates (currently every two years) on world uranium resources, production and demand. Published by the OECD/NEA in what is commonly known as the 'Red Book', the 25. edition, released in September 2014, contains 45 national reports covering uranium producing and consuming countries and those with plans to do so. The uranium resource figures presented in the 25. edition of the Red Book are a snapshot of the situation as of 1 January 2013. Resource figures are dynamic and related to commodity prices. Despite less favourable market conditions, continued high levels of investment and associated exploration efforts have resulted in the identification of additional resources of economic interest, just as in past periods of intense exploration activity. Total identified resources (reasonably assured and inferred) as of 1 January 2013 amounted to 5 902 900 tonnes of uranium metal (tU) in the 3 O 8 ) category, an increase of 10.8% compared to 1 January 2011. In the highest cost category ( 3 O 8 ) which was reintroduced in 2009, total identified resources amounted to 7 635 200 tU, an increase of 7.6% compared to the total reported in 2011. The majority of the increases are a result of re-evaluations of previously identified resources and additions to known deposits, particularly in Australia, Canada, the People's Republic of China, the Czech Republic, Greenland, Kazakhstan and South Africa. Worldwide exploration and mine development expenditures in 2012 totalled USD 1.92 billion, a 21% increase over updated 2010 figures, despite declining market prices. Production in 2012 increased by 7.4% from 2011 to 58 816 tU and is expected to increase to over 59 500 tU in 2013. This recent growth is principally the result of increased production in Kazakhstan, which remains the world

Uranium production from low grade Swedish shale

International Nuclear Information System (INIS)

Carlsson, O.

1977-01-01

In view of the present nuclear programmes a steep increase in uranium demand is foreseen which will pose serious problems for the uranium industry. The annual additions to uranium ore reserves must almost triple within the next 15 years in order to support the required production rates. Although there are good prospects for the discovery of further conventional deposits of uranium there is a growing interest in low grade uranium deposits. Large quantities of uranium exist in black shales, phosphates, granites, sea water and other unconventional sources. There are however factors which limit the utilization of these low grade materials. These factors include the extraction costs, the environmental constrains on mining and milling of huge amounts of ore, the development of technologies for the beneficiation of uranium and, in the case of very low grade materials, the energy balance. The availability of by-product uranium is limited by the production rate of the main product. The limitations differ very much according to types of ores, mining and milling methods and the surroundings. As an illustration a description is given of the Swedish Ranstad uranium shale project, its potential, constraints and technical solutions

Uranium resources, production and demand

International Nuclear Information System (INIS)

1988-01-01

Nuclear power-generating capacity will continue to expand, albeit at a slower pace than during the past fifteen years. This expansion must be matched by an adequately increasing supply of uranium. This report compares uranium supply and demand data in free market countries with the nuclear industry's natural uranium requirements up to the year 2000. It also reviews the status of uranium exploration, resources and production in 46 countries

77 FR 33782 - License Amendment To Construct and Operate New In Situ Leach Uranium Recovery Facility; Uranium...

Science.gov (United States)

2012-06-07

... and Operate New In Situ Leach Uranium Recovery Facility; Uranium One Americas; Ludeman AGENCY: Nuclear... provided the first time that a document is referenced. The Ludeman facility In Situ Leach Uranium Recovery... request to amend Source Material License SUA-1341 to construct and operate a new in situ leach uranium...

Uranium 1999. Resources, production and demand

International Nuclear Information System (INIS)

2000-01-01

In recent years, the world uranium market has been characterised by an imbalance between demand and supply and persistently depressed uranium prices. World uranium production currently satisfies between 55 and 60 per cent of the total reactor-related requirements, while the rest of the demand is met by secondary sources including the conversion of excess defence material and stockpiles, primarily from Eastern Europe. Although the future availability of these secondary sources remains unclear, projected low-cost production capability is expected to satisfy a considerable part of demand through to 2015. Information in this report provides insights into changes expected in uranium supply and demand over the next 15 years. The 'Red Book', jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, is the foremost world reference on uranium. It is based on official information from 49 countries and includes compilations of statistics on resources, exploration, production and demand as of 1 January 1999. It provides substantial new information from all of the major uranium producing centres in Africa, Australia, Eastern Europe, North America and the New Independent States. It also contains an international expert analysis of industry statistics and world-wide projections of nuclear energy growth, uranium requirements and uranium supply. (authors)

Uranium resources, production and demand 1993

International Nuclear Information System (INIS)

1994-10-01

This book is the Japanese edition of 'Uranium Resources, Production and Demand, 1993' published by OECD/NEA-IAEA in 1994. It contains data on uranium exploration activities, resources and production for about 50 countries. (K.I.)

UPSAT guidelines. 1996 edition. Reference document for IAEA Uranium Productions Safety Assessment Teams (UPSATs)

International Nuclear Information System (INIS)

1996-05-01

The IAEA Uranium Production Safety Assessment Team (UPSAT) programme provides advice and assistance to Member States to enhance the safety and environmental performance of uranium production facilities during construction, commissioning and operation. Sound design and construction are prerequisite for the safe and environmentally responsible operation of uranium mines and mills. However, the safety of the facility depends ultimately on sound policies, procedures and practices; on the capability and reliability of the construction, commissioning and operating personnel; on comprehensive instructions; and on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. The UPSAT guidelines have been developed in the following areas: (1) management, organization and administration; (2) training and qualification; (3) operation (4) maintenance; (5) safety, fire protection, emergency planning, and preparedness; (6) radiation protection; (7) environmental monitoring programme; (8) construction management; (9) commissioning and decommissioning

Uranium 2011 resources, production and demand

CERN Document Server

Organisation for Economic Cooperation and Development. Paris

2012-01-01

In the wake of the Fukushima Daiichi nuclear power plant accident, questions are being raised about the future of the uranium market, including as regards the number of reactors expected to be built in the coming years, the amount of uranium required to meet forward demand, the adequacy of identified uranium resources to meet that demand and the ability of the sector to meet reactor requirements in a challenging investment climate. This 24th edition of the “Red Book”, a recognised world reference on uranium jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, provides analyses and information from 42 producing and consuming countries in order to address these and other questions. It offers a comprehensive review of world uranium supply and demand as well as data on global uranium exploration, resources, production and reactor-related requirements. It also provides substantive new information on established uranium production centres around the world and in countri...

Uranium 2007: resources, production and demand

International Nuclear Information System (INIS)

2008-01-01

With several countries building nuclear power plants and many more considering the use of nuclear power to produce electricity in order to meet rising demand, the uranium industry has become the focus of considerable attention. In response to rising demand and declining inventories, uranium prices have increased dramatically in recent years. As a result, the uranium industry is undergoing a significant revival, bringing to an end a period of over 20 years of under investment. The ''Red Book'', jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, is a recognised world reference on uranium. It is based on official information received from 40 countries. This 22. edition provides a comprehensive review of world uranium supply and demand as of 1. January 2007, as well as data on global uranium exploration, resources, production and reactor-related requirements. It provides substantive new information from major uranium production centres in Africa, Australia, Central Asia, Eastern Europe and North America. Projections of nuclear generating capacity and reactor-related uranium requirements through 2030 are also featured, along with an analysis of long-term uranium supply and demand issues. (author)

Uranium 2007: resources, production and demand

International Nuclear Information System (INIS)

2008-01-01

With several countries building nuclear power plants and many more considering the use of nuclear power to produce electricity in order to meet rising demand, the uranium industry has become the focus of considerable attention. In response to rising demand and declining inventories, uranium prices have increased dramatically in recent years. As a result, the uranium industry is undergoing a significant revival, bringing to an end a period of over 20 years of under investment. The ''Red Book'', jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, is a recognised world reference on uranium. It is based on official information received from 40 countries. This second edition provides a comprehensive review of world uranium supply and demand as of first January 2007, as well as data on global uranium exploration, resources, production and reactor-related requirements. It provides substantive new information from major uranium production centres in Africa, Australia, Central Asia, Eastern Europe and North America. Projections of nuclear generating capacity and reactor-related uranium requirements through 2030 are also featured, along with an analysis of long-term uranium supply and demand issues. (author)

Development of 99Mo isotope production targets employing uranium metal foils

International Nuclear Information System (INIS)

Hofman, G.L.; Wiencek, T.C.; Wood, E.L.; Snelgrove, J.L.

1997-01-01

The Reduced Enrichment Research and Test Reactor Program has continued its effort in the past 3 yr to develop use of low-enriched uranium (LEU) to produce the fission product 99 Mo. This work comprises both target and chemical processing development and demonstration. Two major target systems are now being used to produce 99 Mo with highly enriched uranium-one employing research reactor fuel technology (either uranium-aluminum alloy or uranium aluminide-aluminum dispersion) and the other using a thin deposit of UO 2 on the inside of a stainless steel (SST) tube. This paper summarizes progress in irradiation testing of targets based on LEU uranium metal foils. Several targets of this type have been irradiated in the Indonesian RSG-GAS reactor operating at 22.5 MW

Uranium production, the United States perspective

International Nuclear Information System (INIS)

Glasier, G.E.

1984-06-01

U.S. uranium production appears to be headed for a level of approximately one quarter of the peak production of the early 1980's. In a free world market the majority of the U.S. production capability is noncompetitive and unnecessary to supply the free world's demand. Those world producers which can produce into the competitive uranium market of the present and the foreseeable future will be sufficient to supply the uranium needs of the world for the next ten to fifteen years. Thus, the U.S. production industry once the leading producer in the world will not regain nor approach that status in the foreseeable future

World uranium: resources, production and demand

International Nuclear Information System (INIS)

Anon.

1978-01-01

The OECD Nuclear Energy Agency recently announced the publication of a new edition of its report on Uranium resources, production and demand which has been published periodically since 1965, jointly with the International Atomic Energy Agency. In addition to bringing uranium resources and production estimates up-to-date, the new edition offers a more comprehensive treatment of exploration activity and uranium availability, and includes a greater number of countries within the scope of the survey. Information on uranium demand has also been revised, in the light of more recent forecasts of the growth of nuclear power. Finally, a comparison is made between uranium availability and requirements, and the implications of this comparison analysed. The main findings and conclusions of the report are summarized here. (author)

New information on world uranium resource, production, supply and demand

International Nuclear Information System (INIS)

Zhang Jianguo; Meng Jin

2006-01-01

New information on world uranium resource, production, supply and demand is introduced. Up to now, explored uranium resources at production cost < USD 40/kg U has 2523257 t uranium; production cost < USD 80/kg U has 5911514 t uranium; production cost < USD130/kg U has 11280488 t uranium; and cost range unassigned has 3102000 t uranium. At moment, the demand uranium of each year is about 67000 t U. After 2020, world uranium demand will rise well above 100000 t per annum with sharp revival of nuclear power plants. With three kinds of economic growth the cumulative requirement of the uranium in low demand case, middle demand case and high demand case from 2000 to 2050 is 3390000, 5394100 and 7577300 t respectively. In the world market uranium price rises from 20 years lowest 18.2 USD/kg U to 75.4 USD/kg U. In 2003, global uranium product is about 35385 t U, and 2004, global uranium product is about 40475 t U. In 2004's world uranium production underground mining, open pit, in situ, by product, and combination account for 39%, 27%, 19%, 11% and 4% respectively. (authors)

Magnesio-thermic reduction of UF4 to uranium metal : plant operating experience

International Nuclear Information System (INIS)

Mayekar, S.V.; Singh, H.; Meghal, A.M.; Koppiker, K.S.

1991-01-01

Uranium Metal Plant has switched over from calcio-thermy to magnesio-thermy for production of uranium ingots. In this paper, the plant operating experience for magnesio-thermic reduction is described. Based on trials, the production has been stepped up from 40 kg ingots to 200 kg ingots. The operating parameters optimised include : heating schedule, UF 4 quality, magnesium quantity and quality, and particle size. The effect of quality of refractory lining has been discussed. Conditions for lining are optimised with regard to type of material used and size. Developmental work has also been carried out on use of pelletised charge and on use of graphite sleeves. Some experience in the machining of ingots for removal of surface slag is also discussed. Impurity problems, occasionally encountered, have been investigated and results are discussed. Based on the experience gained, specifications for operation have been laid down, and areas for further improvement are identified. (author). 5 refs., 1 fig., 1 tab

World uranium production and demand: A review

International Nuclear Information System (INIS)

Tauchid, M.; Mueller Kahle, E.

1993-01-01

Despite the growing public concern on the use of nuclear energy, nuclear power generation capacity in the world is expected to follow a modest, but positive growth at least during the next two decades. Uranium production needed to fuel these reactors has been below demand since 1985. The WOCA production figure for 1991 is in the order of 27,000 tonnes U which is 39% below the peak production of 1980. With the exception of Australia, all other countries produced less uranium than in the previous year. It is expected that the production figure for 1992 will shrink even further to about 23,000 tonnes U. In-situ leaching uranium production contributed about 16% to the 1991 world production figure, most of which came from Eastern Europe and Central Asia. With the closing of a number of production facilities the relative contribution of in-situ leaching to the world uranium production is expected to grow. Only about 60% of WOCA's reactor related uranium demand for 1991 was supplied from its own production. The remaining 40% was filled from existing inventories and imports from the Russian Federation and China. The estimated gap between the world uranium production and reactor related demand for 1991 is in the order 10,900 tones U or 19.7%. The cumulative requirement for the world reactor related demand to the year 2010 has been estimated to be about 1,270,000 tonnes U. (author). 6 refs, 10 figs

Uranium

International Nuclear Information System (INIS)

Cuney, M.; Pagel, M.; Leroy, J.

1992-01-01

First, this book presents the physico-chemical properties of Uranium and the consequences which can be deduced from the study of numerous geological process. The authors describe natural distribution of Uranium at different scales and on different supports, and main Uranium minerals. A great place in the book is assigned to description and classification of uranium deposits. The book gives also notions on prospection and exploitation of uranium deposits. Historical aspects of Uranium economical development (Uranium resources, production, supply and demand, operating costs) are given in the last chapter. 7 refs., 17 figs

Developments in uranium resources, production, demand and the environment. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2005-01-01

Globalization has led to growing importance of the uranium production industries of the world's developing countries. Uranium supply from these countries could be increasingly important in satisfying worldwide reactor requirements over time. Along with the increasing contribution to worldwide uranium supply, the environmental impact of uranium production in developing countries has come under increasing scrutiny from the nuclear power industry, the end-users of this supply, and from communities impacted by uranium mining and processing. The papers presented at the meeting on 'Developments in Uranium Resources, Production, Demand and the Environment' provide an important overview of uranium production operations and of their environmental consequences in developing countries, as well as offering insight into future production plans and potential. Along with their increasing contribution to worldwide uranium supply, the environmental impact of uranium production in developing countries has come under increasing scrutiny from the nuclear power industry, the end users of this supply, and by communities impacted by uranium mining and processing. Therefore, the environmental consequences of uranium production were included in the meeting agenda as noted in the meeting title, 'Developments in uranium resources, production, demand and the environment'. Accordingly, the papers presented at this meeting are about evenly divided between discussions of known and potential uranium resources and uranium production technology and the environmental impact of uranium mining and processing, its related remediation technology and its costs. Though emphasis is placed on uranium programmes in developing countries, an overview of COGEMA's worldwide activities is also presented. This presentation provides insight into the strategies of arguably the Western world's most integrated and diversified uranium company, including the geographic diversity of its exploration and production

Uranium 2016: Resources, Production and Demand

International Nuclear Information System (INIS)

2016-01-01

Uranium is the raw material used to produce fuel for long-lived nuclear power facilities, necessary for the generation of significant amounts of base-load low-carbon electricity for decades to come. Although a valuable commodity, declining market prices for uranium in recent years, driven by uncertainties concerning evolutions in the use of nuclear power, have led to the postponement of mine development plans in a number of countries and to some questions being raised about future uranium supply. This 26. edition of the 'Red Book', a recognised world reference on uranium jointly prepared by the Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA), provides analyses and information from 49 producing and consuming countries in order to address these and other questions. The present edition provides the most recent review of world uranium market fundamentals and presents data on global uranium exploration, resources, production and reactor-related requirements. It offers updated information on established uranium production centres and mine development plans, as well as projections of nuclear generating capacity and reactor-related requirements through 2035, in order to address long-term uranium supply and demand issues. (authors)

Preliminary analysis about reducing production costs in uranium mining and metallurgy at Fuzhou uranium mine

International Nuclear Information System (INIS)

Wu Sanmao

1999-01-01

The production costs in uranium ming and metallurgy have been analyzed quantitatively term by term according to present production situation for The Uranium Mining and Metallurgy Corp, which is part of Fuzhou Uranium Mine. The principal factors influencing on the production costs and the main means reducing the production costs have been found

World uranium resources, production and demand

International Nuclear Information System (INIS)

Lindholm, I.

1988-01-01

Reasonably assured resources of uranium in WOCA (World Outside the Centrally Planned Economies Area) countries recoverable at less than US $80/kg U increased by about 9% between 1983 and 1985 and currently stand at 1.5 million tonnes. Uranium also exists in significant quantities in higher cost resources or in less known resources. However, the annual exploration expenditure is less than 20% that of the 1979 level. Uranium production in WOCA countries was higher than consumption during the period 1965 to 1984 and considerable stocks were accumulated. However, the production figures for 1985 were estimated to be slightly less than those of consumption. Production from centres now on stand-by or new centres will probably be necessary around 1990. Analysis of the longer term production possibilities indicates that uranium supplies will probably not be constrained by an ultimate resource adequacy. Constraints, if any, are more likely to be of political nature. (author). 11 figs, 1 tab

Operation of the joint panel on occupational and environmental research for uranium production in Canada

International Nuclear Information System (INIS)

Stocker, H.; Duport, P.J.; Brown, L.D.

1993-07-01

The Joint Panel, formed in 1976, is a Canadian organization (composed of federal and provincial government departments and agencies, uranium mining companies, labour unions, and non-profit research institutions) whose members have voluntarily agreed to share information regarding planned, ongoing and completed research on the effects of uranium (and thorium) production on the radiological health and safety of workers and on the environment. The objectives of the Joint Panel are: the identification of areas (within its purview of interest) where research is required; the stimulation of research in areas where the needs have been identified; the dissemination of subsequent research results; and, the avoidance of unnecessary duplication in research activities. The operation of this unique organization permits a free and open discussion of a wide variety of research activities, draws upon its member institutions to form working groups for the preparation of technical documents, and complements its more formal business sessions with technical presentations on topics of current interest. Copies of reports of completed research are maintained by a secretariat, which also issues the minutes of all meetings as well as the annual reports

Uranium 2009 resources, production and demand

CERN Document Server

Organisation for Economic Cooperation and Development. Paris

2010-01-01

With several countries currently building nuclear power plants and planning the construction of more to meet long-term increases in electricity demand, uranium resources, production and demand remain topics of notable interest. In response to the projected growth in demand for uranium and declining inventories, the uranium industry – the first critical link in the fuel supply chain for nuclear reactors – is boosting production and developing plans for further increases in the near future. Strong market conditions will, however, be necessary to trigger the investments required to meet projected demand. The "Red Book", jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, is a recognised world reference on uranium. It is based on information compiled in 40 countries, including those that are major producers and consumers of uranium. This 23rd edition provides a comprehensive review of world uranium supply and demand as of 1 January 2009, as well as data on global ur...

Remotely operated facility for in situ solidification of fissile uranium

International Nuclear Information System (INIS)

McGinnis, C.P.; Collins, E.D.; Patton, B.D.

1986-01-01

A heavily shielded, remotely operated facility, located within the Radiochemical processing Plant at Oak Ridge National Laboratory (ORNL), has been designed and is being operated to convert approx.1000 kg of fissile uranium (containing approx.75% 235 U, approx.10% 233 U, and approx.140 ppM 232 U) from a nitrate solution (130 g of uranium per L) to a solid oxide form. This project, the Consolidated Edison Uranium Solidification Program (CEUSP), is being carried out in order to prepare a stable uranium form for longterm storage. This paper describes the solidification process selected, the equipment and facilities required, the experimental work performed to ensure successful operation, some problems that were solved, and the initial operations

Uranium 2001: resources, production and demand

International Nuclear Information System (INIS)

2002-01-01

The 'Red Book', jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, is a recognised world reference on uranium. Its contents are based on official information received from 45 countries, supplemented by unofficial information for two others. This edition, the 19., presents the results of a thorough review of world uranium supply and demand as of 1 January 2001 and provides a statistical profile of the world uranium industry in the areas of exploration, resource estimates, production and reactor-related requirements. It provides substantial new information from all major uranium production centres in Africa, Australia, Eastern Europe and North America and, for the first time, includes a report on Tajikistan. This edition also features international expert analyses and projections of nuclear generating capacity and reactor-related uranium requirements through 2020. (authors)

Why can rossing uranium mine keep mining even in low price conditions of uranium market

International Nuclear Information System (INIS)

Tan Chenglong

2004-01-01

Rossing uranium mine is the only operating uranium mine in the world where the uranium occurs in intrusive alaskite. In the past 10 years, uranium market regressed in the world, uranium production weakened, expenditures of capital for uranium exploration were insufficient. Uranium spot market price rapidly decreased from $111.8/kg U in late 1970's to $22.1/kg U in mid-1990's. Why can Rossing uranium mine mined with traditional underground and open pit operation can keep running even in low price conditions of uranium market? Augumenting research on the deposit, mineral and technology, decreasing production cost and improving selling strategy can not only maintain Rossing's uranium production at present, but also ensure sustainable development in the coming 15 years. Exploration of low-costed uranium deposits is very important. However, obvious economic benefits can be obtained, as Rossing uranium mine does, by augumenting geological-economical research on the known uranium deposits of hard-rock type and by using new techniques to improve the conventional techniques in the uranium mine development. (authors)

Minimizing the risk and impact of uranium hexafluoride production

International Nuclear Information System (INIS)

Clark, D.R.; Kennedy, T.W.

2010-01-01

Cameco Corporation's Port Hope conversion facility, situated on the shore of Lake Ontario in the Municipality of Port Hope, Ontario, Canada, converts natural uranium trioxide (UO_3) into uranium dioxide (UO_2) or natural uranium hexafluoride (UF_6). Conversion of UO_3 to UF_6 has been undertaken at the Port Hope conversion facility since 1970 and is currently carried out in a second-generation plant licensed to annually produce 12,500 tonnes U as UF_6. Consistent with Cameco's vision, values and measures of success, Cameco recognizes safety and health of its workers and the public, protection of the environment, and the quality of our processes as the highest corporate priorities. Production of UF_6 in a brownfield urban setting requires a commitment to design, build and maintain multiple layers of containment (defence-in-depth) and to continually improve in all operational aspects to achieve this corporate commitment. This paper will describe the conversion processes utilized with a focus on the cultural, management and physical systems employed to minimize the risk and impact of the operation. (author)

Past and future of uranium production

International Nuclear Information System (INIS)

Max, A.; Mason, T.

1996-01-01

Changes in world politics over the last few years have directly affected supplies and price levels in the front-end nuclear industry. Limited by the advance of CIS and East European uranium and nuclear fuel services into the west, the trend towards a declining uranium industry continued until 1994. The expected introduction of military uranium from Russian and American warheads into the civil nuclear fuel cycle creates additional unknowns in the nuclear fuel market. However, the long lasting recession in the uranium industry may already be coming to an end: The uranium inventories still in existence and uranium from the conversion of nuclear warheads will not last long enough to close the existing gap between uranium demand and supply. Additional uranium production will be required as a result. (orig.) [de

Separation and purification of uranium product from thorium in thorex process by precipitation technique

International Nuclear Information System (INIS)

Ramanujam, A.; Dhami, P.S.; Gopalakrishnan, V.; Mukherjee, A.; Dhumwad, R.K.

1989-01-01

A sequential precipitation technique is reported for the separation of uranium and thorium present in the uranium product stream of a single cycle 5 per cent TBP Thorex Process. It involves the precipitation of thorium as oxalate in 1M HNO 3 medium at 60-70degC and after filtration, precipitation of uranium as ammonium diuranate at 80-90degC from the oxalate supernatant. This technique has several advantages over the ion-exchange process normally used for treating these products. In order to meet the varying feed conditions, this method has been tested for feeds containing 10 g/1 uranium and 1-50 g/1 thorium in 1-6M HNO 3 . Various parameters like feed acidities, uranium and thorium concentrations, excess oxalic acid concentrations in the oxalate supernatant, precipitation temperatures, precipitate wash volumes etc. have been optimised to obtain more than 99 per cent recovery of thorium and uranium as their oxides with less than 50 ppm uranium losses to ammonium diuranate filtrate. The distribution patterns of different fission products and stainless steel corrosion products during various steps of this procedure have also been studied. For simulating the actual Thorex plant scale operation, experiments have been conducted with 25g and 100g lots of uranium per batch. (author). 6 tabs., 8 figs., 22 refs

IAEA Activities on Uranium Resources and Production, and Databases for the Nuclear Fuel Cycle

Energy Technology Data Exchange (ETDEWEB)

Ganguly, C.; Slezak, J. [Divison of Nuclear Fuel Cycle and Waste Technology, International Atomic Energy Agency, Vienna (Austria)

2014-05-15

In recent years rising expectation for nuclear power has led to a significant increase in the demand for uranium and in turn dramatic increases in uranium exploration, mining and ore processing activities worldwide. Several new countries, often with limited experience, have also embarked on these activities. The ultimate goal of the uranium raw material industry is to provide an adequate supply of uranium that can be delivered to the market place at a competitive price by environmentally sound, mining and milling practices. The IAEA’s programme on uranium raw material encompass all aspects of uranium geology and deposits, exploration, resources, supply and demand, uranium mining and ore processing, environmental issues in the uranium production cycle and databases for the uranium fuel cycle. Radiological safety and environmental protection are major challenges in uranium mines and mills and their remediation. The IAEA has revived its programme for the Uranium Production Site Appraisal Team (UPSAT) to assist Member States to improve operational and safety performances at uranium mines and mill sites. The present paper summarizes the ongoing activities of IAEA on uranium raw material, highlighting the status of global uranium resources, their supply and demand, the IAEA database on world uranium deposit (UDEPO) and nuclear fuel cycle information system (NFCIS), recent IAEA Technical Meetings (TM) and related ongoing Technical Cooperation (TC) projects. (author)

Uranium-mediated electrocatalytic dihydrogen production from water

Science.gov (United States)

Halter, Dominik P.; Heinemann, Frank W.; Bachmann, Julien; Meyer, Karsten

2016-02-01

Depleted uranium is a mildly radioactive waste product that is stockpiled worldwide. The chemical reactivity of uranium complexes is well documented, including the stoichiometric activation of small molecules of biological and industrial interest such as H2O, CO2, CO, or N2 (refs 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11), but catalytic transformations with actinides remain underexplored in comparison to transition-metal catalysis. For reduction of water to H2, complexes of low-valent uranium show the highest potential, but are known to react violently and uncontrollably forming stable bridging oxo or uranyl species. As a result, only a few oxidations of uranium with water have been reported so far; all stoichiometric. Catalytic H2 production, however, requires the reductive recovery of the catalyst via a challenging cleavage of the uranium-bound oxygen-containing ligand. Here we report the electrocatalytic water reduction observed with a trisaryloxide U(III) complex [((Ad,MeArO)3mes)U] (refs 18 and 19)—the first homogeneous uranium catalyst for H2 production from H2O. The catalytic cycle involves rare terminal U(IV)-OH and U(V)=O complexes, which have been isolated, characterized, and proven to be integral parts of the catalytic mechanism. The recognition of uranium compounds as potentially useful catalysts suggests new applications for such light actinides. The development of uranium-based catalysts provides new perspectives on nuclear waste management strategies, by suggesting that mildly radioactive depleted uranium—an abundant waste product of the nuclear power industry—could be a valuable resource.

Operation of Nuclear Fuel Based on Reprocessed Uranium for VVER-type Reactors in Competitive Nuclear Fuel Cycles

Energy Technology Data Exchange (ETDEWEB)

Troyanov, V.; Molchanov, V.; Tuzov, A. [TVEL Corporation, 49 Kashirskoe shosse, Moscow 115409 (Russian Federation); Semchenkov, Yu.; Lizorkin, M. [RRC ' Kurchatov Institute' (Russian Federation); Vasilchenko, I.; Lushin, V. [OKB ' Gidropress' (Russian Federation)

2009-06-15

Current nuclear fuel cycle of Russian nuclear power involves reprocessed low-enriched uranium in nuclear fuel production for some NPP units with VVER-type LWR. This paper discusses design and performance characteristics of commercial nuclear fuel based on natural and reprocessed uranium. It presents the review of results of commercial operation of nuclear fuel based on reprocessed uranium on Russian NPPs-unit No.2 of Kola NPP and unit No.2 of Kalinin NPP. The results of calculation and experimental validation of safe fuel operation including necessary isotope composition conformed to regulation requirements and results of pilot fuel operation are also considered. Meeting the customer requirements the possibility of high burn-up achieving was demonstrated. In addition the paper compares the characteristics of nuclear fuel cycles with maximum length based on reprocessed and natural uranium considering relevant 5% enrichment limitation and necessity of {sup 236}U compensation. The expedience of uranium-235 enrichment increasing over 5% is discussed with the aim to implement longer fuel cycles. (authors)

Processing of stored uranium tetrafluoride for productive use

International Nuclear Information System (INIS)

Whinnery, W.N. III

1987-01-01

Waste uranium tetrafluoride (UF4) was created from converting uranium hexafluoride (UF6) to UF4 for generation of hydrogen fluoride. This resulted in more tails cylinders being made available in the early days of the Paducah Gaseous Diffusion Plant. A need arose for the UF4; however, a large portion of the material was stored outside in 55-gallon drums where the material became caked and very hard. Chemical operations crushed, ground, and screened a large portion of the waste UF4 from 1981-1987. Over 111,935,000 pounds of the material has been processed and put into productive use at Westinghouse Materials Company of Ohio or at Department of Defense facilities. This long-term effort saved the disposal cost of the material which is estimated at $9,327,900. In addition, the work was for an outside contract which lowered the operating cost of the Chemical Operations Department by $4,477,400. Disposal options for the material still present in the current inventory are outlined

Current U.S. uranium production costs

International Nuclear Information System (INIS)

Steyn, J.J.; Douglas, R.F.

1989-01-01

The U.S. uranium industry has undergone significant changes in the 1980s. These changes have come about largely as a result of the much slower growth of nuclear power than that initially anticipated and the deployment of an excess uranium supply capacity by 1979. The demand and supply imbalance has led to a substantial build-up in excess inventories which will not be remedied until well into the 1990s. At the same time as domestic inventories were building, large low cost uranium deposits were being discovered and developed in Canada and Australia. Additionally, in the past year or so it has become apparent that low cost uranium from the Soviet Union and the Peoples Republic of China will increasingly become a factor in the marketplace. The soft demand, large inventories, and competitive imports, stimulated by the recently ratified U.S.-Canada Free Trade Agreement, have caused the U.S. uranium industry to contract to one-tenth of its size ten years ago, if employment is taken at the gage. In light of the foregoing, this paper examines the current U.S. uranium production cost outlook for the 1990s. It is based on a direct cost analysis of all identifiable uranium deposits, mines, and production centers

Establishing Effective Environmental and Safety Performance Indicators: A Best Practice Approach in Uranium Production

International Nuclear Information System (INIS)

Rezansoff, D.; White, G.

2010-01-01

Cameco Corporation (Cameco), with headquarters in Saskatoon, Saskatchewan, Canada, is the world's largest, low-cost uranium producer, currently supplying sufficient uranium to meet 20% of the world's demand. It is characterized by a diverse range of operations in Canada, the United States and Central Asia, for which Cameco is the majority owner and/or operator, including exploration, mining, milling, refining and conversion. Cameco had four business segments: Uranium; Conversion services; Nuclear energy generation; and Gold Also, in 2002, Cameco revised its vision statement to indicate, 'Cameco will be a dominant nuclear energy company producing uranium fuel and generating clean electricity'. Commensurate with this, Cameco has re-confirmed its overall measures of success as follows: A safe, healthy and rewarding workplace; A clean environment; Supportive communities; and Solid financial performance - all reflected in a growing return to shareholders. Like most organizations, Cameco recognizes the importance of conducting its operations in ways that promote continual improvement in environmental and safety performance. Demonstrating the environmental advantages of nuclear is a vital part of the overall best management practices approach. Detractors often try to point to the uranium production side of the nuclear fuel cycle in pursuit of trying to make the case that the nuclear option does not carry any special environmental advantage. These attempts are mostly based on performance from eras past, not modern performance. The uranium sector must be able to present its case in a modern context, which is largely based on sustainable development principles. This paper focuses on establishing environment and safety performance indicators for the uranium production and conversion aspects of Cameco's business, as well as in support of the environmental advantages of nuclear energy generation

Australian uranium production and trade trends

International Nuclear Information System (INIS)

Armstrong, G.; Braddick, P.

1994-01-01

After overviewing the factors influencing the worldwide production and consumption of uranium, the authors review the world situation and assess the industry in Australia and the impact of Government policy on uranium mining. The conclusion is that Australia, with almost 30 per cent of the western world's uranium resources, including several of the highest grade and lowest cost deposits in the world, remains well placed to enjoy a substantial share of growth in the uranium market, should existing Government restrictions be lifted. 6 figs., 2 tabs

Uranium metal production by molten salt electrolysis

International Nuclear Information System (INIS)

Takasawa, Yutaka

1999-01-01

Atomic vapor laser isotope separation (AVLIS) is a promising uranium enrichment technology in the next generation. Electrolytic reduction of uranium oxides into uranium metal is proposed for the preparation of uranium metal as a feed material for AVLIS plant. Considering economical performance, continuos process concept and minimizing the amount of radioactive waste, an electrolytic process for producing uranium metal directly from uranium oxides will offer potential advantages over the existing commercial process. Studies of uranium metal by electrolysis in fluoride salts (BaF 2 -LiF-UF 4 (74-11-15 w/o) at 1150-1200degC, using both a laboratory scale apparatus and an engineering scale one, and continuous casting of uranium metal were carried out in order to decide the optimum operating conditions and the design of the industrial electrolytic cells. (author)

Test operation of the uranium ore processing pilot plant and uranium conversion plant

International Nuclear Information System (INIS)

Suh, I.S.; Lee, K.I.; Whang, S.T.; Kang, Y.H.; Lee, C.W.; Chu, J.O.; Lee, I.H.; Park, S.C.

1983-01-01

For the guarantee of acid leaching process of the Uranium Ore Processing Pilot Plnat, the KAERI team performed the test operation in coorperation with the COGEMA engineers. The result of the operation was successful achieving the uranium leaching efficiency of 95%. Completing the guarentee test, a continuous test operation was shifted to reconform the reproducibility of the result and check the functions of every units of the pilot plant feeding the low-grade domestic ore, the consistency of the facility was conformed that the uranium can easily be dissolved out form the ore between the temperature range of 60degC-70degC for two hours of leaching with sulfuric acid and could be obtained the leaching efficiency of 92% to 95%. The uranium recovery efficiencies for the processes of extraction and stripping were reached to 99% and 99.6% respectively. As an alternative process for the separation of solid from the ore pulp, four of the Counter Current Decanters were shifted replacing the Belt Filter and those were connected in a series, which were not been tested during the guarantee operation. It was found out that the washing efficiencies of the ore pulp in each tests for the decanters were proportionally increased according to the quantities of the washing water. As a result of the test, it was obtained that washing efficiencies were 95%, 85%, 83% for the water to ore ratio of 3:1, 2:1, 1.5:1 respectively. (Author)

International uranium production. A South African perspective

International Nuclear Information System (INIS)

Sinclair-Smith, D.

1984-01-01

Between 1981 and 1983 South Africa experienced a decline in its uranium resources of 23% in the less than $80/kg U category and 12% in the less than $130/kg U category. In 1983 only $5 million was spent on exploration, with activities being concentrated in the Witwatersrand Basin as a byproduct of gold exploration. South Africa has maintained a production level of around 6000 mt U in 1981, 1982 and 1983. One unusual feature of the South African uranium scene is the ability to selectively dump relatively high grade uranium tailings after the extraction of gold and to rework this material as well as material dumped prior to the emergence of the uranium industry. Uranium from this source amounted to some 28% of total production in 1983. (L.L.) (2 tabs., 6 figs.)

A mathematical model to forecast uranium production

International Nuclear Information System (INIS)

Camisani-Calzolari, F.A.G.M.

1987-01-01

The uranium production forecasting program described in this paper projects production from reasonably assured, estimated additional and speculative resources in the cost categories of less than $130/kg U. Originally designed to handle South African production, it has been expanded and redimensioned using available published information to forecast production for countries of the Western World. The program forecasts production from up to 400 plants over a period of fifty years and has built-in production models derived from documented historical data of the more important uranium provinces. It is particularly suitable to assess production capabilities on a national and global scale where variations in outputs for the individual plants tend to even out. The program is aimed at putting the uranium potential of any one country into a realistic perspective, and it could thus be useful for planning purposes and marketing strategies

Data feature World natural Uranium production 1992

International Nuclear Information System (INIS)

Anon.

1993-01-01

NUKEM estimates that world uranium production fell more than 13% last year, from 40,729 tonnes U [106 million lbs U308] in 1991 to 35,363 tonnes U [92 million lbs U308] in 1992. Production fell in both the Western World and non-Western World. How much of demand was met by production? World uranium production in 1992 amounted to about 65% of reactor consumption. That's assuming that reactor demand of the non-Western World has not changed much from the Uranium Institute's estimate for 1991. Civilian stockpiles are being drawn down on a massive scale while the world waits to see what will become of the military stockpiles that could soon enter the global supply picture

Estimating uranium resources and production. A guide to future supply

International Nuclear Information System (INIS)

Taylor, D.M.; Haeussermann, W.

1983-01-01

Nuclear power can only continue to grow if sufficient fuel, uranium, is available. Concern has been expressed that, in the not too distant future, the supply of uranium may be inadequate to meet reactor development. This will not be the case. Uranium production capability, actual and planned, is the main indicator of short- and medium-term supply. However, for the longer term, uranium resource estimates and projections of the possible rate of production from the resource base are important. Once an estimate has been made of the resources contained in a deposit, several factors influence the decision to produce the uranium and also the rates at which the uranium can be produced. The effect of these factors, which include uranium market trends and ever increasing lead times from discovery to production, must be taken into account when making projections of future production capability and before comparing these with forecasts of future uranium requirements. The uranium resource base has developed over the last two decades mainly in response to dramatically changing projections of natural uranium requirements. A study of this development and the changes in production, together with the most recent data, shows that in the short- and medium-term, production from already discovered resources should be sufficient to cover any likely reactor requirements. Studies such as those undertaken during the International Uranium Resources Evaluation Project, and others which project future discovery rates and production, are supported by past experience in resource development in showing that uranium supply could continue to meet demand until well into the next century. The uranium supply potential has lessened the need for the early large-scale global introduction of the breeder reactor

Preliminary investigations on the use of uranium silicide targets for fission Mo-99 production

Energy Technology Data Exchange (ETDEWEB)

Cols, H.; Cristini, P.; Marques, R.

1997-08-01

The National Atomic Energy Commission (CNEA) of Argentine Republic owns and operates an installation for production of molybdenum-99 from fission products since 1985, and, since 1991, covers the whole national demand of this nuclide, carrying out a program of weekly productions, achieving an average activity of 13 terabecquerel per week. At present they are finishing an enlargement of the production plant that will allow an increase in the volume of production to about one hundred of terabecquerel. Irradiation targets are uranium/aluminium alloy with 90% enriched uranium with aluminium cladding. In view of international trends held at present for replacing high enrichment uranium (HEU) for enrichment values lower than 20 % (LEU), since 1990 the authors are in contact with the RERTR program, beginning with tests to adapt their separation process to new irradiation target conditions. Uranium silicide (U{sub 3}Si{sub 2}) was chosen as the testing material, because it has an uranium mass per volume unit, so that it allows to reduce enrichment to a value of 20%. CNEA has the technology for manufacturing miniplates of uranium silicide for their purposes. In this way, equivalent amounts of Molybdenum-99 could be obtained with no substantial changes in target parameters and irradiation conditions established for the current process with Al/U alloy. This paper shows results achieved on the use of this new target.

Critical review of uranium resources and production capability to 2020

International Nuclear Information System (INIS)

1998-08-01

This report was prepared to assess the changing uranium supply and demand situation as well as the adequacy of uranium resources and the production capability to supply uranium concentrate to meet reactor demand through 2020. Uranium production has been meeting only 50 to 60 percent of the world requirements with the balance met from sale of excess inventory offered on the market at low prices. It is generally agreed by most specialists that the end of the excess inventory is approaching. With inventory no longer able to meet the production shortfall it is necessary to significantly expand uranium production to fill an increasing share of demand. Non-production supplies of uranium, such as the blending of highly enriched uranium (HEU) warheads to produce low enriched reactor fuel and reprocessing of spent fuel, are also expected to grow in importance as a fuel source. This analysis addresses three major concerns as follows: adequacy of resources to meet projected demand; adequacy of production capability to produce the uranium; and market prices to sustain production to fill demand. This analysis indicates uranium mine production to be the primary supply providing about 76 to 78 percent of cumulative needs through 2020. Alternative sources supplying the balance, in order of relative importance are: (1) low enriched uranium (LEU) blended from 500 tonnes of highly enriched uranium (HEU) Russian weapons, plus initial US Department of Energy (US DOE) stockpile sales (11 to 13%); (2) reprocessing of spent nuclear fuel (6%) and; (3) utility and Russian stockpiles. Further this report gives uranium production profiles by countries: CIS producers (Kazakhstan, Russian Federation, Ukraine, Uzbekistan) and other producers (Australia, Canada, China, Gabon, Mongolia, Namibia, Niger, South Africa, United States of America)

Uranium ore mill at Dolni Rozinka: 40 years of operation

International Nuclear Information System (INIS)

Toman, F.; Jezova, V.

2007-01-01

Uranium ore mined in the Rozna deposit is treated at a chemical treatment plant (a mill) situated in the close vicinity of the Rozna mine. In the mill, uranium is extracted from the crushed and ground-up ore by alkaline leaching. Uranium is then recovered from the solution by sorption on ion exchange resin; the next steps are precipitation and drying. Alkaline leaching is applied at the atmospheric pressure and the temperature of 80 deg C; the recovery factor is moving around 93%. The final product of the milling is uranium concentrate, ammonium diuranate (NH 4 ) 2 U 2 O 7 ), a so-called 'yellow cake' which is treated into a fuel for nuclear power plants in conversion facilities abroad. The milling is carried on under the condition of the closed cycle of technology water. Due to the positive annual precipitation balance, the over balance of technology water in tailings pond has to be purified before discharging into a river. Evaporation and membrane processes (electrodialysis and reverse osmosis) are used to purify the water. The mill at Dolni Rozinka has been in operation since 1968. It has processed 13.2 million tons of uranium ore which is about 14000 tons of uranium and purified more than 6 million m 3 of the over balanced technology water during 40 years. From the organizational point of view, the mine and the chemical treatment plant form the branch plant GEAM, which is a part of the state enterprise DIAMO. (author)

Basic status of uranium mine production at the beginning of the new century

International Nuclear Information System (INIS)

Tan Chenglong

2005-01-01

At the beginning of the new century, the global uranium mine production declined slightly, the spot uranium price was close to or slightly higher than that of the last century. The uranium consumption in global nuclear electricity generation does not fluctuate greatly, remains stable as a whole. Although certain accidents have taken place during the period of uranium mine production, uranium production remains stable, uranium's demand and supply remain balanced basically. In the global uranium mine production at the beginning of the new century, production from hard rock uranium mines still plays the leading role, and production from in-situ leachable sandstone-type uranium mines increases by a small margin and makes up one fifth of the total global uranium mine production. Several transnational uranium industry companies have become the main stockholders of low cost uranium production centers all around the world. Most mining uranium deposits and uranium production centers have centralized in a few countries. The globalized distribution of uranium resources during the progress of the world's economy globalization has taken shape in the uranium industry. (authors)

Process development study on production of uranium metal from monazite sourced crude uranium tetra-fluoride

International Nuclear Information System (INIS)

Chowdhury, S; Satpati, S.K.; Hareendran, K.N.; Roy, S.B.

2014-01-01

Development of an economic process for recovery, process flow sheet development, purification and further conversion to nuclear grade uranium metal from the crude UF 4 has been a technological challenge and the present paper, discusses the same.The developed flow-sheet is a combination of hydrometallurgical and pyrometallurgical processes. Crude UF 4 is converted to uranium di-oxide (UO 2 ) by chemical conversion route and UO 2 produced is made fluoride-free by repeated repulping, followed by solid liquid separation. Uranium di-oxide is then purified by two stages of dissolution and suitable solvent extraction methods to get uranium nitrate pure solution (UNPS). UNPS is then precipitated with air diluted ammonia in a leak tight stirred vessel under controlled operational conditions to obtain ammonium di-uranate (ADU). The ADU is then calcined and reduced to produce metal grade UO 2 followed by hydro-fluorination using anhydrous hydrofluoric acid to obtain metal grade UF 4 with ammonium oxalate insoluble (AOI) content of 4 is essential for critical upstream conversion process. Nuclear grade uranium metal ingot is finally produced by metallothermic reduction process at 650℃ in a closed vessel, called bomb reactor. In the process, metal-slag separation plays an important role for attaining metal purity as well as process yield. Technological as well economic feasibility of indigenously developed process for large scale production of uranium metal from the crude UF 4 has been established in Bhabha Atomic Research Centre (BARC), India

Mining-metallurgical projects for the production of uranium concentrates

International Nuclear Information System (INIS)

Ajuria-Garza, S.

1983-01-01

This report presents an overall view of a complete project for a mining-metallurgical complex for the production of uranium concentrates. Relevant aspects of each important topic are discussed as parts of an integrated methodology. The principal project activities are analyzed and the relationships among the various factors affecting the design are indicated. A list of 96 principal activities is proposed as an example. These activities are distributed in eight groups: initial evaluations preliminary feasibility studies, project engineering, construction, industrial operation, decommissioning and post-decommissioning activities. The environmental impact and the radiological risks due to the construction and operation of the mining metallurgical complex are analyzed. The principles of radiological protection and the regulations, standards and recommendations for radiological protection in uranium mines and mills are discussed. This report is also a guide to the specialized literature: a bibliography with 765 references is included. (author)

Vacuum fusion of uranium; Fusion de l'uranium sous vide

Energy Technology Data Exchange (ETDEWEB)

Stohr, J. A.

1957-06-04

After having outlined that vacuum fusion and moulding of uranium and of its alloys have some technical and economic benefits (vacuum operations avoid uranium oxidation and result in some purification; precision moulding avoids machining, chip production and chemical reprocessing of these chips; direct production of the desired shape is possible by precision moulding), this report presents the uranium fusion unit (its low pressure enclosure and pumping device, the crucible-mould assembly, and the MF supply device). The author describes the different steps of cast production, and briefly comments the obtained results.

Case study: Financing growth in uranium production despite today’s serious challenges – from concept to production in five years

International Nuclear Information System (INIS)

Adnani, A.

2014-01-01

Uranium Energy Corp (UEC) is an NYSE-listed uranium exploration, development and production company headquartered in Corpus Christi, Texas. The Company was launched in late 2005 and commenced production in November 2010 using low-cost, environmentally friendly in-situ recovery (ISR) methods. The Company’s assets include a pipeline of exploration and development properties, with ISR operations in Texas built around a hub-and-spoke expansion model. Assets include significant conventional uranium mining properties in Arizona and Colorado, as well as potentially world-class exploration/development projects in an emerging uranium district in the Parana Basin, Paraguay, South America. Securing financing for an array of uranium projects in various stages of development is clearly challenging in a volatile economic environment. Yet, the potential of a compelling long-term uranium supply/demand deficit has attracted contrarian investors despite the difficulties. Since going public in 2006, UEC has relied primarily on raising capital through public equity offerings. UEC has raised over $130M in equity capital since going public as well as recently arranging a $20M debt financing with a group of lenders led by Sprott Resources and Li Ka Shing, one of Asia’s wealthiest and most influential investors. In addition to traditional equity and debt offerings, UEC has benefited from a variety of non-equity vehicles utilized by many metals and mining companies including timely acquisitions and timely divestitures. With a volatile uranium price over this period, as possible, the company has been making acquisitions during periods of low prices, and raising cash through divestitures when prices are higher, while reviewing royalty and streaming opportunities. With a plan to combine cash flow from operations and strategic partnerships, UEC is expanding production while advancing its diversified portfolio for maximum financial and sector flexibility. (author)

International uranium production. Namibian perspective

International Nuclear Information System (INIS)

Daniel, P.

1984-01-01

The Rossing uranium deposit is the only one currently being mined in Namibia. Construction began in 1974 and production started in 1979. Current production is close to 4800 s.t. U3O8 per annum. About 160 000 mt of ore and waste are removed from the open pit every day. Each truck load is radiometrically scanned to determine ore grade and is discharged either directly into the primary crusher or into low-grade stockpiles. The uranium is extracted in a sulphuric acid leaching plant and upgraded in an ion exchange and solvent extraction plant. An ion exchange plant recovers uranium from the tailings solution. Three thousand people are employed at the mine, most living in the nearby town site. Employee training and development are emphasized. Employee health is carefully monitored; no occupationally-related disease has been reported. Rossing contributes one third of the GNP of Namibia. (L.L.)

Improvements in process technology for uranium metal production

International Nuclear Information System (INIS)

Meghal, A.M.; Singh, H.; Koppiker, K.S.

1991-01-01

The research reactors in Trombay use uranium metal as a fuel. The plant to produce nuclear grade uranium metal ingots has been in operation at Trombay since 1959. Recently, the capacity of the plant has been expanded to meet the additional demand of the uranium metal. The operation of the expanded plant, has brought to the surface various shortcomings. This paper identifies various problems and describes the measures to be taken to upgrade the technology. Some comments are made on the necessity for development of technology for future requirement. (author). 6 refs., 1 fig

Physicochemical basics for production of uranium concentrate from wastes of hydrometallurgical plants and technical waters

International Nuclear Information System (INIS)

Khakimov, N.; Nazarov, Kh.M.; Khojiyon, M.; Mirsaidov, I.U.; Nazarov, K.M.; Barotov, B.B.

2012-01-01

Physicochemical and technological basics for reprocessing of uranium industry wastes of Northern Tajikistan shows that the most perspective for reprocessing is Chkalovsk tailing's wastes. Engineer and geological condition and content of radionuclides in wastes are investigated. It is determined that considered wastes by radioactivity are low-active and they can be reprocessed with the purpose of U 3 O 8 production. Grinding, crumbling, thickening and etc. operations are decreased during the wastes reprocessing process. Uranium output is more than 90%. Optimal parameters of products extraction from uranium mining industry wastes are found. Characteristics of mine and technical waters of uranium industry wastes are studied. Characteristics of mine and technical waters of Kiik-Tal and Istiklol city (former Taboshar) showed the expediency of uranium oxide extraction from them. The reasons for non-additional recovery extraction from dumps of State Enterprise 'Vostokredmet' by classical methods of uranium leaching are studied. Kinetics of sulfuric leaching of residues from anthropogenic deposit of Map 1-9 (Chkalovsk city) is investigated. Carried out investigations are revealing the flow mechanism process of residues' sulfuric leaching and enable selection of radiation regime of U 3 O 8 production. Kinetics of sorption process of uranium extraction from mine and technical waters of uranium industry wastes is studied. High sorption properties of apricot's shell comparing to other sorbents are revealed. Basic process flow diagram for reprocessing of uranium tailing wastes is developed as well as diagram for uranium extraction from mine and technical waters from uranium industry wastes which consists of the following stages: acidification, sorption, burning, leaching, sedimentation, filtration, drying.

Methods and measures of enhancing production capacity of uranium mines

International Nuclear Information System (INIS)

Ni Yuhui

2013-01-01

Limited by resource conditions and mining conditions, the production capacity of uranium mines is generally small. The main factors to affect the production capacity determination of uranium mines are analyzed, the ways and measures to enhance the production capacity of uranium mines are explored from the innovations of technology and management mode. (author)

Uranium production and environmental restoration at Priargunsky Centre (Russian Federation)

International Nuclear Information System (INIS)

Shatalov, V.V.; Boitsov, A.V.; Nikolsky, A.L.; Chernigov, V.G.; Ovseichuk, V.A.

2002-01-01

The state enterprise 'Priargunsky Mining and Chemical Production Association' (PPGHO) is the only active uranium production centre in Russia in last decade. Mining has been operated since 1968 by two open pits and four underground mines. It is based on resources of 19 volcanic-type deposits of Streltsovsk U-ore region situated at the area of 150 km 2 . Milling and processing has been carried out since 1974 at the local hydrometallurgical plant. Since the mid 1980s, limited amount of uranium is produced by heap and block leaching methods. High level of total production marks PPGHO as one of the outstanding uranium production centers worldwide. Significant amount of solid, liquid and gas wastes have been generated for more than 30 years. The principal environmental contamination comes from waste rock piles, mine water and tailing ponds. Liquid waste seepage through tailing pond bed can essentially contaminate underground waters. The principal environmental remediation activities are: waste rock dumps and open pits rehabilitation; waste rock utilization for industrial needs; heap and block leaching mining development, strengthening dam bodies and construction intercepting wells below the tailing pond dam, hydrogeological monitoring, upgrade of mine water treatment unit. Waste is being managed by the environmental service team of PPGHO. Environmental restoration activities, including rehabilitation of the territories and waste utilization, are implemented gradually in line with decommissioning of enterprise's particular facilities. (author)

Uranium and thorium occurrences in New Mexico: distribution, geology, production, and resources, with selected bibliography. Open-file report OF-183

International Nuclear Information System (INIS)

McLemore, V.T.

1983-09-01

Over 1300 uranium and thorium occurrences are found in over 100 formational units in all but two counties, in all 1- by 2-degree topographic quadrangles, and in all four geographic provinces in New Mexico. Uranium production in New Mexico has surpassed yearly production from all other states since 1956. Over 200 mines in 18 counties in New Mexico have produced 163,010 tons (147,880 metric tons) of U 3 O 8 from 1948 to 1982, 40% of the total uranium production in the United States. More than 99% of this production has come from sedimentary rocks in the San Juan Basin area in northwestern New Mexico; 96% has come from the Morrison Formation alone. All of the uranium reserves and the majority of the potential uranium resources in New Mexico are in the Grants uranium district. About 112,500 tons (102,058 metric tons) of $30 per pound of U 3 O 8 reserves are in the San Juan Basin, about 55% of the total $30 reserves in the United States. Thorium reserves and resources in New Mexico have not been adequately evaluated and are unknown. Over 1300 uranium and thorium occurrences are described in this report, about 400 of these have been examined in the field by the author. The occurrence descriptions include information on location, commodities, production, development, geology, and classification. Over 1000 citations are included in the bibliography and referenced in the occurrence descriptions. Production statistics for uranium mines that operated from 1948 to 1970 are also included. Mines that operated after 1970 are classified into production categories. 43 figures, 9 tables

Australian uranium resources and production in a world context

International Nuclear Information System (INIS)

Cleary, B.

2003-01-01

The aim of the paper is to discuss Australian uranium resources and production from the perspective of ERA, the world's third-largest uranium producer, and one of only three producing uranium mining companies in Australia. ERA is a long-term supplier of uranium concentrates for the nuclear power generation industry overseas, a key part of clean global energy supply. ERA's Ranger plant was designed to produce 3,000t U 3 Og/yr, with expansion of the plant hi the early 90s to a 5,700t U 3 O 8 /yr capacity. Australia continues to have the worlds' largest reserves of uranium recoverable at costs of US$40 kg or less, but lags behind Canada in primary production of uranium. This paper discusses some of the reasons for the gap between resources and production, with examples from the company's own experience. Political, social and environmental factors have played a big role in the development of the uranium industry - ERA has been in the forefront of these issues as it pursues sustainable development practices

The uranium supply strategy of China

International Nuclear Information System (INIS)

Gao, S.

2014-01-01

Currently there are 28 units of nuclear power plants (NPPs) under construction in China. Most of these plants will be put into operation sequentially in a couple years. The paper will present the operational and construction status of NPPs in China. As the reactor fleet increases, the requirement for uranium will also substantially increase. Due to declining air quality, as atmospheric pollution spreads rapidly from northern parts to southern parts of China, the option to develop nuclear power has become the highest priority. Uranium demand will be the key to support the expanded nuclear power in the future. Current and future requirements of uranium and the envisaged supply strategy will be discussed. Domestic production is seen as one of the channels to meet the increased requirement. As the uranium price remain low, there will be limited the expansion of domestic production in the short term. The exploration of economic resources is being promoted. Decreasing production costs is mandated in operations due to low uranium prices at present. Development of overseas uranium resources is another channel to supply for the NPPs. Through acquisition of uranium mining projects, advanced uranium projects and exploration projects, China can meet the requirement of NPPs in the long-term. Joint venture partnership is also flexible option for developing uranium resources overseas. Purchasing uranium in the market is the third option. Complementing the supply by domestic production and overseas development, purchase of uranium product in the market is a simple and easy option. Advantages and disadvantages of these three channels and how these can be combined into an integrated strategy of supply and the proprotionate weightage of each channel for the potential future supply of uranium to the NNP fleet will be discussed. (author)

Uranium problem in production of wet phosphoric acid

Energy Technology Data Exchange (ETDEWEB)

Gorecka, H; Gorecki, H [Politechnika Wroclawska (Poland)

1980-01-01

The balance of the uranium in the wet dihydrate method was presented. This balance shows that a large quantity of the uranium compounds shift from mineral phosphate rock to liquid phase of decomposition pulp (about 70-85% U) and the rest moves to phosphogypsum (about 15-25% U). The contents of uranium in phosphate rock imported for our country and in products and by-products of the fertilizer industry, were determined. Concentration of uranium in the phosphogypsum is dependent on the type of mineral rock and the process of phosphogypsum crystallization. Analysis of the uranium contents in phosphogypsum samples and results of the sedimentation analysis indicated influence of the specific surface of phosphogypsum crystals on the uranium concentration. Investigation of the sets of samples obtained in the industrial plant proved that phosphogypsum cake washed counter-currently on the filter contained from 10 to 20 ..mu..g U/g. The radioactivity of these samples fluctuated from 35 to 60 pCi/g. Using solution sulphuric acid of concentration in range 2-4% by weight H/sub 2/SO/sub 4/ to washing and repulpation of the phosphogypsum enables to reduce its radioactivity to level below 25 pCi/g. This processing makes possible to utilize this waste material in the building industry. Extraction of uranium from the wet phosphoric acid using kerosen solution of the reaction product between octanol -1 and phosphorus pentaoxide showed possibility to recover over 80% of uranium contained in phosphate rock.

South African uranium resource and production capability estimates

International Nuclear Information System (INIS)

Camisani-Calzolari, F.A.G.M.; Toens, P.D.

1980-09-01

South Africa, along with Canada and the United States, submitted forecasts of uranium capacities and capabilites to the year 2025 for the 1979 'Red Book' edition. This report deals with the methodologies used in arriving at the South African forecasts. As the future production trends of the South African uranium producers cannot be confidently defined, chiefly because uranium is extracted as a by-product of the gold mining industry and is thus highly sensitive to market fluctuations for both uranium and gold, the Evaluation Group of the Atomic Energy Board has carried out numerous forecast exercises using current and historical norms and assuming various degrees of 'adverse', 'normal' and 'most favourable' conditions. The two exercises, which were submitted for the 'Red Book', are shown in the Appendices. This paper has been prepared for presentation to the Working Group on Methodologies for Forecasting Uranium Availability of the NEA/IAEA Steering Group on Uranium Resources [af

Uranium. Resources, production, and market - 2009 Red Book

International Nuclear Information System (INIS)

Anon.

2010-01-01

The ''Red Book'' has been compiled since the mid-1960s as a joint OECD/NEA and IAEA publication. The analysis presents an overview of present uranium supply and demand with perspectives reaching as far as 2035. Data from 35 countries were accumulated about exploration, resources, production, and prices. The 23 rd edition contains the most recent basic evaluations of the world uranium market, providing a profile of nuclear fuel supply. Forecasts of nuclear generating capacity and uranium requirement for reactor use up until 2035 are presented along with a discussion of uranium supplies and aspects of demand beyond that time frame. Worldwide expenditures for the exploration of uranium resources in 2008 totaled more than US $1.6 billion, which is a 133% increase over expenses in 2006. Most of the important producer countries reported rising expenses for exploration as well as for commissioning new production centers. The total ''identified'' (=reasonably assured and inferred) reserves as of January 1, 2009 in the 3 O 8 ) category decreased slightly to 5,404,000 t U while a clear increase to 6,306,300 t U was seen in the re-introduced ''high cost'' category ( 3 O 8 ). Uranium production in 2008 amounted to 43,880 t U, which is an increase of 6% over 2007 (41,244 t U), and of 11% over 2006 (39,617 t U). In 2008, worldwide uranium production (43,880 t U) covered roughly 74% of the worldwide requirement for use in reactors (59,065 t U). The balance was met out of secondary sources. (orig.)

Uranium resources, production and demand in South Africa

Energy Technology Data Exchange (ETDEWEB)

Brynard, H J; Ainslie, L C [Atomic Energy Corporation of South Africa Ltd., Pretoria (South Africa)

1990-06-01

This paper provides a review of the historical development of the South African uranium market and the current status of uranium exploration, resources and production. A prognosticated view of possible future demand for uranium in South Africa is attempted, taking cognisance of the finite nature of the country's coal resources and estimated world uranium demand. Although well endowed with uranium resources, South Africa could face a shortage of this commodity in the next century, should the predicted electricity growth materials. (author)

Uranium resources, production and demand in South Africa

International Nuclear Information System (INIS)

Brynard, H.J.; Ainslie, L.C.

1990-01-01

This paper provides a review of the historical development of the South African uranium market and the current status of uranium exploration, resources and production. A prognosticated view of possible future demand for uranium in South Africa is attempted, taking cognisance of the finite nature of the country's coal resources and estimated world uranium demand. Although well endowed with uranium resources, South Africa could face a shortage of this commodity in the next century, should the predicted electricity growth materials. (author)

Nuclear material control and accounting system evaluation in uranium conversion operations

International Nuclear Information System (INIS)

Moreira, Jose Pontes

1994-01-01

The Nuclear Material Control and Accounting Systems in uranium conversion operations are described. The conversion plant, uses ammonium diuranate (ADU), as starting material for the production of uranium hexafluoride. A combination of accountability and verification measurement is used to verify physical inventory quantities. Two types of inspection are used to minimize the measurements uncertainty of the Material Unaccounted For (MUF) : Attribute inspection and Variation inspection. The mass balance equation is the base of an evaluation of a Material Balance Area (MBA). Statistical inference is employed to facilitate rapid inventory taking and enhance material control of Safeguards. The calculation of one sampling plan for a MBA and the methodology of inspection evaluation are also described. We have two kinds of errors : no detection and false delation. (author)

Physicochemical basics for production of uranium concentrate from wastes of hydrometallurgical plants and technical waters

International Nuclear Information System (INIS)

Khakimov, N.; Nazarov, Kh.M.; Khojiyon, M.; Mirsaidov, I.U.; Nazarov, K.M.; Barotov, B.B.

2012-01-01

Physicochemical and technological basics for reprocessing of uranium industry wastes of Northern Tajikistan shows that the most perspective for reprocessing is Chkalovsk tailing's wastes. Engineer and geological condition and content of radionuclides in wastes are investigated. It is determined that considered wastes by radioactivity are low-active and they can be reprocessed with the purpose of U 3 O 8 production. Grinding, crumbling, thickening and etc. operations are decreased during the wastes reprocessing process. Uranium output is more than 90%. Optimal parameters of products extraction from uranium mining industry wastes are found. Characteristics of mine and technical waters of uranium industry wastes are studied. Characteristics of mine and technical waters of Kiik-Tal and Istiklol city (former Taboshar) showed the expediency of uranium oxide extraction from them. The reasons for non-additional recovery extraction from dumps of State Enterprise 'Vostokredmet' by classical methods of uranium leaching are studied. Kinetics of sulfuric leaching of residues from anthropogenic deposit of Map 1-9 (Chkalovsk city) is investigated. Carried out investigations are revealing the flow mechanism process of residues' sulfuric leaching and enable selection of radiation regime of U 3 O 8 production. Kinetics of sorption process of uranium extraction from mine and technical waters of uranium industry wastes is studied. High sorption properties of apricot's shell comparing to other sorbents are revealed. Basic process flow diagram for reprocessing of uranium tailing wastes is developed as well as diagram for uranium extraction from mine and technical waters from uranium industry wastes which consists of the following stages: acidification, sorption, burning, leaching, sedimentation, filtration, drying.

Refining of crude uranium by solvent extraction for production of nuclear pure uranium metal

International Nuclear Information System (INIS)

Gupta, S.K.; Manna, S.; Singha, M.; Hareendran, K.N.; Chowdhury, S.; Satpati, S.K.; Kumar, K.

2007-01-01

Uranium is the primary fuel material for any nuclear fission energy program. Natural uranium contains only 0.712% of 235 U as fissile constituent. This low concentration of fissile isotope in natural uranium calls for a very high level of purity, especially with respect to neutron poisons like B, Cd, Gd etc. before it can be used as nuclear fuel. Solvent extraction is a widely used technique by which crude uranium is purified for reactor use. Uranium metal plant (UMP), BARC, Trombay is engaged in refining of uranium concentrate for production of nuclear pure uranium metal for fabrication of fuel for research reactors. This paper reviews some of the fundamental aspects of this refining process with some special references to UMP, BARC. (author)

Uranium as an energy source: resources, production and reserves from the point of view of technological development

International Nuclear Information System (INIS)

Lersow, M.

2008-01-01

A reliable evaluation of the uranium resources available in the future and associated strategic reserves must take into account trends in prospecting, degree of technological development of the different stages of the nuclear fuel cycle (starting with the mining industry and preparation), but in particular also the specific raw material and energy yield of future generations of fuel and reactor technology. Uranium deposits are categorised with regard to ore content and probable production costs. The intensified prospecting following the increase in the uranium price will lead to discovery of further reserves and thus continue to follow the historical trend. Uranium production is subject to increasingly stringent legal boundary conditions - mining and preparation are approved according to strict international standards to minimise the environmental effects during operation and to restore and recultivate the sites after closure. New or extended/modernised uranium production sites are based on modern semi- or fully automated technologies. Exposure to radiation and environmental effects are minimised by avoidance of tailings (in situ leaching), by relocation of preparation partial processes underground or by storage of the residues from conventional plants according to international standards. In addition to a rough prediction based on currently available data trends in resource development, uranium production, fuel production and the energy yield from uranium including the option of utilisation of transuranic elements for energy production in order to minimise the radioactive waste are discussed and applied qualitatively to estimation of the reserves. (orig.)

Fact sheet on uranium exploration, mining production and environmental protection

International Nuclear Information System (INIS)

2006-01-01

During the last 3 years, there has been a dramatic revival and comeback of the uranium industry in the light of the expanding nuclear power programme all over the world. As a result, there has been a boom in uranium exploration, mining and production activities to meet the higher demand of uranium and reduce the gap between uranium demand and uranium supply from mines. In coming years, additional requests for TC, training/workshop and CRPs are expected in the areas of: 1) advanced aerial and ground geophysical techniques for discovery of new deposits which could be deeply buried; 2) investigations of uranium sources in sedimentary, igneous and metamorphic environments; 3) In-Situ leaching (ISL) of uranium deposits; 4) advanced acid/alkali leaching of low, medium and high grade uranium ores and purification of uranium; 5) reclamation of used uranium mines and related environmental protection issues; and 6) uranium supply, demand and market issues. Services provided by the Nuclear Fuel Cycle and Materials Section could be workshops and hands-on field trainings at National and/or Regional levels in mines, mills and sites covering the following activities: uranium exploration involving conventional and advanced geophysical techniques and instruments, advanced drilling equipment and tools, etc.; uranium mining (open-cast and underground), recovery and purification by acid/alkali leaching, In-Situ leaching (ISL), purification by conventional and advanced solvent extraction and ion exchange techniques and concentration of uranium in the form of yellowcake (ammonium diuranate, magnesium diuranate and uranium peroxide); promoting best practices in uranium mining and milling (including tailing pond), covering environmental issues, reclamation of used uranium mines and chemistry of uranium production cycle and ground water and sustainability of uranium production. Member States interested in uranium geology, exploration, mining, milling, purification and environmental issues

Guidebook on design, construction and operation of pilot plants for uranium ore processing

International Nuclear Information System (INIS)

1990-01-01

The design, construction and operation of a pilot plant are often important stages in the development of a project for the production of uranium concentrates. Since building and operating a pilot plant is very costly and may not always be required, it is important that such a plant be built only after several prerequisites have been met. The main purpose of this guidebook is to discuss the objectives of a pilot plant and its proper role in the overall project. Given the wide range of conditions under which a pilot plant may be designed and operated, it is not possible to provide specific details. Instead, this book discusses the rationale for a pilot plant and provides guidelines with suggested solutions for a variety of problems that may be encountered. This guidebook is part of a series of Technical Reports on uranium ore processing being prepared by the IAEA's Division of Nuclear Fuel Cycle and Waste Management. 42 refs, 7 figs, 3 tabs

Uranium ore mining in Spain with a focus on the closure and remediation measures in former production facilities

International Nuclear Information System (INIS)

Koch, H.; Blunck, S.; Lopez Romero, A.R.

2004-01-01

In early 2000, the uranium ore mining activities in Spain ceased. Since the middle of the last century, Spain had pushed ahead its own production of uranium concentrate with the formation of several companies (ENUSA, J.E.N.). In that period, Spain produced around 6000 t of uranium. With the completion of the operations at Andujar, La Haba and Elephante as well as Quercus at Saelices el Chico, the corporate tasks have shifted from building-up of a strategic uranium reserve to remediation and subsequent use of the locations. The operations have reached different remediation phases. While at Saelices el Chico remediation is still proceeding, the Andujar and La Haba locations are undergoing a monitoring phase as agreed for all former operating facilities. The estimated closure and remediation costs for the three operating facilities described amount to approx. 85 mio. Euro. In all three cases dealt with, however, these limited financial resources have been sufficient to successfully implement a closure and remediation concept that minimizes the risks from the facilities of uranium ore mining and processing with regard to the environment. (orig.)

Developments in uranium in 1986

International Nuclear Information System (INIS)

Chenoweth, W.L.

1987-01-01

Imported uranium and low prices continued to plague the domestic uranium industry and, as a result, the Secretary of Energy declared the domestic industry to be nonviable for the second straight year. Uranium exploration expenditures in the US declined for the eighth consecutive year. In 1986, an estimated $19 million was spent on uranium exploration, including 1.9 million ft of surface drilling. This drilling was done mainly in producing areas and in areas of recent discoveries. Production of uranium concentrate increased in 1986, when 13.8 million lb of uranium oxide (U 3 O 8 ) were produced, a 22% increase over 1985. Uranium produced as the result of solution mining and as the by-product of phosphoric acid production accounted for about 37% of the total production in the US. At the end of 1986, only 6 uranium mills were operating in the US. Canada continued to dominate the world market. The development under way at the huge Olympic Dam deposit in Australia will increase that country's production. US uranium production is expected to show a small decrease in 1987. 3 figures, 2 tables

Vacuum fusion of uranium

International Nuclear Information System (INIS)

Stohr, J.A.

1957-01-01

After having outlined that vacuum fusion and moulding of uranium and of its alloys have some technical and economic benefits (vacuum operations avoid uranium oxidation and result in some purification; precision moulding avoids machining, chip production and chemical reprocessing of these chips; direct production of the desired shape is possible by precision moulding), this report presents the uranium fusion unit (its low pressure enclosure and pumping device, the crucible-mould assembly, and the MF supply device). The author describes the different steps of cast production, and briefly comments the obtained results

Fuel powder production from ductile uranium alloys

International Nuclear Information System (INIS)

Clark, C.R.; Meyer, M.K.

1998-01-01

Metallic uranium alloys are candidate materials for use as the fuel phase in very-high-density LEU dispersion fuels. These ductile alloys cannot be converted to powder form by the processes routinely used for oxides or intermetallics. Three methods of powder production from uranium alloys have been investigated within the US-RERTR program. These processes are grinding, cryogenic milling, and hydride-dehydride. In addition, a gas atomization process was investigated using gold as a surrogate for uranium. (author)

Report of Sectional Committee on Industrialization of Uranium Enrichment

International Nuclear Information System (INIS)

1981-01-01

In order to accelerate the development and utilization of atomic energy which is the core of the substitute energies for petroleum, it is indispensable requirement to establish independent fuel cycle as the base. In particular, the domestic production of enriched uranium is necessary to eliminate the obstacles to secure the energy supply in Japan. The construction and operation of the pilot plant for uranium enrichment by centrifugal separation method have progressed smoothly, and the technical base for the domestic production of enriched uranium is being consolidated. For the time being, the service of uranium enrichment is given by USA and France, but it is expected that the short supply will arise around 1990. The start of operation of the uranium enrichment plant in Japan is scheduled around 1990, and the scale of the plant will be expanded stepwise thereafter. The scale of production is assumed as 3000 t SWU/year in 2000. Prior to this commercial plant, the prototype plant of up to 250 t SWU/year capacity will be operated in 1986, starting the production of centrifugal separators in 1983. The production line for centrifugal separators will have the capacity of up to 125 t SWU/year. The organization for operating these plants, the home production of natural uranium conversion, the uranium enrichment by chemical method and others are described. (Kako, I.)

Social Licensing in uranium mining: Experiences from the IAEA review of planned Mukju River Uranium Project, Tanzania

International Nuclear Information System (INIS)

Schnell, Henry

2014-01-01

The IAEA Uranium Production Site Appraisal Team (UPSAT) programme is designed to assist Member States to enhance the operational performance and the occupational, public and environmental health and safety of uranium mining and processing facilities across all phases of the uranium production cycle. These include exploration, resource assessment, mining, processing, waste management, site management and remediation, and final closure.

Uranium favourability and evaluation in Mongolia (phase II), recent events in uranium resources and production in Mongolia

International Nuclear Information System (INIS)

Batbold, T.

2001-01-01

Uranium exploration in Mongolia covered a period of over 5 decades. The main results of these activities were the discoveries of 6 uranium deposits and about 100 occurrences as well as numerous favourable indications. Sizable resources are found mainly in deposits of the sandstone, volcanic and alkaline intrusive types. Of these, the first two are considered to be of economic importance. Uranium production in Mongolia started in 1989 with the exploitation of volcanic type uranium deposits of the Mongol-Priargun metallogenic province, known as the Dornot Mine. Due to political and economic changes in the country and neighbouring areas of the Russian Federation, this uranium production was terminated in 1995. A new plan to restart production at the Mardai-gol deposits as a joint venture between Mongolia, the Russian Federation and a US company is being considered. (author)

The model of interaction with the National Operator when doing uranium mining in Kazakhstan

International Nuclear Information System (INIS)

Yermilov, A.; Niyetbayev, M.; Sakharova, Y.

2014-01-01

The report presents a model of organizational and production interaction with the National Operator, NAC Kazatomprom JSC, with regard to uranium mining in Kazakhstan by means of mechanism of joint management of mining, processing and service companies. NAC Kazatomprom JSC is the world's largest producer of uranium, and Uranium One Holding is the largest foreign partner of the National Operator. The mining assets of Uranium One Holdings include the following joint ventures: Betpak Dala LLP (South Inkai and Akdala Mines), Karatau LLP, Akbastau JSC, Kyzylkum LLP and KRC Zarechnoye JSC. It shows that the project management in the form of joint ventures allows for minimization of investment risks in Kazakhstan. The practice of corporate communication with NAC Kazatomprom JSC goes far beyond the “investment– receipt of dividends” scheme when the investment guarantees mean control over the enterprise activities through participation in the meetings of enterprise management bodies. The sustainable model has been developed for the interaction with the National Operator and with state authorities of the Republic of Kazakhstan through or together with the National Operator, whereby various projects have been implemented starting with the joint support of social development of Kazakhstan regions in excess of the minimum amounts established by the government in subsoil use contracts (through Kazatomprom-Demeu LLP, specially established for this purpose) and ending with the implementation of such major projects as the “Atomic Ring” or innovative projects on the construction of alternative energy sources (solar power plant) on sites of joint industrial projects. Effective cooperation with the National operator Kazatomprom allowed to successfully establish and run at the jointly owned mines the program of efficiency improvement which stimulates continuous improvement of current operations and results in considerable cost reduction. The key ideas of the Efficiency

Converting the Caetité Mill Process to Enhance Uranium Recovery and Expand Production

Energy Technology Data Exchange (ETDEWEB)

Gomiero, L. A.; Scassiotti Filho, W.; Veras, A., E-mail: gomiero@inb.gov.br [Indústrias Nucleares do Brasil S/A — INB, Caetité, BA (Brazil); Cunha, J. W. [Instituto de Engenharia Nuclear-IEN/CNEN, Rio de Janeiro, RJ (Brazil); Morais, C. A. [Centro do Desenvolvimento da Tec. Nuclear-CDTN/CNEN, Belo Horizonte, MG (Brazil)

2014-05-15

The Caetité uranium mill was commissioned in 2000 to produce about 340 t U per year from an uranium ore averaging 0.29% U{sub 3}O{sub 8}. This production is sufficient to supply the two operating nuclear power plants in the country. As the Brazilian government has recently confirmed its plan to start building another ones from 2009, the uranium production will have to expand its capacity in the next two years. This paper describes the changes in the milling process that are being evaluated in order to not only increase the production but also the uranium recovery, to fulfil the increasing local demand. The heap leaching process will be changed to conventional tank agitated leaching of ground ore slurry in sulphuric acid medium. Batch and pilot plant essays have shown that the uranium recovery can increase from the 77% historical average to about 93%. As the use of sodium chloride as the stripping agent has presented detrimental effects in the extraction and stripping process, two alternatives are being evaluated for the uranium recovery from the PLS: (a) uranium peroxide precipitation at controlled pH from a PLS that was firstly neutralized and filtered. Batch essays have shown good results with a final calcined precipitate averaging 99% U{sub 3}O{sub 8}. Conversely the results obtained at the first pilot plant essay has shown that the precipitation conditions of the continuous process calls for further evaluation. The pilot plant is being improved and another essay will be carried out. (b) uranium extraction with a tertiary amine followed by stripping with concentrated sulphuric acid solution. Efforts are being made to recover the excess sulphuric acid from the pregnant stripping solution to enhance the economic viability of the process and to avoid the formation of a large quantity of gypsum in the pre-neutralization step before the uranium peroxide precipitation. (author)

Operational experience in the production of 131Molybdenum and 99Iodine with high and low uranium enrichment

International Nuclear Information System (INIS)

Bravo, C.; Cristini, Pablo R..; Novello, A.; Bronca, M.; Cestau, Daniel; Centurion, R.; Bavaro, R.; Cestau, J.; Gualda, E.; Bronca, P.; Carranza, Eduardo C.

2009-01-01

In 1992, in an effort to curtail use of Highly Enriched Uranium (HEU), hoping to alleviate nuclear security concerns, United States passed the Schumer amendment to the Energy Policy Act. This legislation conditioned U.S. export of HEU to foreign companies, understanding that these companies would switch as soon as possible to Lowly Enriched Uranium (LEU). This paper describes 99 Mo production flow chart, characteristics of process cells, shielding, systems of manipulation at distance, cell ventilation system and the method for personal dose monitoring. Production evolution for the span of years 1998 to 2007 is given by indicators, keeping in mind enrichment proportion change. Evolution shown on the indicators is directly related to the application of Safety Culture concepts adopted by personnel. (author)

Some economic aspects of the low enriched uranium production

International Nuclear Information System (INIS)

1990-05-01

At the Technical Committee Meeting on Economics of Low Enriched Uranium 14 papers were presented. A separate abstract was prepared for each of these papers. The five technical sessions covered several economic aspects of uranium concentrates production, conversion into uranium hexafluoride and uranium enrichment and the recycling of U and Pu in LWR. Four Panel discussions were held to discuss the uranium market trends, the situation of conversion industry, the reprocessing and the uranium market, the future trends of enrichment and the economics of LWRs compared with other reactors. Refs, figs and tabs

Uranium, resources, production and demand

International Nuclear Information System (INIS)

1990-01-01

The thirteenth edition of the report looks at recent developments and their impact on the short term (i.e. to the year 2005) and presents a longer term (to 2030) analysis of supply possibilities in the context of a range of requirement scenarios. It presents results of a 1989 review of uranium supply and demand in the World Outside Centrally Planned Economies Areas. It contains updated information on uranium exploration activities, resources and production for over 40 countries including a few CPEs, covering the period 1987 and 1988

Development of uranium metal targets for 99Mo production

International Nuclear Information System (INIS)

Wiencek, T.C.; Hofman, G.L.

1993-10-01

A substantial amount of high enriched uranium (HEU) is used for the production of medical-grade 99 Mo. Promising methods of producing irradiation targets are being developed and may lead to the reduction or elimination of this HEU use. To substitute low enriched uranium (LEU) for HEU in the production of 99 Mo, the target material may be changed to uranium metal foil. Methods of fabrication are being developed to simplify assembly and disassembly of the targets. Removal of the uranium foil after irradiation without dissolution of the cladding is a primary goal in order to reduce the amount of liquid radioactive waste material produced in the process. Proof-of-concept targets have been fabricated. Destructive testing indicates that acceptable contact between the uranium foil and the cladding can be achieved. Thermal annealing tests, which simulate the cladding/uranium diffusion conditions during irradiation, are underway. Plans are being made to irradiate test targets

Thermodynamic Simulation of Equilibrium Composition of Reaction Products at Dehydration of a Technological Channel in a Uranium-Graphite Reactor

Science.gov (United States)

Pavliuk, A. O.; Zagumennov, V. S.; Kotlyarevskiy, S. G.; Bespala, E. V.

2018-01-01

The problems of accumulation of nuclear fuel spills in the graphite stack in the course of operation of uranium-graphite nuclear reactors are considered. The results of thermodynamic analysis of the processes in the graphite stack at dehydration of a technological channel, fuel element shell unsealing and migration of fission products, and activation of stable nuclides in structural elements of the reactor and actinides inside the graphite moderator are given. The main chemical reactions and compounds that are produced in these modes in the reactor channel during its operation and that may be hazardous after its shutdown and decommissioning are presented. Thermodynamic simulation of the equilibrium composition is performed using the specialized code TERRA. The results of thermodynamic simulation of the equilibrium composition in different cases of technological channel dehydration in the course of the reactor operation show that, if the temperature inside the active core of the nuclear reactor increases to the melting temperature of the fuel element, oxides and carbides of nuclear fuel are produced. The mathematical model of the nonstationary heat transfer in a graphite stack of a uranium-graphite reactor in the case of the technological channel dehydration is presented. The results of calculated temperature evolution at the center of the fuel element, the replaceable graphite element, the air gap, and in the surface layer of the block graphite are given. The numerical results show that, in the case of dehydration of the technological channel in the uranium-graphite reactor with metallic uranium, the main reaction product is uranium dioxide UO2 in the condensed phase. Low probability of production of pyrophoric uranium compounds (UH3) in the graphite stack is proven, which allows one to disassemble the graphite stack without the risk of spontaneous graphite ignition in the course of decommissioning of the uranium-graphite nuclear reactor.

Worldwide developments in uranium

International Nuclear Information System (INIS)

Hoellen, E.E.

1987-01-01

World uranium production will continue to change in most major producing nations. Canadian production will increase and will be increasingly dominated by western producers as eastern Canadian high-cost production declines. Australian production will increase as major projects come into operation before 2000. US production will stabilize through the end of the century. South African production will be dependent upon the worldwide support for economic sanctions. China's entry into the world market injects yet another variable into the already cloudy supply picture. Many risks and uncertainties will face uranium producers through the 1980s. Recognizing that the uranium industry is not a fast-growing market, many existing and potential producers are seeking alternate investment courses, causing a restructuring of the world uranium production industry in ways not anticipated even a few years ago. During the restructuring process, world uranium production will most likely continue to exceed uranium consumption, resulting in a further buildup of world uranium inventories. Inventory sales will continue to redistribute this material. As inventory selling runs its course, users will turn to normal sources of supply, stimulating additional production to meet needs. Stimulation in the form of higher prices will be determined by how fast producers are willing and able to return to the market. Production costs are expected to have an increasing impact as it has become apparent that uranium resources are large in comparison to projected consumption. Conversely, security-of-supply issues have seemed to be of decreasing magnitude as Canada, Australia, and other non-US producers continue to meet delivery commitments

Uranium-production forecasting: the simulation of a South African gold mine

International Nuclear Information System (INIS)

Boydell, D.W.

1979-01-01

A computer program is described that estimates the amount of uranium that will be produced from a mine as a co-product of gold subject to a changing economic environment. The program makes use of two models. The first simulates activities underground, whereas the second simulates the performance of processing plant on the surface. The combination of these models generates a description of the flow of ore from stopes and from development, through hoisting, sorting, and the metallurgical plant to the despatch of saleable product. The total production of uranium to the end of the life of the mine constitutes the uranium reserve. The effects on production forecasts and reserve estimates of future trends in cost and price factors are illustrated by results generated from the application of the program to a typical South African mine producing gold and uranium. The graphs presented show that South Africa's future uranium production from underground sources is critically dependent on the gold price in the years ahead. (author)

Patterns and Features of Global Uranium Resources and Production

Science.gov (United States)

Wang, Feifei; Song, Zisheng; Cheng, Xianghu; Huanhuan, MA

2017-11-01

With the entry into force of the Paris Agreement, the development of clean and low-carbon energy has become the consensus of the world. Nuclear power is one energy that can be vigorously developed today and in the future. Its sustainable development depends on a sufficient supply of uranium resources. It is of great practical significance to understand the distribution pattern of uranium resources and production. Based on the latest international authoritative reports and data, this paper analysed the distribution of uranium resources, the distribution of resources and production in the world, and the developing tendency in future years. The results show that the distribution of uranium resources is uneven in the world, and the discrepancies between different type deposits is very large. Among them, sandstone-type uranium deposits will become the main type owing to their advantages of wide distribution, minor environmental damage, mature mining technology and high economic benefit.

Production and analysis of ultradispersed uranium oxide powders

Science.gov (United States)

Zajogin, A. P.; Komyak, A. I.; Umreiko, D. S.; Umreiko, S. D.

2010-05-01

Spectroscopic studies are made of the laser plasma formed near the surface of a porous body containing nanoquantities of uranium compounds which is irradiated by two successive laser pulses. The feasibility of using laser chemical methods for obtaining nanoclusters of uranium oxide particles in the volume of a porous body and the simultaneous possibility of determining the uranium content with good sensitivity are demonstrated. The thermochemical and spectral characteristics of the analogs of their compounds with chlorine are determined and studied. The possibility of producing uranium dioxides under ordinary conditions and their analysis in the reaction products is demonstrated.

Production, inventories and HEU in the world uranium market: Production's vital role

International Nuclear Information System (INIS)

Underhill, D.H.

1997-01-01

This paper analyses recent uranium supply and demand relationship and projects supply through 2010. The extremely depressed record low market prices have led to the ongoing annual inventory drawdown of over 25,000 t U resulting from the current 45% world production shortfall. The policy of the European Union and anti-dumping related activities in the USA are restricting imports of uranium from CIS producers to a majority of the world's nuclear utilities. These factors are reducing low priced uranium supply and forcing buyers to again obtain more of their requirements from producers. It discusses how the sale of Low Enriched Uranium (LEU) produced from of 550 t High Enriched Uranium (HEU) from Russia and Ukraine could potentially supply about 15% of world requirements through 2010. However, legislation currently being developed by the US Congress may ration the sale of this material, extending the LEU supply well into the next century. Nuclear generation capacity and its uranium requirements are projected to grow at about 1.5% through 2010. Demand for new uranium purchases is however, increasing at the much higher rate of 25-30% over the next 10-15 years. This increasing demand in the face of decreasing supply is resulting in a market recovery in which the spot price for non-CIS produced uranium has risen over 25% since October 1994. Prices will continue to increase as the market equilibrium shifts from a balance with alternative excess low priced supply to an equilibrium between production and demand. 19 refs, 14 figs, 2 tabs

Development of the Ranger uranium milling operations

International Nuclear Information System (INIS)

Baily, P.A.

1982-01-01

The development and operation of the Ranger uranium project is described. In 1969 Ranger discovered a uranium-bearing ore deposit in the Alligator Rivers Region of the Northern Territory of Australia. Extensive testwork on drill core samples proved the viability of the extraction of the uranium and a process flowsheet and plant design criteria were developed based on a conventional crushing, grinding, acid leach, C.C.D., solvent extraction circuit. Detailed design concentrated on plant layout, materials of construction, equipment vendor selection and process control. These factors required special attention because of the remote location of the mine and the high cost and difficulty in obtaining trained labour for such sites. Environmental considerations were key factors in design. The mine is located adjacent to a national park and has an average rainfall of 1,600 mm. No water or liquid effluents are to be released from the project area and thus water management is a key factor. Tailings are ponded in an impervious earth-rockfill dam

Idaho National Engineering and Environmental Laboratory Site Report on the Production and Use of Recycled Uranium

Energy Technology Data Exchange (ETDEWEB)

L. C. Lewis; D. C. Barg; C. L. Bendixsen; J. P. Henscheid; D. R. Wenzel; B. L. Denning

2000-09-01

Recent allegations regarding radiation exposure to radionuclides present in recycled uranium sent to the gaseous diffusion plants prompted the Department of Energy to undertake a system-wide study of recycled uranium. Of particular interest, were the flowpaths from site to site operations and facilities in which exposure to plutonium, neptunium and technetium could occur, and to the workers that could receive a significant radiation dose from handling recycled uranium. The Idaho National Engineering and Environmental Laboratory site report is primarily concerned with two locations. Recycled uranium was produced at the Idaho Chemical Processing Plant where highly enriched uranium was recovered from spent fuel. The other facility is the Specific Manufacturing Facility (SMC) where recycled, depleted uranium is manufactured into shapes for use by their customer. The SMC is a manufacturing facility that uses depleted uranium metal as a raw material that is then rolled and cut into shapes. There are no chemical processes that might concentrate any of the radioactive contaminant species. Recyclable depleted uranium from the SMC facility is sent to a private metallurgical facility for recasting. Analyses on the recast billets indicate that there is no change in the concentrations of transuranics as a result of the recasting process. The Idaho Chemical Processing Plant was built to recover high-enriched uranium from spent nuclear fuel from test reactors. The facility processed diverse types of fuel which required uniquely different fuel dissolution processes. The dissolved fuel was passed through three cycles of solvent extraction which resulted in a concentrated uranyl nitrate product. For the first half of the operating period, the uranium was shipped as the concentrated solution. For the second half of the operating period the uranium solution was thermally converted to granular, uranium trioxide solids. The dose reconstruction project has evaluated work exposure and

Uranium from Coal Ash: Resource Assessment and Outlook on Production Capacities

International Nuclear Information System (INIS)

Monnet, Antoine

2014-01-01

Conclusion: Uranium production from coal-ash is technically feasible: in some situations, it could reach commercial development, in such case, fast lead time will be a plus. Technically accessible resources are significant (1.1 to 4.5 MtU). Yet most of those are low grade. Potential reserves don’t exceed 200 ktU (cut-off grade = 200 ppm). • By-product uranium production => constrained production capacities; • Realistic production potential < 700 tU/year; • ~ 1% of current needs. → Coal ash will not be a significant source of uranium for the 21st century – even if production constrains are released (increase in coal consumption

Chapter 1. General information about uranium. 1.10. Uranium application

International Nuclear Information System (INIS)

Khakimov, N.; Nazarov, Kh.M.; Mirsaidov, I.U.

2011-01-01

Full text: Metallic uranium or its compounds are used as nuclear fuel in nuclear reactors. A natural or low-enriched admixture of uranium isotopes is applied in stationery reactors of nuclear power plants, and products of a high enrichment degree are used in nuclear power plants or in reactors that operates with fast neutrons. 235 U is a source of nuclear energy in nuclear weapons. Depleted uranium is used as armour-piercing core in bombshells. 238 U serves as a source of secondary nuclear fuel - plutonium. (author)

Chapter 1. General information about uranium. 1.10. Uranium application

International Nuclear Information System (INIS)

Khakimov, N.; Nazarov, Kh.M.; Mirsaidov, I.U.

2012-01-01

Full text: Metallic uranium or its compounds are used as nuclear fuel in nuclear reactors. A natural or low-enriched admixture of uranium isotopes is applied in stationery reactors of nuclear power plants, and products of a high enrichment degree are used in nuclear power plants or in reactors that operates with fast neutrons. 235 U is a source of nuclear energy in nuclear weapons. Depleted uranium is used as armour-piercing core in bombshells. 238 U serves as a source of secondary nuclear fuel - plutonium.

Assessment of radiological status of Bagjata underground uranium mine operating in the east Singhbhum District of Jharkhand

International Nuclear Information System (INIS)

Rana, B.K.; Meena, J.S.; Thakur, V.K.; Sahoo, S.K.; Tripathi, R.M.; Puranik, V.D.

2012-01-01

Bagjata uranium mine deposits (22 °28’ 07”N and 86°29’ 36” E) is located in Dhalmugarh subdivision of East Singhbhum district of Jharkhand. This mine was commissioned in 2008 and presently it is operating with a production capacity of 500 tonne/day. The mining of uranium ores can lead to both internal and external exposures of workers. Internal exposure arises from the inhalation of radon gas and its decay products and radionuclides in ore dust. The contribution of respirable ore dust toward internal exposure has been reported to be insignificant in a low ore grade uranium mines by several authors. Radon gas is produced by the alpha decay of 226 Ra, which is a product of the long lived antecedent uranium ( 238 U), is present in the rocks, decays to a number of short-lived decay products that are themselves radioactive. Radon gas diffuses into the mine air through cracks and fissures present in the ore body, during blasting, mucking and fragmentation of ore body in mine. The short-lived daughters, 218 Po, 214 Pb, 214 Bi and 214 Po, are the principal contributor to internal exposure to mine workers. Radon has been recognized as a radiation hazard causing excess lung cancer among underground miners (NAS, 1988; ATSDR, 1990). 222 Rn concentration in the mine air was estimated by using a scintillation cell technique

Experience of IAEA UPSAT mission to Tanzanian uranium sites as a means of sustaining best practice for uranium production in Tanzania

International Nuclear Information System (INIS)

Mwalongo, D.; Kileo, A.

2014-01-01

Utilization of nuclear power has been escalating, hence the growing demand for Uranium for the world nuclear power worldwide and in particular Asia and Middle East. This has influenced uranium exploration, development and investment in different countries in the world. In 2007, Tanzania witnessed extensive uranium exploration investment and discovery of several sites with economically viable uranium deposits at Bahi, Manyoni and Mkuju River. The most advanced project is Mkuju River Project located in the Selous Game Reserve, which is a classified UNESCO World Heritage site. At a time of discovery, the country had no previous experience managing uranium production cycle, hence the necessity for cooperation with national and international stakeholders to ensure safe, secure and safeguarded Uranium mining. This development pressed a need to quickly and efficiently setting up of an internationally accepted best practice for uranium mining in the country. Preparations and stakeholder involvement in setting regulatory framework for uranium mining were initiated. Therefore, the request was submitted to International Atomic Energy Agency (IAEA) Uranium Production Site Appraisal Team (UPSAT) mission to review the country’s regulatory readiness for uranium governance. The review mission aimed at appraising the country’s preparedness for overseeing the Uranium Production Cycle in general and with emphasis on the planned Mkuju River Project (MRP) in the south of the country in particular. The mission comprehensively reviewed the regulatory system, sustainable uranium production life cycle, health, safety and environment, social licensing and capacity building and gave objective recommendations based on best practice. Therefore, this paper briefly reviews the impact of the first UPSAT mission in African soil for fostering sustainable best practice for uranium life cycle in Tanzania. (author)

Analyses of uranium in some phosphate commercial products

International Nuclear Information System (INIS)

Kamel, N.H.M.; Sohsah, M.; Mohammad, H.M.; Sadek, M.

2005-01-01

The raw materials used in manufacturing of phosphate fertilizer products were derived from rocks. Rocks contain a remarkable of natural radioactivity. Uranium and phosphorous were originally initiated at the same time of the initiated rocks. The purpose of this research is to investigate solubility of uranium phosphate species at the phosphate fertilizer samples, samples including; raw phosphate material, single super phosphates (SSP) granules and powdered, triple super phosphates (TSP) and phosphogypsum samples were obtained from Abu-Zabal factory in Egypt. Solubility of uranium phosphate species was estimated. It was found that, less than half of the uranium phosphate species are soluble in water. The soluble uranium may be enter into the food chains by plant. Therefore, restriction should be done in order to limit contamination of land and the public

Review of recent developments in uranium extraction technology

International Nuclear Information System (INIS)

Alfredson, P.G.; Crawford, R.E.; Ring, R.J.

1978-12-01

Developments in uranium ore processing technology since the AAEC Symposium on Uranium Processing in July 1972 are reviewed. The main developments include the use of autogenous or semi-autogenous grinding, beneficiation techniques such as radiometric sorting, flotation, magnetic and gravity seperation, strong acid and ferric bacterial leaching processes, solution mining and heap leaching operations, horizontal belt filters for solid-liquid separation, continuous ion exchange processes for use with solutions containing up to 8 wt % solids, hydrogen peroxide and ammonia for the precipitation of uranium to improve product yield and purity, and the recovery of by-product uranium from the manufacture of phosphoric acid and copper processing operations

Uranium Fuel Plant. Applicants environmental report

International Nuclear Information System (INIS)

1975-05-01

The Uranium Fuel Plant, located at the Cimarron Facility, was constructed in 1964 with operations commencing in 1965 in accordance with License No. SNM-928, Docket No. 70-925. The plant has been in continuous operation since the issuance of the initial license and currently possesses contracts extending through 1978, for the production of nuclear fuels. The Uranium Plant is operated in conjunction with the Plutonium Facility, each sharing common utilities and sanitary wastes disposal systems. The operation has had little or no detrimental ecological impact on the area. For the operation of the Uranium Fuel Fabrication Plant, initial equipment provided for the production of UO 2 , UF 4 , uranium metal and recovery of scrap materials. In 1968, the plant was expanded by increasing the UO 2 and pellet facilities by the installation of another complete production line for the production of fuel pellets. In 1969, fabrication facilities were added for the production of fuel elements. Equipment initially installed for the recovery of fully enriched scrap has not been used since the last work was done in 1970. Economically, the plant has benefited the Logan County area, with approximately 104 new jobs with an annual payroll of approximately $1.3 million. In addition, $142,000 is annually paid in taxes to state, local and federal governments, and local purchases amount to approximately $1.3 million. This was all in land that was previously used for pasture land, with a maximum value of approximately 37,000 dollars. Environmental effects of plant operation have been minimal. A monitoring and measurement program is maintained in order to ensure that the ecology of the immediate area is not affected by plant operations

Blueprint for domestic uranium enrichment

International Nuclear Information System (INIS)

1981-01-01

The AEC advisory committee on domestic production of uranium enrichment has studied for more than a year how to achieve the domestic enrichment of uranium by the construction and operation of a commercial enriching plant using centrifugal separation method, and the report was submitted to the Atomic Energy Commission on August 18, 1980. Japan has depended wholly on overseas services for her uranium enrichment needs, but the development of domestic enrichment has been carried on in parallel. The AEC decided to construct a uranium enrichment pilot plant using centrifuges, and it has been forwarded as a national project. The plant is operated by the Power Reactor and Nuclear Fuel Development Corp. since 1979. The capacity of the plant will be raised to approximately 75 ton SWU a year. The centrifuges already operated have provided the first delivery of fuel of about 1 ton for the ATR ''Fugen''. The demand-supply balance of uranium enrichment service, the significance of the domestic enrichment of uranium, the evaluation of uranium enrichment technology, the target for domestic enrichment plan, the measures to promote domestic uranium enrichment, and the promotion of the construction of a demonstration plant are reported. (Kako, I.)

Chemical Separation of Fission Products in Uranium Metal Ingots from Electrolytic Reduction Process

International Nuclear Information System (INIS)

Lee, Chang-Heon; Kim, Min-Jae; Choi, Kwang-Soon; Jee, Kwang-Yong; Kim, Won-Ho

2006-01-01

Chemical characterization of various process materials is required for the optimization of the electrolytic reduction process in which uranium dioxide, a matrix of spent PWR fuels, is electrolytically reduced to uranium metal in a medium of LiCl-Li 2 O molten at 650 .deg. C. In the uranium metal ingots of interest in this study, residual process materials and corrosion products as well as fission products are involved to some extent, which further adds difficulties to the determination of trace fission products. Besides it, direct inductively coupled plasma atomic emission spectrometric (ICP-AES) analysis of uranium bearing materials such as the uranium metal ingots is not possible because a severe spectral interference is found in the intensely complex atomic emission spectra of uranium. Thus an adequate separation procedure for the fission products should be employed prior to their determinations. In present study ion exchange and extraction chromatographic methods were adopted for selective separation of the fission products from residual process materials, corrosion products and uranium matrix. The sorption behaviour of anion and tri-nbutylphosphate (TBP) extraction chromatographic resins for the metals in acidic solutions simulated for the uranium metal ingot solutions was investigated. Then the validity of the separation procedure for its reliability and applicability was evaluated by measuring recoveries of the metals added

Social Licensing in uranium mining: Experiences from the IAEA review of the planned Mukju River Uranium Project, Tanzania

International Nuclear Information System (INIS)

Schnell, H.; Hilton, J.; Saint-Pierre, S.; Baldry, K.; Fan, Z.; Tulsidas, H.

2014-01-01

The IAEA Uranium Production Site Appraisal Team (UPSAT) programme is designed to assist Member States to enhance the operational performance and the occupational, public and environmental health and safety of uranium mining and processing facilities across all phases of the uranium production cycle. The scope of the appraisal process includes exploration, resource assessment, planning, environmental and social impact assessment, mining, processing, waste management, site management, remediation, and final closure. An UPSAT review was requested in 2010 by the United Republic of Tanzania (URT) to address the challenges the country is currently facing in developing its uranium mining and processing capability for the first time. The review that was carried out from 27 May to 5 June, 2013 had the objective to to appraise URT’s preparedness for overseeing the Uranium Production Cycle in general, at the same time focusing on the planned Mkuju River Project (MRP) in the south of the country in particular. The UPSAT team was tasked to report its findings according to five primary areas: 1. Regulatory system; 2. Sustainable uranium production life cycle; 3. Health, Safety and Environment (HSE); 4. Social licensing; 5. Capacity building. The paper will discuss the key findings and suggestions that were provided to governmental stakeholders and the operater to improve the planned operations. (author)

Uranium refining in South Africa. The production of uranium trioxide, considering raw material properties and nuclear purity requirements

International Nuclear Information System (INIS)

Colborn, R.P.; Bayne, D.L.G.; Slabber, M.N.

1980-01-01

Conventional practice results in raw materials being delivered to the uranium refineries in a form more suitable for transportation than for processing, and therefore the refineries are required to treat these raw materials to produce an acceptable intermediate feed stock. During this treatment, it is advantageous to include a purification step to ensure that the feed stock is of the required purity for nuclear grade uranium hexafluoride production, and this usually results in ammonium diuranate slurries of the required quality being produced as the intermediate feed stock. All subsequent processing steps can therefore be standardized and are effectively independent of the origin of the raw materials. It is established practice in South Africa to transport uranium as an ammonium diuranate slurry from the various mines to the Nufcor central processing plant for UOC production, and therefore the process for the production of uranium hexafluoride in South Africa was designed to take cognizance of existing transport techniques and to accept ammonium diuranate slurries as the raw material. The South African refinery will be able to process these slurries directly to uranium trioxide. This paper discusses the conditions under which the various ammonium diuranate raw materials, exhibiting a wide range of properties, can be effectively processed to produce a uranium trioxide of acceptably consistent properties. Mention is also made of the uranium hexafluoride distillation process adopted

Uranium update: geo-socio-political factors of U.S. production, or you wonder where the yellow went

International Nuclear Information System (INIS)

Odell, R.D.

1986-01-01

Industry developments of 1986 indicate a steady but modest confidence for recovery of the domestic nuclear raw materials business. Concerns of oversupply and foreign inroads into utility contracts were somewhat alleviated with long-overdue recognition by the US Department of Energy in November 1985 that the industry in 1984 failed to meet viability tests, as required of government by public law. However, by February of this year, the government had initiated no perceptive corrective help for the domestic industry, and the DOE was accused of enhancing its competitive position as a provider of enrichment services. New Mexico, once the leader in production of domestic uranium, is compared with Wyoming for remaining and potential reserves. The monopoly by south Texas of low-production-cost uranium in the in-situ-leach (ISL) extractive industry is threatened by oncoming ISL operations in Wyoming and the Crawford, Nebraska, area. Arizona breccia-pipe occurrence of high-grade uranium, domestically speaking, bodes well for mining operators there to compete in what is left of the domestic market

Uranium industry annual 1993

International Nuclear Information System (INIS)

1994-09-01

Uranium production in the United States has declined dramatically from a peak of 43.7 million pounds U 3 O 8 (16.8 thousand metric tons uranium (U)) in 1980 to 3.1 million pounds U 3 O 8 (1.2 thousand metric tons U) in 1993. This decline is attributed to the world uranium market experiencing oversupply and intense competition. Large inventories of uranium accumulated when optimistic forecasts for growth in nuclear power generation were not realized. The other factor which is affecting U.S. uranium production is that some other countries, notably Australia and Canada, possess higher quality uranium reserves that can be mined at lower costs than those of the United States. Realizing its competitive advantage, Canada was the world's largest producer in 1993 with an output of 23.9 million pounds U 3 O 8 (9.2 thousand metric tons U). The U.S. uranium industry, responding to over a decade of declining market prices, has downsized and adopted less costly and more efficient production methods. The main result has been a suspension of production from conventional mines and mills. Since mid-1992, only nonconventional production facilities, chiefly in situ leach (ISL) mining and byproduct recovery, have operated in the United States. In contrast, nonconventional sources provided only 13 percent of the uranium produced in 1980. ISL mining has developed into the most cost efficient and environmentally acceptable method for producing uranium in the United States. The process, also known as solution mining, differs from conventional mining in that solutions are used to recover uranium from the ground without excavating the ore and generating associated solid waste. This article describes the current ISL Yang technology and its regulatory approval process, and provides an analysis of the factors favoring ISL mining over conventional methods in a declining uranium market

Uranium industry annual 1993

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

Uranium production in the United States has declined dramatically from a peak of 43.7 million pounds U{sub 3}O{sub 8} (16.8 thousand metric tons uranium (U)) in 1980 to 3.1 million pounds U{sub 3}O{sub 8} (1.2 thousand metric tons U) in 1993. This decline is attributed to the world uranium market experiencing oversupply and intense competition. Large inventories of uranium accumulated when optimistic forecasts for growth in nuclear power generation were not realized. The other factor which is affecting U.S. uranium production is that some other countries, notably Australia and Canada, possess higher quality uranium reserves that can be mined at lower costs than those of the United States. Realizing its competitive advantage, Canada was the world`s largest producer in 1993 with an output of 23.9 million pounds U{sub 3}O{sub 8} (9.2 thousand metric tons U). The U.S. uranium industry, responding to over a decade of declining market prices, has downsized and adopted less costly and more efficient production methods. The main result has been a suspension of production from conventional mines and mills. Since mid-1992, only nonconventional production facilities, chiefly in situ leach (ISL) mining and byproduct recovery, have operated in the United States. In contrast, nonconventional sources provided only 13 percent of the uranium produced in 1980. ISL mining has developed into the most cost efficient and environmentally acceptable method for producing uranium in the United States. The process, also known as solution mining, differs from conventional mining in that solutions are used to recover uranium from the ground without excavating the ore and generating associated solid waste. This article describes the current ISL Yang technology and its regulatory approval process, and provides an analysis of the factors favoring ISL mining over conventional methods in a declining uranium market.

Construction of a new plant in Gabon by the Compagnie des Mines d'Uranium de Franceville: Three years' experience of operation

International Nuclear Information System (INIS)

Jug, V.

1987-01-01

As part of a programme to modernize and extend its means of production which had already commenced with the setting up of a solvent extraction unit in 1977, and a sulphuric acid production facility of increased capacity (60 t/d) in 1980, the Compagnie des Mines d'Uranium de Franceville (COMUF) started a new uranium ore treatment plant in 1982. The aim was to replace the older installation built in 1959-60, which had reached the limit of its capacity and whose largest equipment was in need of renewal. The new installations are capable of an annual uranium production of 1500 t of magnesium uranate. The techniques adopted were the most modern, those likely to simplify the process and improve operating costs, namely semi-autogenous grinding and solid-liquid separation using band filters. Three years of operating experience confirm the sound choice of the main options made when designing the installations. The treatment performances, especially those which are independent of the nature of the ore, and the reliability of operation are indeed excellent. Thanks to a training programme started in the late 1980s the staff adapted rapidly to the new technical environment and it has been possible to run the entire plant with almost exclusively Gabonese staff. (author). 1 tab

Improved operating strategies for uranium extraction: a stochastic simulation

International Nuclear Information System (INIS)

Broekman, B.R.

1986-01-01

Deterministic and stochastic simulations of a Western Transvaal uranium process are used in this research report to determine more profitable uranium plant operating strategies and to gauge the potential financial benefits of automatic process control. The deterministic simulation model was formulated using empirical and phenomenological process models. The model indicated that profitability increases significantly as the uranium leaching strategy becomes harsher. The stochastic simulation models use process variable distributions corresponding to manually and automatically controlled conditions to investigate the economic gains that may be obtained if a change is made from manual to automatic control of two important process variables. These lognormally distributed variables are the pachuca 1 sulphuric acid concentration and the ferric to ferrous ratio. The stochastic simulations show that automatic process control is justifiable in certain cases. Where the leaching strategy is relatively harsh, such as that in operation during January 1986, it is not possible to justify an automatic control system. Automatic control is, however, justifiable if a relatively mild leaching strategy is adopted. The stochastic and deterministic simulations represent two different approaches to uranium process modelling. This study has indicated the necessity for each approach to be applied in the correct context. It is contended that incorrect conclusions may have been drawn by other investigators in South Africa who failed to consider the two approaches separately

Uranium mining: industry performance will continue to be driven by trends in the output and price or uranium

International Nuclear Information System (INIS)

2006-01-01

Industry revenue, which rose very strongly in the mid 2000s on the back of higher prices and higher production, is expected to retreat during the outlook i period. Indications are that a small gain in real industry revenue will be made in 2007-08, reflecting slightly higher output and some- what higher Australian dollar contract prices. However, real industry revenue is then expected to fall over the remaining years of the out- , look period, as output and exports edge lower and prices ease. Production from Ranger is expected to ease as mining winds down and the operation becomes ore processing only, and no new mines or mine expansions will come on stream over this relatively short period. Large increases in spot uranium prices in the mid 2000s were driven by falling uranium stocks, increased concern over future uranium supplies and growing speculative demand for uranium. Despite very large price rises, world uranium production responded only slowly, reflect-ing the long lead-time required to either expand existing operations or bring new developments on stream

Critical analysis of world uranium resources

Science.gov (United States)

Hall, Susan; Coleman, Margaret

2013-01-01

The U.S. Department of Energy, Energy Information Administration (EIA) joined with the U.S. Department of the Interior, U.S. Geological Survey (USGS) to analyze the world uranium supply and demand balance. To evaluate short-term primary supply (0–15 years), the analysis focused on Reasonably Assured Resources (RAR), which are resources projected with a high degree of geologic assurance and considered to be economically feasible to mine. Such resources include uranium resources from mines currently in production as well as resources that are in the stages of feasibility or of being permitted. Sources of secondary supply for uranium, such as stockpiles and reprocessed fuel, were also examined. To evaluate long-term primary supply, estimates of uranium from unconventional and from undiscovered resources were analyzed. At 2010 rates of consumption, uranium resources identified in operating or developing mines would fuel the world nuclear fleet for about 30 years. However, projections currently predict an increase in uranium requirements tied to expansion of nuclear energy worldwide. Under a low-demand scenario, requirements through the period ending in 2035 are about 2.1 million tU. In the low demand case, uranium identified in existing and developing mines is adequate to supply requirements. However, whether or not these identified resources will be developed rapidly enough to provide an uninterrupted fuel supply to expanded nuclear facilities could not be determined. On the basis of a scenario of high demand through 2035, 2.6 million tU is required and identified resources in operating or developing mines is inadequate. Beyond 2035, when requirements could exceed resources in these developing properties, other sources will need to be developed from less well-assured resources, deposits not yet at the prefeasibility stage, resources that are currently subeconomic, secondary sources, undiscovered conventional resources, and unconventional uranium supplies. This

Pilot production of 325 kg of uranium carbide

International Nuclear Information System (INIS)

Clozet, C.; Dessus, J.; Devillard, J.; Guibert, M.; Morlot, G.

1969-01-01

This report describes the pilot fabrication of uranium carbide rods to be mounted in bundles and assayed in two channels of the EL 4 reactor. The fabrication process includes: - elaboration of uranium carbide granules by carbothermic reduction of uranium dioxide; - electron bombardment melting and continuous casting of the granules; - machining of the raw ingots into rods of the required dimensions; finally, the rods will be piled-up to make the fuel elements. Both qualitative and quantitative results of this pilot production chain are presented and discussed. (authors) [fr

International Symposium on Uranium Raw Material for the Nuclear Fuel Cycle: Exploration, Mining, Production, Supply and Demand, Economics and Environmental Issues. Presentations

International Nuclear Information System (INIS)

2014-01-01

The long term sustainability of nuclear power will depend on, among several factors, an adequate supply of uranium resources that can be delivered to the marketplace at competitive prices. New exploration technologies and a better understanding of the genesis of uranium ores will be required to discover often deep-seated and increasingly hard to find uranium deposits. Exploration, mining and milling technologies should be environmentally benign, and site decommissioning plans should meet the requirements of increasingly stringent environmental regulations and societal expectations. The purpose of this symposium is to analyse uranium supply–demand scenarios and to present and discuss new developments in uranium geology, exploration, mining and processing, as well as in environmental requirements for uranium operations and site decommissioning. The presentations and discussions at URAM-2014 will: - Lead to a better understanding of the adequacy of uranium sources (both primary and secondary) to meet future demand; - Provide information on geological models, new exploration concepts, knowledge and technologies that will potentially lead to the discovery and development of new uranium resources; - Describe new production technologies that have the potential to more efficiently and sustainably develop new uranium resources; and - Document the environmental compatibility of uranium production and the overall effectiveness of progressive final decommissioning and, where required, remediation of production facilities.

Production of high-purity uranium at a South African gold mine

Energy Technology Data Exchange (ETDEWEB)

Faure, A; Finney, S; Hart, H P; Jordaan, C L; Heerden, D van; Viljoen, E B; Robinson, R E; Lloyd, P J.D. [National Institute for Metallurgy, Pelindaba (South Africa)

1967-06-15

The chemistry of the Bufflex solvent-extraction process is described. Uranium is extracted by a tertiary amine solvent, from which the impurities are removed by means of dilute ammonia, and the uranium is stripped by an ammonium sulphate strip. In the pilot plant, these processes are carried out in mixer-settlers. Details of pumps, flow controllers, and materials of construction are given. The operation of the extraction, scrub, strip, precipitation and thickening, and regeneration sections is described. Comparative tests on the elution of ion-exchange resin with 10% sulphuric acid, and with nitrate, are described. The results of resin analyses and plant tests are given. A breakdown of the costs of reagents in the Bufflex process, compared with the conventional process, is given. It is concluded that a solvent-extraction process treating the sulphuric acid eluate from ion-exchange columns is technically feasible. As regards the resin itself, elution with 10% sulphuric acid is satisfactory. There is more polythionate build-up than with nitrate elution, and the capacity of the resin is slightly lower, but the difference is small. The operating cost of the Bufflex process is cheaper by at least 5 cents/lb U{sub 3}O{sub 8} produced. The product satisfies the most stringent specification for nuclear-grade uranium, except as regards cobalt, molybdenum, silicon, and hafnium. (author)

Cost study on waste management at three model Canadian uranium mines

International Nuclear Information System (INIS)

1984-03-01

A waste management cost study was initiated to determine the capital and operating costs of three different uranium waste management systems which incorporate current technologies being used in Canadian uranium mining operations. Cost estimates were to be done to a thirty percent level of accuracy and were to include all waste management related costs of a uranium ore processing facility. Each model is based on an annual uranium production of 1,923,000 kg U (5,000,000 lbs U 3 O 8 ) with a total operating life of 20 years for the facility. The three models, A, B, and C, are based on three different uranium ore grades, 0.10 percent U 3 O 8 , 0.475 percent U 3 O 8 and 1.5 percent U 3 O 8 respectively. Yellowcake production is assumed to start in January 1984. Model A is based on a conceptual 7,180 tonne per day uranium ore processing facility and waste management system typical of uranium operations in the Elliot Lake area of northern Ontario with an established infrastructure. Model B is a 1.512 tonne per day operation based on a remote uranium operation typical of the Athabasca Basin properties in northern Saskatchewan. Model C is a 466 tonne per day operation processing a high-grade uranium ore containing arsenic and heavy metal concentrations typical of some northern Saskatchewan deposits

Uranium exploration, mining and ore enrichment techniques

International Nuclear Information System (INIS)

Fuchs, H.D.; Wentzlau, D.

1985-01-01

The paper describes the different types of uranium deposits and their importance. It is shown that during the present depressed uranium market situation, mainly high grade deposits such as unconformity-related deposits can be mined economically. The different successive exploration steps are outlined including methods used for uranium. Uranium mining does not greatly differ from normal mining, but the uranium metallurgy needs its own specialized but already classic technology. Only a relative small amount of uranium can be expected from projects where uranium is produced by in situ leach methods or by extraction from phosphoric acid. A short summary of investment costs and operating costs is given for an average uranium mine. The last chapter deals with the definition of different reserve categories and outlines the uranium reserves of the western world including the uranium production (1983) and the expected uranium production capacity for 1985 and 1990. (orig.) [de

Provision by the uranium and uranium products

International Nuclear Information System (INIS)

Elagin, Yu.P.

2005-01-01

International uranium market is converted from the buyer market into the seller market. The prices of uranium are high and the market attempts to adapt to changing circumstances. The industry of uranium enrichment satisfies the increasing demands but should to increase ots capacities. On the whole the situation is not stable and every year may change the existing position [ru

The Joint NEA/IAEA Uranium Group -- its role in assessing world uranium resources, production, demand and environmental activities and issues

International Nuclear Information System (INIS)

Barthel, F.H.; Vera, I.

2002-01-01

In 1965 a 20-page report entitled World Uranium and Thorium Resources was published by the OECD-European Nuclear Energy Agency. Today, 35 years later, the report is jointly prepared by the OECD/Nuclear Energy Agency and the IAEA and published by the OECD. The report: Uranium Resources, Production and Demand also known as the Red Book is in its 18th edition. It is the only official publication on world uranium statistics and provides information from 45 or more countries. One aim of the Red Book is to obtain a uniform, worldwide acceptable classification of uranium resources. The Red Book provides statistics and analyses for resources, exploration, production, demand, secondary sources, surplus defence material and the supply and demand relationship. The sales records indicate that it is used as reference material for various purposes including public and private libraries, energy companies, uranium production companies, national and international organisation, universities and other research and business institutions. In 1996 a study was started which led to the 1999 report: Environmental Activities in Uranium Mining and Milling, a companion to the Red Book. This complementary report provides information on the site characterization, dismantling and decommissioning, waste management, water remediation, long term monitoring policies and regulations for 29 countries. A second report entitled 'Environmental Remediation of Uranium Production Facilities' is being prepared. (author)

Changes and events in uranium deposit development, exploration, resources, production and the world supply-demand relationship. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1997-09-01

This report consists of the proceedings of the Technical Committee Meeting on Recent Changes and Events in Uranium Deposit Development, Exploration, Resources, Production and the World Supply/Demand Relationship, held in co-operation with the OECD Nuclear Energy Agency (OECD/NEA) in Kiev, Ukraine, from 22 to 26 May 1995. Some of the information from this meeting was also used in preparation of the 1995 edition of ''Uranium - Resources, Production and Demand'' a joint report by the OECD/NEA and the IAEA. At the Beginning of 1995 there were 432 nuclear power plants in operation with a combined electricity generating capacity of 340 GW(e). This represents nearly a 100% increase over the last decade. In 1995 over 2228 TW·h of electricity were generated, equivalent to about 17% of the world's total electricity. To achieve this, about 61,000 t U were required as nuclear fuel. For about a decade and a half uranium production and related activities have been decreasing because of declining uranium prices. For many participants in the nuclear industry there has been little interest in uranium supply because of the oversupplied market condition. The declining production led to the development of a supply and demand balance were production is currently meeting a little over 50% of reactor requirements and the excess inventory is being rapidly drawn down. This very unstable relationship has resulted in great uncertainty about the future supply or uranium. One of the objectives of this Technical Committee meeting was to bring together specialists in the field of uranium supply and demand to collect information on new developments. This helps provide a better understanding of the current situation, as well as providing information to plan for the future. Refs, figs, tabs

The production of sinterable uranium dioxide from ammonium diuranate

International Nuclear Information System (INIS)

Fane, A.G.; Le Page, A.H.

1975-02-01

The development of a 0.13 m diameter pulsed fluidised bed reactor for the continuous production of sinterable uranium dioxide from ammonium diuranate is described. Calcination-reduction at 670 to 680 0 C produced powders with surface areas of 4 to 6 m 2 g -1 giving pellet densities in excess of 10.6 g cm -3 . Sinterability was relatively insensitive to changes in operating conditions, provided the availability of hydrogen was adequate, for gas flow rates in the range 0.95 to 1.4 l S -1 , pulse frequencies of 0.5 and 0.75 Hz and mean residence times of the solids from 0.6 to 1.4 hours. Sinterability was shown to be improved either by use of higher input concentrations, or by use of a secondary flow of hydrogen (about 5 per cent of input) fed into the powder collection system and flowing countercurrent to the UO 2 product. The maximum throughput of 17 kg UO 2 h -1 (0.6 hours mean residence time) required only 120 per cent of the stoichiometric requirement at an input concentration of 50 vol.per cent with secondary hydrogen flow. Results are given for studies of the kinetics of reduction of calcined ammonia diuranate in hydrogen and the residence time distribution of solids in a pulsed fluidised bed. Estimates based on these data suggested that the overall conversion of ammonium diuranate to uranium dioxide in the continuously operated pulsed fluidised bed reactor was in excess of 99 per cent. Continuous stabilisation of the UO 2 product was demonstrated at 12 kg h -1 or UO 2 , in a 0.15 m diameter glass stabiliser, using 10 vol.per cent air in nitrogen and a temperature of about 50 0 C. (author)

Evaluation of environmental impacts of uranium mining and milling operations in Spain

International Nuclear Information System (INIS)

Morales, M.; Lopez Romero, A.

1996-01-01

Uranium mining and production activities have been carried out by ENUSA since 1973. This report describes the evaluation of environmental aspects connected with uranium mining and milling. (author). 7 figs, 3 tabs

Recovering and recycling uranium used for production of molybdenum-99

Science.gov (United States)

Reilly, Sean Douglas; May, Iain; Copping, Roy; Dale, Gregory Edward

2017-12-12

A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina.

Uranium

Energy Technology Data Exchange (ETDEWEB)

Williams, R M

1976-01-01

Evidence of expanding markets, improved prices and the short supply of uranium became abundantly clear in 1975, providing the much needed impetus for widespread activity in all phases of uranium operations. Exploration activity that had been at low levels in recent years in Canada was evident in most provinces as well as the Northwest Territories. All producers were in the process of expanding their uranium-producing facilities. Canada's Atomic Energy Control Board (AECB) by year-end had authorized the export of over 73,000 tons of U/sub 3/0/sub 8/ all since September 1974, when the federal government announced its new uranium export guidelines. World production, which had been in the order of 25,000 tons of U/sub 3/0/sub 8/ annually, was expected to reach about 28,000 tons in 1975, principally from increased output in the United States.

Critical review of uranium resources and production capability to 2020

International Nuclear Information System (INIS)

Underhill, D.H.

2002-01-01

Even with a modest forecast of nuclear power growth for the next 25 years, it is expected that the world uranium requirements will increase. This analysis indicates uranium mine production will continue to be the primary supply of requirements through 2020. Secondary supplies, such as low enriched uranium blended from highly enriched uranium, reprocessing of spent fuel would have to make-up the remaining balance, although the contribution of US and Russian strategic stockpiles is not well known at this time. (author)

International uranium production. An eastern Canadian perspective

International Nuclear Information System (INIS)

Albino, G.R.

1984-01-01

The Eastern Canadian perspective on uranium production is based on 30 years of continuous mining at Elliot Lake and on the experience of selling uranium over the same time period, mainly to export markets. In Ontario the orebodies are basically contiguous, being part of the same large formation. All the mining is underground. Ore grades are low, but economic extraction is improved by continuity and uniformity of grades, stable ground conditions, and the ability to mine and mill on a large scale. Mining is being carried out by two companies, Denison and Rio Algom. It is unlikely that mine capacity will be increased. Government policies have significant effects on the Eastern Canadian uranium industry in particular, as to U.S. import policies. (L.L.)

Mechanism of 232U production in MTR fuel evolution of activity in reprocessed uranium

International Nuclear Information System (INIS)

Harbonnier, G.; Lelievre, B.; Fanjas, Y.; Naccache, S.J.P.

1993-01-01

The use of reprocessed uranium for research reactor fuel fabrication implies to keep operators safe from the hard gamma rays emitted by 232 U daughter products. CERCA has carried out, with the help of French CEA and COGEMA, a detailed study to determine the evolution of the radiation dose rate associated with the use of this material. (author)

Energies and media nr 28. Uranium mining exploitations and residues. Uranium mines in Niger. Depleted uranium as a by-product of enrichment

International Nuclear Information System (INIS)

2009-02-01

After some comments on recent events in the nuclear sector in different countries (USA, China, India, UK, Sweden, Italy and France), this publication addresses the issue of uranium mining exploitations and of their residues. It comments the radioactivity in mining areas, briefly discusses the issue of low doses, describes the uranium ore and its processing, indicates which are the various residues of the mining activity (sterile uncovered tailings, non exploitable mineralized rocks, ore and residue processing, residue radioactivity, mine closing down, witnesses on health in ancient mines). Some reflections are stated about uranium mines in Niger, and about depleted uranium as a by-product of the enrichment activity

Biological treatment of nitrate bearing wastewater from a uranium production plant

International Nuclear Information System (INIS)

Benear, A.K.; Kneip, R.W.

1988-01-01

The Feed Materials Production Center (FMPC) produces uranium metal products used for DOE defense programs resulting in the generation of nitrate-bearing wastewaters. To treat these wastewaters, a two-column fluidized bed biodenitrification facility (BDN) was constructed at the FMPC. The operation of the BDN resulted in substantial compliance with the design criteria limits for nitrate from July through November, 1987. Since the BDN surge lagoon (BSL) proved inadequate for providing nitrate concentration equalization, the BDN feed nitrate concentration fluctuated widely throughout this period of operation. BDN effluent caused a doubling of the hydraulic loading and a tripling of the organic loading on the FMPC sewage treatment plant (STP). Better control of the methanol feed to the BDN, coupled with reduced throughput and improved preaeration, caused a significant improvement in the operation of the STP. The overloading of the STP prompted a decision to add a stand-alone effluent treatment system to the BDN

Uranium and nuclear energy: 1986

International Nuclear Information System (INIS)

1987-01-01

The papers (25 in all) cover energy policy issues (5 papers), uranium mining safety (4 papers), uranium production (3 papers), public attitudes and waste management (4 papers), advancing enrichment technology especially laser-based techniques (4 papers) and the uranium market (5 papers). The address by Lord Marshall, chairman of the Central Electricity Generating Board, which explains why an accident like the one at Chernobyl could not happen in a British reactor is also reprinted. All are indexed separately. The first appendix lists the nuclear power plants in the world, country by country, and gives details of type, supplier and commercial operation. The second appendix lists the uranium production facilities in the world country by country giving their status, ownership and some brief comments. (U.K.)

Uranium 1990 resources, production and demand

International Nuclear Information System (INIS)

1990-01-01

Periodic assessments of world uranium supply and demand have been conducted by the OECD Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA) since the mid 1960s. Published every two years, the report URANIUM RESOURCES, PRODUCTION AND DEMAND, commonly referred to as the RED BOOK, has become an essential reference document for nuclear planners and policy makers in the international nuclear community. The latest Red Book, published in 1990, was based on data collected mainly in early 1989. Most of the data for 1989 were therefore provisional. The STATISTICAL UPDATE 1990 provides updated 1989 data collected in 1990 and provisional for 1990 [fr

Recovery of uranium from low-grade sandstone ores and phosphate rock

Energy Technology Data Exchange (ETDEWEB)

Kennedy, R H [United States Atomic Energy Commission, Washington, D. C. (United States)

1967-06-15

This paper is concerned principally with commercial-scale experience in the United States in the recovery of uranium from low-grade sources. Most of these operations have been conducted by the operators of uranium mills as an alternative to processing normal-grade ores. The operations have been generally limited, therefore, to the treatment of low-grade materials generated in the course of mining normal-grade ores. In some circumstances such materials can be treated by simplified procedures as an attractive source of additional production. The experience gained in uranium recovery from phosphate rock will be treated in some detail. The land pebble phosphate rock of central Florida generally contains about 0.01 to 0.02% U{sub 3}O{sub 8}. While no uranium is being recovered from this source at the present time, it does represent a significant potential source of by-product uranium production because of the large tonnages being mined. (author)

Uranium resources production and demand: a forty years evaluation 'Red book retrospective'

International Nuclear Information System (INIS)

2007-01-01

Uranium Resources, Production and Demand, also familiarly known as the ''Red Book'' is a biennial publication produced jointly by the NEA and the IAEA under the auspices of the joint NEA/IAEA Uranium Group. The first edition was published in 1965. The red book retrospective was undertaken to collect, analyse and publish all of the key information collected in the 20 editions of the Red Book published between 1965 and 2004. The red book gives a full historical profile of the world uranium industry in the areas of exploration, resources, reactor-related requirements, inventories and price. It provides in depth information relating to the histories of the major uranium producing countries. Thus for the first time a comprehensive look at annual and cumulative production and demand of uranium since the inception of the atomic age is possible. Expert analysis provide fresh insights into important aspects of the industry including the cost of discovery, resources to production ratios and the time to reach production after discovery. (A.L.B.)

Seismicity induced by mining operations in the surrounding of the uranium ore mine Schlema-Alberoda

International Nuclear Information System (INIS)

Wallner, Olaf; Hiller, Axel

2013-01-01

The uranium mine Schlema-Alberoda of the Wismut GmbH (Chemnitz, Federal Republic of Germany) is situated in the Westerzgebirge between the villages Aue, Schneeberg and Hartenstein. This 22 km 2 large area contains the villages Bad Schlema with the districts Oberschlema, Niederschlema and Wildbach as well as the district Alberode of the village Aue. The most important waters are the Zwickauer Mulde flowing through this territory from the south to the north. This territory can be designated as a densely populated low mountain range landscape being characterized by mining operations for centuries. Subsequently to the year 1945, the former Soviet 'Saxonian mining administration' started the first explorations on uranium ores inter alia in the area around Schneeberg and Schlema. In the year 1946, the intensive exploration and exploitation began in the health resort Oberschlema well-known by the existence of water containing radium. Up to the year 1959, the part deposit Oberschlema was dismantled. The dismantling ranged till to a depth of 750 m. With the expansion of the explorations in north-western direction, in 1948 the first uranium containing corridors of the part deposit Niederschlema-Alberoda was verified. The mining activities began in the year 1949 and culminated in the midst of the 1960ies with an annual production of more than 4,000 tons of uranium. The 1,800 m floor level as the deepest floor level was reached in the year 1986. A total of 49.5 million cubic meters of rocks was dissolved, and a total of 80,500 tons of uranium ores was mined. These were nearly 35% of the total production of the former Soviet-German public limited company Wismut (SDAG Wismut).

Uranium

International Nuclear Information System (INIS)

Anon.

1983-01-01

Recent decisions by the Australian Government will ensure a significant expansion of the uranium industry. Development at Roxby Downs may proceed and Ranger may fulfil two new contracts but the decision specifies that apart from Roxby Downs, no new mines should be approved. The ACTU maintains an anti-uranium policy but reaction to the decision from the trade union movement has been muted. The Australian Science and Technology Council (ASTEC) has been asked by the Government to conduct an inquiry into a number of issues relating to Australia's role in the nuclear fuel cycle. The inquiry will examine in particular Australia's nuclear safeguards arrangements and the adequacy of existing waste management technology. In two additional decisions the Government has dissociated itself from a study into the feasibility of establishing an enrichment operation and has abolished the Uranium Advisory Council. Although Australian reserves account for 20% of the total in the Western World, Australia accounts for a relatively minor proportion of the world's uranium production

World uranium exploration, resources, production and related activities

International Nuclear Information System (INIS)

Hanly, A.

2014-01-01

A Nuclear Energy Series publication entitled “World Uranium Exploration, Resources, Production and Related Activities” (WUERPRA) will soon be published by the IAEA. The objective of the publication is to provide a comprehensive compilation of historic uranium exploration, resources, production and related activities based primarily on information from the 1966 to 2009 editions of the publication “Uranium Resources, Production and Demand”, a joint publication of the International Atomic Energy Agency and the Nuclear Energy Agency/Organization for Economic Cooperation and Development commonly known as the ‘Red Book’. This has been supplemented by historic information from other reliable sources. The publications also include, where enough information was available, descriptions of the relative potential for discovery of new uranium resources on a per country basis. To recover complete historic information it is frequently necessary to refer to earlier editions of the Red Book, many of which may not be readily available. This publication aims to provide one comprehensive source for much of this type of information which will reduce the effort required to prepare future editions of the Red Book, as well as make the historic Red Book information, together with select related information from other sources, more readily available to all users with an interest in uranium. WUERPRA comprises 6 volumes containing 164 country reports, each organized by region; Volume 1: Africa (53 countries); Volume 2: Central, Eastern and Southeastern Europe (25 countries); Volume 3: Southeastern Asia, Pacific, East Asia (18 countries); Volume 4: Western Europe (22 countries); Volume 5: Middle East, Central and Southern Asia (19 countries), and; Volume 6: North America, Central America and South America (27 countries). The report also contains information on countries that have not reported to the Red Book. The poster will summarize select major highlights from each volume

The IAEA activities supporting implementation of best practice in uranium production cycle

International Nuclear Information System (INIS)

Slezak, J.

2010-01-01

'Full text:' Since the International Atomic Energy Agency's foundation in 1957, the Agency has had an increasing interest in uranium production cycle (UPC) developments. Recent activities cover tasks on uranium geology & deposits, exploration, mining & processing including environmental issues. The two projects titles are (1) Updating uranium resources, supply and demand and nuclear fuel cycle databases and (2) Supporting good practices in the UPC in particular for new countries. Based o the recent experience, one of the new activities is focused at human resources development to improve application of best practice called Uranium Production Cycle Network (UPNet). (author)

International symposium on uranium raw material for the nuclear fuel cycle: Exploration, mining, production, supply and demand, economics and environmental issues (URAM-2009). Book of abstracts

International Nuclear Information System (INIS)

2009-01-01

The International Symposium on Uranium Raw Material for the Nuclear Fuel Cycle: Exploration, Mining, Production, Supply and Demand, Economics and Environmental Issues (URAM-2009) addressed all aspects of the uranium fuel cycle, from the availability of raw materials to the long-term sustainability of nuclear power. The revival of the uranium industry in recent years has caused a dramatic increase in uranium exploration and mining activities in several countries. URAM-2009 was intended to bring together scientists, exploration and mining geologists, engineers, operators, regulators and fuel cycle specialists to exchange information and discuss updated research and current issues in uranium geology and deposits, exploration, mining and processing, production economics, and environmental and legal issues. Contributed papers covered uranium markets and economics (including supply and demand); social licensing in the uranium production cycle; uranium exploration (including uranium geology and deposits); uranium mining and processing; environmental and regulatory issues; human resources development. There was a poster session throughout the symposium, as well as an exhibition of topical photographs. A workshop on recent developments in Technical Cooperation Projects relevant to the Uranium Production Cycle area was also organized. On the last day of the symposium, there was an experts' Panel Discussion. The presentations and discussions at URAM-2009 (a) led to a better understanding of the adequacy of uranium sources (both primary and secondary) to meet future demand, (b) provided information on new exploration concepts, knowledge and technologies that will potentially lead to the discovery and development of new uranium resources, (c) described new production technology having the potential to more efficiently and economically exploit new uranium resources; (d) documented the environmental compatibility of uranium production and the overall effectiveness of the final

International Symposium on Uranium Raw Material for the Nuclear Fuel Cycle: Exploration, Mining, Production, Supply and Demand, Economics and Environmental Issues. Book of Abstracts

International Nuclear Information System (INIS)

2014-01-01

The long term sustainability of nuclear power will depend on, among several factors, an adequate supply of uranium resources that can be delivered to the marketplace at competitive prices. New exploration technologies and a better understanding of the genesis of uranium ores will be required to discover often deep-seated and increasingly hard to find uranium deposits. Exploration, mining and milling technologies should be environmentally benign, and site decommissioning plans should meet the requirements of increasingly stringent environmental regulations and societal expectations. The purpose of this symposium is to analyse uranium supply–demand scenarios and to present and discuss new developments in uranium geology, exploration, mining and processing, as well as in environmental requirements for uranium operations and site decommissioning. The presentations and discussions at URAM-2014 will: - Lead to a better understanding of the adequacy of uranium sources (both primary and secondary) to meet future demand; - Provide information on geological models, new exploration concepts, knowledge and technologies that will potentially lead to the discovery and development of new uranium resources; - Describe new production technologies that have the potential to more efficiently and sustainably develop new uranium resources; and - Document the environmental compatibility of uranium production and the overall effectiveness of progressive final decommissioning and, where required, remediation of production facilities.

Steps for preparing uranium production feasibility studies: A guidebook

International Nuclear Information System (INIS)

1996-06-01

Uranium exploration, development and eventual production, form a series of progressive and logical steps. Each step is part of a progression of activities with the objective of obtaining new or additional information from which a crucial decision is to be made. This guidebook is primarily aimed at mineral management personnel in developing countries who have little or no experience in preparing feasibility studies in uranium production. It is not a textbook which describes the geology, mining or processing of uranium. This guidebook deals with the philosophy, basic principles and important factors in the various stages of economic evaluation of the project. This guidebook is primarily concerned with small to medium sized mining projects. However, it can also provide useful guidance for the initial study of larger mining projects. More detailed studies of larger projects, however, should be left to well known experts in the field. While the mineral commodity in question is uranium, the procedures and approaches outlined in this guidebook are generally applicable to the study of other commodities. Refs, figs, tabs

The uranium industry of Bulgaria

International Nuclear Information System (INIS)

Pool, T.C.

1991-01-01

For 45 years, the Bulgarian uranium industry operated behind an impenetrable veil of secrecy. As this veil is slowly lifted, the breadth and structure of the industry are becoming apparent-and so are the problems. Bulgaria's uranium industry began in 1945 with the evaluation of several uranium mineral occurrences in the Balkan Mountains. These occurrences provided to be mineable deposits and became the foundation for a continuing program of exploration and development. Mining commenced in 1946, and all production was exported under contract to the Soviet Union in exchange for an eventual supply of fabricated nuclear fuel. In concert with most other countries of the COMECON block, Bulgaria's exploration and development program reached its zenith in the late 1960s and early 1970s. Like other COMECON countries, the contract with the Soviet Union was reduced during the 1980s and finally terminated. The Bulgarian uranium industry now is under substantial pressure to: (1) Maintain uranium production as a base of support for its 10,000 employees. (2) Develop mineral deposits other than uranium as a replacement for high-cost uranium production. (3) Clean up past and present production sites, most of which have significant environmental problems. The probability of successfully completing these three tasks without outside assistance is limited. Bulgaria's almost complete dependence for four and a half decades on Soviet aid, contracts, and technology has taken its toll

Method for the production of uranium chloride salt

Science.gov (United States)

Westphal, Brian R.; Mariani, Robert D.

2013-07-02

A method for the production of UCl.sub.3 salt without the use of hazardous chemicals or multiple apparatuses for synthesis and purification is provided. Uranium metal is combined in a reaction vessel with a metal chloride and a eutectic salt- and heated to a first temperature under vacuum conditions to promote reaction of the uranium metal with the metal chloride for the production of a UCl.sub.3 salt. After the reaction has run substantially to completion, the furnace is heated to a second temperature under vacuum conditions. The second temperature is sufficiently high to selectively vaporize the chloride salts and distill them into a condenser region.

Some design and operating aspects of the Ranger uranium mine treatment plant

International Nuclear Information System (INIS)

Baily, P.A.

1984-01-01

Environmental considerations were key factors in the design of the Ranger Uranium Mines treatment plant. The mine is located adjacent to the Kakadu National Park and has an average rainfall of 1.6m per annum. No contaminated water or liquid effluents are to be released from the project area and thus water management is a key design and operating fact. Particulate and gas emission criteria influenced design as did occupational hygiene factors (dust, radon, housekeeping, maintenance access). Equipment selection and engineering standards were conservative and resulted in the plant attaining design performance in less than three months from the date of commissioning. A number of mechanical and operational problems were experienced. However, none of these problems have had a significant effect on production

Production capability of the US uranium industry

International Nuclear Information System (INIS)

deVergie, P.C.; Anderson, J.R.; Miley, J.W.; Frederick, C.J.L.

1980-01-01

Demand for U 3 O 8 through the late 1990s could be met at the grades and costs represented by the $30 resources, although for the next 3 or 4 years, production will probably be from the lower cost portions of these resources if prices remain low. However, to meet currently projected uranium requirements beyond the year 2000, there will have to be a transition by the mid-1990s to higher cost and lower grade production in order to include supply from the additional increment of resources available between the $30 and $50 levels. Plans and financial commitments required to accomplish such a transition must be initiated y the mid-1980s, since lead times are increasing for exploration and for mill licensing and construction. Engineering planning and feasibility analyses would have to be carried out under a more advanced time frame than previously required. The importance of the potential resources can easily be seen. In meeting the high-case demand during the years 2005 through 2019 more than 50% of the production would be from resources assigned to the $50 probable potential resource category. By about the year 2006, there will have had to be considerable development of the possible, and perhaps, some of the speculative resources to assure continued production expansion; by 2020, more than 50% of the production would depend on the previous successes in finding and developing such resources. The continuation of the current trend in production curtailment and decreasing exploration will significantly lessen the domestic uranium industry's ability to respond quickly to the projected increases in uranium requirements. The industry's future will be unsettled until it preceives clear indications of demand and price incentives that will justify long-term capital investments

Natural uranium metallic fuel elements: fabrication and operating experience

International Nuclear Information System (INIS)

Hammad, F.H.; Abou-Zahra, A.A.; Sharkawy, S.W.

1980-01-01

The main reactor types based on natural uranium metallic fuel element, particularly the early types, are reviewed in this report. The reactor types are: graphite moderated air cooled, graphite moderated gas cooled and heavy water moderated reactors. The design features, fabrication technology of these reactor fuel elements and the operating experience gained during reactor operation are described and discussed. The interrelation between operating experience, fuel design and fabrication was also discussed with emphasis on improving fuel performance. (author)

The uranium market: 1986-2000

International Nuclear Information System (INIS)

Lewiner, C.; Walton, D.; Sinclair-Smith, D.

1987-01-01

This paper summarizes the main conclusions of the 1986 supply and demand report of the Uranium Institute. The probable nuclear generating capacity is estimated for 1986-2000. Previous capacity forecasts (1981-1986) are compared with actual generating capacity. When looking at demand, a distinction has to be made between what reactor operators require to fuel reactors (reactor requirements) and what they intend to purchase (uranium procurements). This distinction is defined and discussed. The interaction between supply and demand is shown and factors affecting trade (eg government policies) are discussed. 1985 was the first year when uranium production was less than reactor requirements. This shortfall will continue for a number of years with the current excess in consumer inventories supplying the difference between reactor requirements and uranium procurements. Uranium demand should exceed production by 1988 but additional capacity should be available from planned and possible restart and possible new facilities. (U.K.)

Uranium Resources, production and demand

International Nuclear Information System (INIS)

1988-01-01

Periodic assessments of world uranium supply and demand have been conducted by the OECD Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA) since the mid 1960s. Published every two years, the report URANIUM RESOURCES, PRODUCTION AND DEMAND, commonly referred to as the RED BOOK, has become an essential reference document for nuclear planners and policy makers in the international nuclear community. The latest Red Book, published in 1988, was based on data collected mainly in early 1987. Most of the data for 1987 were therefore provisional. The STATISTICAL UPDATE 1988 provides updated 1987 data collected in 1988 and provisional data for 1988. The publication, which covers OECD Countries and gives Secretariat estimates for the rest of the World Outside Centrally Planned Economies (WOCA), is being issued every second year, between publications of more complete Red Books

Uranium, resources, production and demand

International Nuclear Information System (INIS)

1986-01-01

Periodic assessments of world uranium supply have been conducted by the OECD Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA) since the mid 1960s. Published every two years, the report Uranium resources, production and demand, commonly referred to as the red book, has become an essential reference document for nuclear planners and policy makers in the international nuclear community. The latest red book, published in 1986, was based on data collected mainly in early 1985. Most of the data for 1985 were therefore provisional. The statistical update 1986 provides updated 1985 data collected in 1986 and provisional data for 1986. This is the first time such an annual update of key Red Book statistical data has been prepared. This year it covers only OECD countries with a secretariat estimate for the rest of Woca

Conversion and Blending Facility highly enriched uranium to low enriched uranium as metal. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-05

The mission of this Conversion and Blending Facility (CBF) will be to blend surplus HEU metal and alloy with depleted uranium metal to produce an LEU product. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The blended LEU will be produced as a waste suitable for storage or disposal.

Conversion and Blending Facility highly enriched uranium to low enriched uranium as metal. Revision 1

International Nuclear Information System (INIS)

1995-01-01

The mission of this Conversion and Blending Facility (CBF) will be to blend surplus HEU metal and alloy with depleted uranium metal to produce an LEU product. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The blended LEU will be produced as a waste suitable for storage or disposal

Review of environmental aspects of uranium mill operations: industry's view

International Nuclear Information System (INIS)

Beverly, R.G.

1977-01-01

Problems faced by uranium mill operators in complying with new environmental regulations and guidelines are discussed. It is pointed out that valid data must be available in order to evaluate impacts on the environment, to determine background radiation levels, to measure the effectiveness of control techniques, and to determine compliance with standards and regulations. Specific problem areas facing mill operators today and some of the unresolved questions include: sampling methods and equipment for radon in ambient air, measurements of radon and radon daughter exposures of people, radon emanation rate meaurements applicable to monitoring mill tailings, the calibration of γ counters, measurements of population doses, regulations concerning mill tailings reclamation nd stabilization, and the comparative value of in-vivo counting and uranium urinary excretion measurements for monitoring personnel

Uranium production and environmental restoration at the Priargunsky Centre, Russian Federation

International Nuclear Information System (INIS)

Boitsov, A.V.; Nikolsky, A.L.; Chernigov, V.G.; Ovseichuk, V.A.

2002-01-01

State JSK 'Priargunsky Mining-Chemical Production Association' (PPGHO) has been the only active uranium production centre in Russia during the last decade. Mining has operated since 1968, and derives from resources in 19 volcanic-type deposits of Streltsovsk U-ore region, which covers an area of 150 km 2 . The average U grade is about 0.2%. Ten deposits have been brought into production: eight by underground mines and two by open pits. Milling and processing has been carried out since 1974 at the local hydrometallurgical plant by sulphuric acid leaching with subsequent recovery by a sorption-extraction ion exchange scheme. The high level of total production (over 100,000 mtU through 2000) marks it as one of the outstanding uranium production districts worldwide. Significant amounts of wastes have been accumulated. The main sources of the environmental contamination are: 30 piles of waste rocks and sub-grade ores, mine waters, milling and sulphuric acid plant tailings. The following activities are performed to decrease the negative impact on the environment: rehabilitation of waste rock dumps and open pits utilization of waste rock for industrial needs, heap and in situ leach mining of low-grade ores, construction of dams and intercepting wells below the tailings, hydrogeological monitoring and waste water treatment plant modernization. Environmental activities, including rehabilitation of the impacted territories and also waste utilization will be realized after final closure takes place. (author)

Determination of uranium and plutonium in metal conversion products from electrolytic reduction process

International Nuclear Information System (INIS)

Lee, Chang Heon; Suh, Moo Yul; Joe, Kih Soo; Sohn, Se Chul; Jee, Kwang Young; Kim, Won Ho

2005-01-01

Chemical characterization of process materials is required for the optimization of an electrolytic reduction process in which uranium dioxide, a matrix of spent PWR fuels, is electrolytically reduced to uranium metal in a medium of LiCl-Li 2 O molten at 650 .deg. C. A study on the determination of fissile materials in the uranium metal products containing corrosion products, fission products and residual process materials has been performed by controlled-potential coulometric titration which is well known in the field of nuclear science and technology. Interference of Fe, Ni, Cr and Mg (corrosion products), Nd (fission product) and LiCl molten salt (residual process material) on the determination of uranium and plutonium, and the necessity of plutonium separation prior to the titration are discussed in detail. Under the analytical condition established already, their recovery yields are evaluated along with analytical reliability

Study of reactions for the production of uranium titrafluoride and uranium hexafluoride

International Nuclear Information System (INIS)

Guzella, M.F.R.

1985-01-01

The main production processes of uranium hexafluoride in pilot plants and industrial facilities are described. The known reactions confirmed in laboratory experiments that lead to Uf 6 or other intermediate fluorides are discussed. For the purpose of determining a thermodinamically feasible reaction involving the sulfur hexafluoride as fluorinating agent, a mock-up facility was designed and constructed as a part of the R and D work planned at the CDTN (Nuclebras Center for Nuclear Technology Development). IN the uranium tatrafluoride synthesis employing U 3 O 8 and SF 6 several experimental parameters are studied. The reaction time, gasflow, temperature and stoechiometic relations among reagents are described in detail. (Author) [pt

Role of modern analytical techniques in the production of uranium metal

International Nuclear Information System (INIS)

Hareendran, K.N.; Roy, S.B.

2009-01-01

Production of nuclear grade uranium metal conforming to its stringent specification with respect to metallic and non metallic impurities necessitates implementation of a comprehensive quality control regime. Founding members of Uranium Metal Plant realised the importance of this aspect of metal production and a quality control laboratory was set up as part of the production plant. In the initial stages of its existence, the laboratory mainly catered to the process control analysis of the plant process samples and Spectroscopy Division and Analytical Division of BARC provided analysis of trace metallic impurities in the intermediates as well as in the product uranium metal. This laboratory also provided invaluable R and D support for the optimization of the process involving both calciothermy and magnesiothermy. Prior to 1985, analytical procedures used were limited to classical methods of analysis with minimal instrumental procedures. The first major analytical instrument, a Flame AAS was installed in 1985 and a beginning to the trace analysis was made. However during the last 15 years the Quality Control Section has modernized the analytical set up by acquiring appropriate instruments. Presently the facility has implemented a complete quality control and quality assurance program required to cover all aspects of uranium metal production viz analysis of raw materials, process samples, waste disposal samples and also determination of all the specification elements in uranium metal. The current analytical practices followed in QCS are presented here

Obtaining of uranium tetrafluoride UF4 by electrodialysis reactive from uranium concentrates

International Nuclear Information System (INIS)

Munoz Lay, Danny Mauricio

2014-01-01

The generation of uranium fuels has always been a topic worldwide. The uranium fuel manufacturing base is made under very strict parameters of radiological and industrial safety, being a stage called 'nuclear fuel cycle'. In Chile, it is done constant research for fuels. This report focuses primarily on participating in such research; mainly in the production of uranium tetrafluoride (UF 4 ) .The tetrafluoride production is very crucial for the nuclear fuel industry. Its production varies from precipitation in stirred conditions to electrolysis in mercury. However, both processes has shortcomings either in performance and environmental pollution, which is why it is proposed a new method of production based on a friendly process to the environment and easier to operate, the reactive electrodialysis (RED). Electrodialysis is a hybrid reactive process of separation by membranes, cationic and / or anionic, namely, ionic species. In the process, ions are induced to move by an electric potential applied and separated by these membranes, a highly selective physical barrier which allows passage of ions with certain charge, and prevents the passage of oppositely charged ions. And in turn, it is reactive because it forces a chemical reaction, redox, to obtain uranium tetrafluoride (UF 4 ). The results of these experiments show that by reactive electrodialysis, NH 4 UF 5 deposits were obtained. However, calcinating the NH 4 UF 5 to 450 o C, it decomposes to obtain uranium tetrafluoride, UF 4 . The best working conditions were obtained with an electric current of 0.5 (A), 41 o C and a flow of 16 (ml / s) of the electrolyte. It was possible to obtain 5,995 (g) to 3 (h), giving a current efficiency of 71.42%. In turn, working at high temperatures and flow recirculation is possible to operate with a potential difference of 1.7 (V)

Uranium recovering from slags generated in the metallic uranium by magnesiothermic reduction

International Nuclear Information System (INIS)

Fornarolo, F.; Carvalho, E.F. Urano de; Durazzo, M.; Riella, H.G.

2008-01-01

The Nuclear Fuel Center of IPEN/CNEN-SP has recent/y concluded a program for developing the fabrication technology of the nuclear fuel based on the U 3 Si 2 -Al dispersion, which is being used in the IEA-R1 research reactor. The uranium silicide (U 3 Si 2 ) fuel production starts with the uranium hexafluoride (UF 6 ) processing and uranium tetrafluoride (UF 4 ) precipitation. Then, the UF 4 is converted to metallic uranium by magnesiothermic reduction. The UF 4 reduction by magnesium generates MgF 2 slag containing considerable concentrations of uranium, which could reach 20 wt%. The uranium contained in that slag should be recovered and this work presents the results obtained in recovering the uranium from that slag. The uranium recovery is accomplished by acidic leaching of the calcined slag. The calcination transforms the metallic uranium in U 3 O 8 , promoting the pulverization of the pieces of metallic uranium and facilitating the leaching operation. As process variables, have been considered the nitric molar concentration, the acid excess regarding the stoichiometry and the leaching temperature. As result, the uranium recovery reached a 96% yield. (author)

The potential of centrifugal casting for the production of near net shape uranium parts

International Nuclear Information System (INIS)

Robertson, E.

1993-09-01

This report was written to provide a detailed summary of a literature survey on the near net shape casting process of centrifugal casting. Centrifugal casting is one potential casting method which could satisfy the requirements of the LANL program titled Near Net Shape Casting of Uranium for Reduced Environmental, Safety and Health Impact. In this report, centrifugal casting techniques are reviewed and an assessment of the ability to achieve the near net shape and waste minimization goals of the LANL program by using these techniques is made. Based upon the literature reviewed, it is concluded that if properly modified for operation within a vacuum, vertical or horizontal centrifugation could be used to safely cast uranium for the production of hollow, cylindrical parts. However, for the production of components of geometries other than hollow tubes, vertical centrifugation could be combined with other casting methods such as semi-permanent mold or investment casting

MILDOS - a computer program for calculating environmental radiation doses from uranium recovery operations. Research report

International Nuclear Information System (INIS)

Strenge, D.L.; Bander, T.J.

1981-04-01

MILDOS is a Fortran Computer Code which calculates the dose commitments received by individuals and the general population within an 80 kilometer radius of an operating uranium recovery facility. In addition air and ground concentrations are presented for individual locations, as well as for a generalized population grid. Extra-regional population doses resulting from transport of radon and export of agricultural produce are also displayed. The transport of radiological emissions from point and area sources is predicted by using a sector-averaged Gaussian plume dispersion model. Mechanisms such as radioactive decay, plume depletion by deposition, ingrowth of daughter products and resuspension of deposited radionuclides are included in the transport model. Alterations in operation throughout the facility's lifetime can be accounted for in the input stream. The pathways considered are: inhalation; external exposure from ground shine and cloud immersion; and ingestion of vegetables, meat and milk. Dose commitments are calculated primarily on the basis of the recommendations of the International Commission on Radiological Protection (ICRP). Predictive 40 CFR 190 and 10 CFR 20 compliances are also performed. This computer code is designed primarily for uranium milling facilities and should not be used for operations with different radionuclides or processes

Method for converting uranium oxides to uranium metal

International Nuclear Information System (INIS)

Duerksen, W.K.

1988-01-01

A method for converting uranium oxide to uranium metal is described comprising the steps of heating uranium oxide in the presence of a reducing agent to a temperature sufficient to reduce the uranium oxide to uranium metal and form a heterogeneous mixture of a uranium metal product and oxide by-products, heating the mixture in a hydrogen atmosphere at a temperature sufficient to convert uranium metal in the mixture to uranium hydride, cooling the resulting uranium hydride-containing mixture to a temperature sufficient to produce a ferromagnetic transition in the uranium hydride, magnetically separating the cooled uranium hydride from the mixture, and thereafter heating the separated uranium hydride in an inert atmosphere to a temperature sufficient to convert the uranium hydride to uranium metal

Dissolution testing of intermediary products in uranium dioxide production by the sol-gel method

International Nuclear Information System (INIS)

Melichar, F.; Landspersky, H.; Urbanek, V.

1979-01-01

A method was developed of dissolving polyuranates and uranium dioxides in sulphuric acid and in carbonate solutions for testing intermediate products in the sol-gel process preparation of uranium dioxide. A detailed granulometric analysis of spherical particle dispersion was included as part of the tests. Two different production methods were used for the two types of studied materials. The test results show that the test method is suitable for determining temperature sensitivity of the materials to dissolution reaction. The geometrical distribution of impurities in the spherical particles can be determined from the dissolution kinetics. The method allows the determination of the effect of carbon from impurities on the process of uranium dioxide leaching and is thus applicable for testing materials prepared by the sol-gel method. (Z.M.)

Production of sized particles of uranium oxides and uranium oxyfluorides

International Nuclear Information System (INIS)

Knudsen, I.E.; Randall, C.C.

1976-01-01

A process is claimed for converting uranium hexafluoride (UF 6 ) to uranium dioxide (UO 2 ) of a relatively large particle size in a fluidized bed reactor by mixing uranium hexafluoride with a mixture of steam and hydrogen and by preliminary reacting in an ejector gaseous uranium hexafluoride with steam and hydrogen to form a mixture of uranium and oxide and uranium oxyfluoride seed particles of varying sizes, separating the larger particles from the smaller particles in a cyclone separator, recycling the smaller seed particles through the ejector to increase their size, and introducing the larger seed particles from the cyclone separator into a fluidized bed reactor where the seed particles serve as nuclei on which coarser particles of uranium dioxide are formed. 9 claims, 2 drawing figures

The last twenty years of the IAEA technical cooperation on the uranium production cycle in Argentina

International Nuclear Information System (INIS)

Lopez, L.

2014-01-01

Since 1993, the National Atomic Energy Commission (Argentina) has been involved in several IAEA Technical Cooperation Projects at interregional, regional and national levels, covering different aspects of the uranium production cycle. The TC referred projects can be listed as follows: - INT 2/015 “Supporting Uranium Exploration Resource Augmentation and Production Using Advanced Techniques” (2012 – Present). - RLA 3/006 - 010 “Upgrading of Uranium Exploration, Exploitation and Yellowcake Production Techniques taking Environmental Problems into Account” (2007 - Present). - ARG 2/014 “Development and Strengthening of the Uranium Mining Cycle Human Resources” (2012 – Present). - ARG 3/012 - 014 "Geology favourability, production feasibility and environmental impact assessment of uranium deposits exploitable by the in situ leaching technology (ISL)'' (2007 - Present). - ARG 3/009 “Development and use of biological techniques for uranium production (ARG 3/009)” (2003 - 2006). - ARG 3/008 “Prospection of uranium and other elements using gamma-ray spectrometry surveys” (2001 – 2005). - ARG 3/007 “Uranium Favorability and Exploration in Argentina” (1993 - 1997). It can be considered that the role of the technological transfer by the IAEA has been highly relevant for increasing the capability of strategically plan and more efficiently carry out the uranium production cycle projects in Argentina. (author)

Status Report from Canada [Processing of Low-Grade Uranium Ores

Energy Technology Data Exchange (ETDEWEB)

Thunaes, A [Eldorado Mining and Refining Ltd., Ottawa (Canada)

1967-06-15

The Canadian production of uranium increased in a spectacular manner during the period 1955-1959 from 1000 to 15 500 tons U{sub 3}O{sub 8} per year. Since 1959 the production has declined to the 1966 level of 3900 tons U{sub 3}O{sub 8} per year; stretch-out of contracts and government stockpiling programmes has made the decline gradual, and is maintaining the current rate of production until 1970. Nineteen mills were in operation during the period of peak production but only three are operating today. Ten mills were shut down and dismantled because of exhaustion of ore bodies or because the operation was uneconomical; six mills are maintained in stand-by condition. The total daily capacity of mills in operation or standing by is about 28 000 tons ore, but some of these mills would not be reopened unless an appreciable increase in uranium price occurs. The tide of uranium demand is about ready to turn and prospecting for uranium is very active this year, particularly in the Elliot Lake and Beaverlodge areas. The estimates for uranium demand in 1975-1980 are such that new ore will have to be found and developed, and new treatment plants must be built. The new ore that is found will likely be of lower grade or more expensive to mine than most of the current proven reserves in Canada and the most efficient methods of treatment will be needed to avoid excessive increases in production costs. This seems an opportune time to review Canadian milling of uranium ore, the improvements that have been made and development work towards further improvements.

Uranium in Canada

International Nuclear Information System (INIS)

1987-09-01

Canadian uranium exploration and development efforts in 1985 and 1986 resulted in a significant increase in estimates of measured uranium resources. New discoveries have more than made up for production during 1985 and 1986, and for the elimination of some resources from the overall estimates, due to the sustained upward pressure on production costs and the stagnation of uranium prices in real terms. Canada possesses a large portion of the world's uranium resources that are of current economic interest and remains the major focus of inter-national uranium exploration activity. Expenditures for uranium exploration in Canada in 1985 and 1986 were $32 million and $33 million, respectively. Although much lower than the $130 million total reported for 1979, expenditures for 1987 are forecast to increase. Exploration and surface development drilling in 1985 and 1986 were reported to be 183 000 m and 165σ2 000 m, respectively, 85 per cent of which was in Saskatchewan. Canada has maintained its position as the world's leading producer and exporter of uranium. By the year 2000, Canada's annual uranium requirements will be about 2 100 tU. Canada's known uranium resources are more than sufficient to meet the 30-year fuel requirements of those reactors in Canada that are either in operation now or expected to be in service by the late 1990s. A substantial portion of Canada's identified uranium resources is thus surplus to Canadian needs and available for export. Annual sales currently approach $1 billion, of which exports account for 85 per cent. Forward domestic and export contract commitments totalled 73 000 tU and 62 000 tU, respectively, as of early 1987

78 FR 17450 - Notice of Issuance of Materials License Renewal, Operating License SUA-1341, Uranium One USA, Inc...

Science.gov (United States)

2013-03-21

... License Renewal, Operating License SUA-1341, Uranium One USA, Inc., Willow Creek Uranium In Situ Recovery.... SUA- 1341 to Uranium One USA, Inc. (Uranium One) for its Willow Creek Uranium In Situ Recovery (ISR... Commission License No. SUA-1341 For Uranium One USA, Inc., Irigaray and Christensen Ranch Projects (Willow...

DEVELOPMENT OF HIGH-DENSITY U/AL DISPERSION PLATES FOR MO-99 PRODUCTION USING ATOMIZED URANIUM POWDER

OpenAIRE

RYU, HO JIN; KIM, CHANG KYU; SIM, MOONSOO; PARK, JONG MAN; LEE, JONG HYUN

2013-01-01

Uranium metal particle dispersion plates have been proposed as targets for Molybdenum-99 (Mo-99) production to improve the radioisotope production efficiency of conventional low enriched uranium targets. In this study, uranium powder was produced by centrifugal atomization, and miniature target plates containing uranium particles in an aluminum matrix with uranium densities up to 9 g-U/cm3 were fabricated. Additional heat treatment was applied to convert the uranium particles into UAlx compou...

Characteristics of uranium districts of the Russian Federation

International Nuclear Information System (INIS)

Boitsov, A.V.; Nikolsky, A.L.

2001-01-01

Uranium deposits are discovered in 15 ore districts of the Russian Federation. They are subdivided into four groups: Streltsovsky district with existing production centre, Stavropolsky district with depleted deposits, three prospective districts and ten reserve districts. The overview of new data on these districts is presented. Streltsovsky district with Priargunsky Production Centre include 19 molybdenum-uranium deposits of structure-bound volcanic type in caldera. The main activities in Stavropolsky district with two depleted uranium deposits are connected with restoration works and wastes rehabilitation. Except Streltsovsky district there are no more deposits in the Russian Federation prepared for uranium production. At the same time some uranium deposits of Vitimsky, Zauralsky, and West-Siberian districts are prospective for new development of production centres. They belong to the sandstone type, related to paleovalley or basal channel, and are suitable for ISL operation. The deposits of the other districts are considered to be reserve and considered unprofitable for uranium production at present and in the nearest future. The biggest of them is Aldansky district with gold-uranium deposits in potassium metasomatites in areas of Mesozoic activation of Archean cratons. Central Transbaikalsky, Yeniseisky, Yergeninsky, Onezhsky, Ladozhsky, Bureinsky, Khankaisky, Volgo-Uralsky reserve districts include mainly small-size deposits of vein, volcanic, surficial and metasomatite types with low uranium grades. (author)

The uranium recovery from UO{sub 2} kernel production effluent

Energy Technology Data Exchange (ETDEWEB)

Chen, Xiaotong, E-mail: chenxiaotong@tsinghua.edu.cn; He, Linfeng; Liu, Bing; Tang, Yaping; Tang, Chunhe

2016-12-15

Graphical abstract: In this study, a flow sheet including evaporation, flocculation, filtration, adsorption, and reverse osmosis was established for the UO{sub 2} kernel production effluent of HTR spherical fuel elements. The uranium recovery could reach 99.9% after the treatment, with almost no secondary pollution produced. Based on the above experimental results, the treating flow process in this study would be feasible for laboratory- and engineering-scale treatment of UO{sub 2} kernel production effluent of HTR spherical fuel elements. - Highlights: • A flow sheet including evaporation, flocculation, filtration, adsorption, and reverse osmosis was established for the UO{sub 2} kernel production effluent. • The uranium recovery could reach 99.9% after the treatment, with almost no secondary pollution produced. • The treating flow process would be feasible for laboratory- and engineering-scale treatment of UO{sub 2} kernel production effluent. - Abstract: For the fabrication of coated particle fuel elements of high temperature gas cooled reactors, the ceramic UO{sub 2} kernels are prepared through chemical gelation of uranyl nitrate solution droplets, which produces radioactive effluent with components of ammonia, uranium, organic compounds and ammonium nitrate. In this study, a flow sheet including evaporation, flocculation, filtration, adsorption, and reverse osmosis was established for the effluent treating. The uranium recovery could reach 99.9% after the treatment, with almost no secondary pollution produced.

Uranium production in thorium/denatured uranium fueled PWRs

International Nuclear Information System (INIS)

Arthur, W.B.

1977-01-01

Uranium-232 buildup in a thorium/denatured uranium fueled pressurized water reactor, PWR(Th), was studied using a modified version of the spectrum-dependent zero dimensional depletion code, LEOPARD. The generic Combustion Engineering System 80 reactor design was selected as the reactor model for the calculations. Reactors fueled with either enriched natural uranium and self-generated recycled uranium or uranium from a thorium breeder and self-generated recycled uranium were considered. For enriched natural uranium, concentrations of 232 U varied from about 135 ppM ( 232 U/U weight basis) in the zeroth generation to about 260 ppM ( 232 U/U weight basis) at the end of the fifth generation. For the case in which thorium breeder fuel (with its relatively high 232 U concentration) was used as reactor makeup fuel, concentrations of 232 U varied from 441 ppM ( 232 U/U weight basis) at discharge from the first generation to about 512 ppM ( 232 U/U weight basis) at the end of the fifth generation. Concentrations in freshly fabricated fuel for this later case were 20 to 35% higher than the discharge concentration. These concentrations are low when compared to those of other thorium fueled reactor types (HTGR and MSBR) because of the relatively high 238 U concentration added to the fuel as a denaturant. Excellent agreement was found between calculated and existing experimental values. Nevertheless, caution is urged in the use of these values because experimental results are very limited, and the relevant nuclear data, especially for 231 Pa and 232 U, are not of high quality

Uranium conversion

International Nuclear Information System (INIS)

Oliver, Lena; Peterson, Jenny; Wilhelmsen, Katarina

2006-03-01

FOI, has performed a study on uranium conversion processes that are of importance in the production of different uranium compounds in the nuclear industry. The same conversion processes are of interest both when production of nuclear fuel and production of fissile material for nuclear weapons are considered. Countries that have nuclear weapons ambitions, with the intention to produce highly enriched uranium for weapons purposes, need some degree of uranium conversion capability depending on the uranium feed material available. This report describes the processes that are needed from uranium mining and milling to the different conversion processes for converting uranium ore concentrate to uranium hexafluoride. Uranium hexafluoride is the uranium compound used in most enrichment facilities. The processes needed to produce uranium dioxide for use in nuclear fuel and the processes needed to convert different uranium compounds to uranium metal - the form of uranium that is used in a nuclear weapon - are also presented. The production of uranium ore concentrate from uranium ore is included since uranium ore concentrate is the feed material required for a uranium conversion facility. Both the chemistry and principles or the different uranium conversion processes and the equipment needed in the processes are described. Since most of the equipment that is used in a uranium conversion facility is similar to that used in conventional chemical industry, it is difficult to determine if certain equipment is considered for uranium conversion or not. However, the chemical conversion processes where UF 6 and UF 4 are present require equipment that is made of corrosion resistant material

RIB production with photofission of uranium

Energy Technology Data Exchange (ETDEWEB)

Oganessian, Yu.Ts. E-mail: oganessian@flnr.jinr.ru; Dmitriev, S.N.; Kliman, J.; Maslov, O.A.; Starodub, G.Ya.; Belov, A.G.; Tretiakova, S.P

2002-04-22

The process of uranium photofission with electron beams of 20-50 MeV is considered in terms of the production of fission fragments. It is shown that in the interaction between an electron beam (25 MeV in energy and 20 {mu}A in intensity), produced by a compact accelerator of the microtron type, and a uranium target of about 40 g/cm{sup 2} in thickness, an average of 1.5x10{sup 11} fission events per second is generated. According to the calculations and test experiments, this corresponds to the yield of {sup 132}Sn and {sup 142}Xe isotopes of approximately 2x10{sup 9}/s. The results of experiments on the optimal design of the U-target are presented. Problems are discussed connected with the separation of isotopes and isobars for their further acceleration up to energies of 5-18 MeV A. The photofission reactions of a heavy nucleus are compared with other methods of RIB production of medium mass nuclei.

Uranium mining impacts on water resources in Brazil

International Nuclear Information System (INIS)

Simoes Filho, Francisco Fernando Lamego; Lauria, Dejanira C.; Vasconcellos, Luisa M.H.; Fernandes, Horst M.; Clain, Almir F.; Silva, Liliane F.

2009-01-01

Uranium mining and milling activities started operations in Brazil during the 80's. The first production Center was deployed in Pocos de Caldas (CIPC) State of Minas Gerais. The mine was exhausted in 1997, after has produced only 1200 t of U 3 O 8 . The second uranium plant began the operations in Caetite (URA), Bahia State, since 1999 and keeps operations until now with an annual U 3 O 8 production of up to 400 t. The company plans to double this mark in Caetite production center with the exploration of another uranium deposits and initiate underground operations of current open-pit mine. Simultaneously, they are seeking a license for a third plant in the State of Ceara that could produce the double of foreseen capacity in URA. This scenery drives to some issues related to the impact of uranium production on water resources of the respective watersheds. The CIPC plant is a closing mine site, which requires permanent treatment of the company due to the fact their sources of pollutants are subject to the occurrence of Acid Mine Drainage. The URA plant is located in a semi-arid region of Brazil. The extraction of uranium from the ore is achieved by means of a Heap-Leach process, which has low water demand supplied by a network of wells and from a dam, but can contribute to change the groundwater quality and in some cases the extinguishing of wells was observed. An overall assessment of these impacts in national level could produce some lessons that we must take advantage for the ongoing project of Santa Quiteria or even in future sites. (author)

Environmental monitoring program design for uranium refining and conversion operations

International Nuclear Information System (INIS)

1984-08-01

The objective of this study was to develop recommendations for the design of environmental monitoring programs at Canadian uranium refining and conversion operations. In order to develop monitoring priorities, chemical and radioactive releases to the air and water were developed for reference uranium refining and conversion facilities. The relative significance of the radioactive releases was evaluated through a pathways analysis which estimated dose to individual members of the critical receptor group. The effects of chemical releases to the environment were assessed by comparing predicted air and water contaminant levels to appropriate standards or guidelines. For the reference facilities studied, the analysis suggested that environmental effects are likely to be dominated by airborne release of both radioactive and nonradioactive contaminants. Uranium was found to be the most important radioactive species released to the air and can serve as an overall indicator of radiological impacts for any of the plants considered. The most important nonradioactive air emission was found to be fluoride (as hydrogen fluoride) from the uranium hexafluoride plant. For the uranium trioxide and uranium dioxide plants, air emissions of oxides of nitrogen were considered to be most important. The study recommendations for the design of an environmental monitoring program are based on consideration of those factors most likely to affect local air and water quality, and human radiation exposure. Site- and facility-specific factors will affect monitoring program design and the selection of components such as sampling media, locations and frequency, and analytical methods

Study on environmental impact assessment index system of uranium production base construction plan

International Nuclear Information System (INIS)

Liu Xiaochao; Song Liquan

2008-01-01

The index system on planning environmental impact assessment of uranium mining base construction is discussed by using the hiberarchy method according to characteristics of uranium production and environmental protection object of planning assessment. The suggested index system is in favor of persistent exploitation of uranium resource and environmental protection in the uranium mining area, and can provide a reference for planning environmental impact assessment of uranium mining base construction in China. (authors)

Product Stewardship in Uranium: A Way for the Industry to Demonstrate its High Performance

International Nuclear Information System (INIS)

Harris, Frank

2014-01-01

Conclusions: • Product stewardship is an means for communicating the high performance on health, safety and environment of the nuclear fuel cycle including uranium mining. • It has been effective with other products and is appropriate for uranium. • Can be a vehicle for addressing public concerns across the industry. • Due to uranium’s unique characteristics it has the potential to be a best practice example of product stewardship. • Work is underway in the international arena to progress uranium product stewardship and it represent a unique opportunity to provide whole of industry benefits

Machining of uranium and uranium alloys

International Nuclear Information System (INIS)

Morris, T.O.

1981-01-01

Uranium and uranium alloys can be readily machined by conventional methods in the standard machine shop when proper safety and operating techniques are used. Material properties that affect machining processes and recommended machining parameters are discussed. Safety procedures and precautions necessary in machining uranium and uranium alloys are also covered. 30 figures

Uranium, resources, production and demand including other nuclear fuel cycle data

International Nuclear Information System (INIS)

1975-12-01

The uranium reserves exploitable at a cost below 15 dollars/lb U 3 O 8 , are 210,000 tonnes. While present uranium production capacities amount to 26,000 tonnes uranium per year, plans have been announced which would increase this capacity to 44,000 tonnes by 1978. Given an appropriate economic climate, annual capacities of 60,000 tonnes and 87,000 tonnes could be attained by 1980 and 1985, respectively, based on presently known reserves. However, in order to maintain or increase such a capacity beyond 1985, substantial additional resources would have to be identified. Present annual demand for natural uranium amounts to 18,000 tonnes and is expected to establish itself at 50,000 tonnes by 1980 and double this figure by 1985. Influences to increase this demand in the medium term could come from shortages in other fuel cycle capacities, i.e. enrichment (higher tails assays) and reprocessing (no uranium and plutonium recycle). However, the analysis of the near term uranium supply and demand situation does not necessarily indicate a prolongation of the current tight uranium market. Concerning the longer term, the experts believe that the steep increase in uranium demand foreseen in the eighties, according to present reactor programmes, with doubling times of the order of 6 to 7 years, will pose formidable problems for the uranium industry. For example, in order to provide reserves sufficient to support the required production rates, annual additions to reserves must almost triple within the next 15 years. Efforts to expand world-wide exploration levels to meet this challenge would be facilitated if a co-ordinated approach were adopted by the nuclear industry as a whole

Recovery of valuable products from the raffinate of uranium and thorium pilot-plant

International Nuclear Information System (INIS)

Martins, E.A.J.

1990-01-01

IPEN-CNEN/SP has being very active in refining yellow cake to pure ammonium diuranate which is converted to uranium trioxide, uranium dioxide, uranium tetra-and hexa-fluoride in sequential way. The technology of the thorium purification and its conversion to nuclear grade products has been a practice since several years as well. For both elements the major waste to be worked is the raffinate from purification via TBP-varsol in pulsed columns. In this paper the actual processing technology is reviewed with special emphasis on the recovery of valuable products, mainly nitric acid, ammonium nitrate, uranium, thorium and rare earth elements. Ammonium nitrate from the precipitation of uranium diuranate is of good quality, being radioactivity and uranium-free, and recommended to be applied as fertilizer. In conclusion the main effort is to maximize the recycle and reuse of the above mentioned chemicals. (author)

Ontario's uranium mining industry

International Nuclear Information System (INIS)

Runnalls, O.J.C.

1981-01-01

This report traces the Ontario uranium mining industry from the first discovery of uranium north of Sault Ste. Marie through the uranium boom of the 1950's when Elliot Lake and Bancroft were developed, the cutbacks of the 1960s, the renewed enthusiasm in exploration and development of the 1970s to the current position when continued production for the domestic market is assured. Ontario, with developed mines and operational expertise, will be in a position to compete for export markets as they reopen. The low level of expenditures for uranium exploration and the lack of new discoveries are noted. The report also reviews and places in perspective the development of policies and regulations governing the industry and the jurisdictional relationships of the Federal and Provincial governments

Uranium production in Australia

International Nuclear Information System (INIS)

Fisk, B.G.

1984-01-01

The history of uranium mining and milling in Australia is briefly outlined, particular attention being given to the development of Australia's only two operating mills, Nabarlek and Ranger, and its only operating mine, Ranger. The latter project is used to illustrate the prerequisites for development of the industry and the complex roles of the various parties involved in establishing a new mine: equity holders, customers, financiers, the securities industry, trade unions, and the public. The moves currently being taken to resolve the future of the industry in Australia, particularly the examination of issues relating to Australia's role in the nuclear fuel cycle being conducted by the Australian Science and Technology Council, preclude any firm conclusions being drawn, but the various options open to the government are reviewed and the record of Australian governments and unions and the attitude of the Australian public are described. (Author) (3 tabs., fig.)

Occupational health experience with a contractor uranium refinery

International Nuclear Information System (INIS)

Heatherton, R.C.

1975-01-01

This paper presents information related to the occupational exposure of workers in uranium refinery operations at the Feed Materials Production Center since 1958. Included are: a brief history of the FMPC; a description of the operations and the principal sources of exposure; airborne uranium, urinary excretion, in vivo monitoring and tissue analysis data; and some observations regarding the exposure and health status of employees

Uranium in Canada: 1982 assessment of supply and requirements

International Nuclear Information System (INIS)

1983-09-01

Estimates of Canada's uranium resources for 1982 remained essentially unchanged from those of 1980. However, the economic conditions facing the industry have changed greatly during the past few years as production costs continued to rise without corresponding increases in uranium prices. As a result, a smaller portion of Canada's uranium resources is of current economic interest. Total resources amount to 573 000 tonnes of uranium. Just over 10% of this uranium will be required domestically during the next 30 years to fuel the more than 15 000 megawatts of nuclear power capacity now operating or committed for operation in Canada by 1993. In 1982 seven uranium producers in Canada, directly employing 4800 people, produced concentrates containing 8075 tonnes of uranium. Based on currently committed expansion plans, Canada's projected annual production capability could grow to some 12 000 tonnes of uranium by 1986. Canadian producers shipped 7643 tonnes of uranium valued at some $838 millon in 1982. As of January 1, 1983, outstanding uranium export commitments amounted to 60 000 tonnes or roughly 10% of the total Canadian uranium resources mentioned above. Japan has been Canada's most important single customer in the past decade, receiving about 34% of Canada's total exports since 1972. Most of the remaining exports have gone to the European Economic Community (33%), other countries in Western Europe (18%), and the United States (15%). Substantial efforts in uranium exploration that have been continued, especially in northern Saskatchewan, where two-thirds of the $71 million total exploration expenditures of 1982 were incurred. This continued effort has led to the discovery of a number of important deposits over the past few years which could be developed if market conditions improve. It is estimated that total Canadian production capability could reach 15 000 tonnes of uranium annually by the mid-1990s

Production of uranium metal via electrolytic reduction of uranium oxide in molten LiCl and salt distillation

International Nuclear Information System (INIS)

Eun-Young Choi; Chan Yeon Won; Dae-Seung Kang; Sung-Wook Kim; Ju-Sun Cha; Sung-Jai Lee; Wooshin Park; Hun Suk Im; Jin-Mok Hur

2015-01-01

Recovery of metallic uranium has been achieved by electrolytic reduction of uranium oxide in a molten LiCl-Li 2 O electrolyte at 650 deg C, followed by the removal of the residual salt by vacuum distillation at 850 deg C. Four types of stainless steel mesh baskets, with various mesh sizes (325, 1,400 and 2,300 meshes) and either three or five ply layers, were used both as cathodes and to contain the reduced product in the distillation stage. The recovered uranium had a metal fraction greater than 98.8 % and contained no residual salt. (author)

Dynamic removal of uranium by chitosan: influence of operating parameters

International Nuclear Information System (INIS)

Jansson-Charrier, Marielle; Guibal, Eric; Roussy, Jean; Surjous, Robert; Le Cloirec, Pierre

1996-01-01

New wastewater treatments involving biosorption processes are being developed. This work focuses on the dynamic removal of uranium using chitosan in fixed-bed reactors and investigates the main operating parameters: particle size, column size, flow velocity and metal ion concentrations. The results confirm the predominant effect of diffusion on the control rate. The optimization of the process should take into account both sorption performances and hydrodynamic behaviour. The process is successfully applied to the treatment of leachates at an abandoned mine site. This study shows that chitosan is an effective sorbent for the treatment and recovery of uranium from dilute effluents. (Author)

Nuclear purity and the production of uranium (1962)

International Nuclear Information System (INIS)

Verte, P.

1962-01-01

When the production of 'nuclear grade' uranium is dealt with, it is difficult, the author of this study points out, to separate its chemical, technical, and economical bearings. While recalling the evolution of chemical processes in various countries and describing the technic of uranium manufacture in the plant of the French 'Commissariat a l'Energie Atomique' at Le Bouchet, the author outlines the effect of economical contingencies on the problems the chemists and engineer are faced with. The question of cost price is also considered here with particular attention. (author) [fr

Moderation control in low enriched 235U uranium hexafluoride packaging operations and transportation

International Nuclear Information System (INIS)

Dyer, R.H.; Kovac, F.M.; Pryor, W.A.

1993-01-01

Moderation control is the basic parameter for ensuring nuclear criticality safety during the packaging and transport of low 235 U enriched uranium hexafluoride before its conversion to nuclear power reactor fuel. Moderation control has permitted the shipment of bulk quantities in large cylinders instead of in many smaller cylinders and, therefore, has resulted in economies without compromising safety. Overall safety and uranium accountability have been enhanced through the use of the moderation control. This paper discusses moderation control and the operating procedures to ensure that moderation control is maintained during packaging operations and transportation

Nichols Ranch ISL Uranium Mine - A case history

International Nuclear Information System (INIS)

Catchpole, G.; Thomas, G.

2014-01-01

The Nichols Ranch ISL Uranium Mine is located in the Powder River Basin of Wyoming, U.S.A. The mine is owned and operated by Uranerz Energy Corporation (Uranerz), a U.S. corporation headquartered in Casper, Wyoming. Nichols Ranch started operations in February 2014 and is the newest uranium mine to go into production in the USA. The uranium being extracted is hosted in a sandstone, roll-front deposit at a depth ranging from 400 to 800 feet [~120 to ~240 m). The In-Situ Recovery (ISL) mining method is employed at the Nichols Ranch mine which is the method currently being utilized at most uranium mines in the USA. Environmental permit applications for the Nichols Ranch mine were submitted to the appropriate regulatory agencies in late 2007. It required more than three and a half years to obtain all the necessary permits and licenses to construct and operate the mine. Construction of the mining facilities and the first wellfield started in late 2011 and was completed in late 2013. Mining results to date have been better than anticipated and Uranerz expects to reach its 2014 production target. The most challenging part of getting a new uranium mine in production in the United States of America was the three plus years it took to get through the environmental permitting process. Uranerz was one of three companies in 2011 that applied for permits to construct and operate uranium mines in Wyoming at essentially the same time. The Nichols Ranch mine is licensed to produce up to two million pounds per year of uranium (as U_3O_8) [~770 tU] ready for shipment to the converter. At this time only the ion exchange portion of the central processing plant has been installed at Nichols Ranch with uranium loaded resin being shipped to Cameco’s nearby Smith Ranch – Highland ISL uranium mine for elution, precipitation, drying and packaging under a toll processing agreement. Cameco provides Uranerz with dried and drummed yellowcake that Uranerz owns which is shipped to the

Production from new uranium mines a Cogema resources Saskatchewan perspective

International Nuclear Information System (INIS)

Pollock, B.

2001-01-01

The province of Saskatchewan is best known for the large flat tracts of land in the south that are primarily used for agricultural purposes. Less well known is the fact that the northern part of the province hosts the richest uranium mines in the world. In fact, to use a petroleum analogy, Saskatchewan has been referred to as the 'Saudi Arabia' of the uranium producing countries. The mining industry in Saskatchewan is a flourishing, high technology industry and supplies approximately one-third of the annual world primary production of uranium. The purpose of this paper is to examine the uranium mining industry in Saskatchewan and why this province stands alone as the dominant uranium producer in the world and will maintain that position into the foreseeable future. As well, an overview of the significant role played by COGEMA Resources in developing the Saskatchewan uranium industry will be undertaken. This company whose roots date back almost 40 years in the province, now holds significant interests in all four of the mines currently producing uranium. With investments of over one billion dollars (U.S.) in this province, COGEMA has established itself as a long-term player in the Saskatchewan Uranium Industry. (author)

Uranium hexafluoride production plant decommissioning

International Nuclear Information System (INIS)

Santos, Ivan

2008-01-01

The Institute of Energetic and Nuclear Research - IPEN is a research and development institution, located in a densely populated area, in the city of Sao Paulo. The nuclear fuel cycle was developed from the Yellow Cake to the enrichment and reconversion at IPEN. After this phase, all the technology was transferred to private enterprises and to the Brazilian Navy (CTM/SP). Some plants of the fuel cycle were at semi-industrial level, with a production over 20 kg/h. As a research institute, IPEN accomplished its function of the fuel cycle, developing and transferring technology. With the necessity of space for the implementation of new projects, the uranium hexafluoride (UF 6 ) production plant was chosen, since it had been idle for many years and presented potential leaking risks, which could cause environmental aggression and serious accidents. This plant decommission required accurate planning, as this work had not been carried out in Brazil before, for this type of facility, and there were major risks involving gaseous hydrogen fluoride aqueous solution of hydrofluoric acid (HF) both highly corrosive. Evaluations were performed and special equipment was developed, aiming to prevent leaking and avoid accidents. During the decommissioning work, the CNEN safety standards were obeyed for the whole operation. The environmental impact was calculated, showing to be not relevant.The radiation doses, after the work, were within the limits for the public and the area was released for new projects. (author)

Recovery of valuable products in liquid effluents from uranium and thorium pilot units

International Nuclear Information System (INIS)

Jardim, E.A.; Abrao, A.

1988-01-01

IPEN-CNEN/SP has being very active in refining yellowcake to pure ammonium diuranate which is converted to uranium trioxide, uranium dioxide, uranium tetra- and hexafluoride in a sequential way. The technology of the thorium purification and its conversion to nuclear grade products has been a practice since several years as well. For both elements the major waste to be worked is the refinate from the solvent extraction column where uranium and thorium are purified via TBP-varsol in pulsed columns. In this paper the actual processing technology is reviewed with special emphasis on the recovery of valuable products, mainly nitric acid and ammonium nitrate. Distilled nitric acid and the final sulfuric acid as residue are recycle. Ammonium nitrate from the precipitation of uranium diuranate is of good quality, being radioactivity and uranium-free, and recommended to be applied as fertilizer. In conclusion the main effort is to maximise the recycle and reuse of the abovementioned chemicals. (author) [pt

DEVELOPMENT OF HIGH-DENSITY U/AL DISPERSION PLATES FOR MO-99 PRODUCTION USING ATOMIZED URANIUM POWDER

Directory of Open Access Journals (Sweden)

HO JIN RYU

2013-12-01

Full Text Available Uranium metal particle dispersion plates have been proposed as targets for Molybdenum-99 (Mo-99 production to improve the radioisotope production efficiency of conventional low enriched uranium targets. In this study, uranium powder was produced by centrifugal atomization, and miniature target plates containing uranium particles in an aluminum matrix with uranium densities up to 9 g-U/cm3 were fabricated. Additional heat treatment was applied to convert the uranium particles into UAlx compounds by a chemical reaction of the uranium particles and aluminum matrix. Thus, these target plates can be treated with the same alkaline dissolution process that is used for conventional UAlx dispersion targets, while increasing the uranium density in the target plates

Canadian experience with uranium tailings disposal

International Nuclear Information System (INIS)

Culver, K.B.

1982-06-01

During the first years of uranium production in Canada uranium tailings were discharged directly into valleys or lakes near the mill. Treatment with barium chloride to precipitate radium began in 1965 at the Nordic Mine at Elliot Lake, Ontario. In the mid-60s and early 70s water quality studies indicated that discharges from uranium tailings areas were causing degradation to the upper part of the Serpent River water system. Studies into acid generation, revegetation, and leaching of radium were initiated by the mining companies and resulted in the construction of treatment plants at a number of sites. Abandoned tailings sites were revegetated. At hearings into the expansion of the Elliot Lake operations the issue of tailings management was a major item for discussion. As a result federal and provincial agencies developed guidelines for the siting and development of urnaium tailings areas prior to issuing operating licences. Western Canadian uranium producers do not have the acid generation problem of the Elliot Lake operations. The Rabbit Lake mill uses settling ponds followed by filtration. High-grade tailings from Cluff Lake are sealed in concrete and buried. Uranium producers feel that the interim criteria developed by the Atomic Energy Control Board, if adopted, would have a harmful effect on the viability of the Canadian uranium industry

Quality assurance in the enriched uranium operations NDA facility

Energy Technology Data Exchange (ETDEWEB)

May, P.K.; Ceo, R.N. [Oak Ridge Y-12 Plant, TN (United States)

1997-11-01

The Nondestructive Analysis (NDA) Facility at the Oak Ridge Y-12 Plant has characterized process wastes for Enriched Uranium Operations since 1978. Since that time, over 50,000 items have been analyzed. Analysis results are used to determine whether or not recovery of uranium from process wastes is economically feasible. Our instrument complement includes one large segmented gamma scanner (SGS), two smaller SGS, two solution assay systems (SAS), and Active Well Coincidence Counter (AWCC). The large SGS is used for analyzing High Efficiency Particulate Air (HEPA) filters ant 208-L drums filled with combustible contaminated waste. The smaller SGS are used to analyze 4-L containers of ash and leached residues. The SAS are used to analyze 125 ml bottles of aqueous or organic waste solutions that may contain uranium. The gamma-based NDA techniques are used to identify which process wastes can be discarded, and which must be recycled. The AWCC is used to analyze high-density materials which are not amenable to gamma-ray analysis. 1 ref., 4 figs.

Reduction of uranium hexafluoride to uranium tetrafluoride

International Nuclear Information System (INIS)

Chang, I.S.; Do, J.B.; Choi, Y.D.; Park, M.H.; Yun, H.H.; Kim, E.H.; Kim, Y.W.

1982-01-01

The single step continuous reduction of uranium hexafluoride (UF 6 ) to uranium tetrafluoride (UF 4 ) has been investigated. Heat required to initiate and maintain the reaction in the reactor is supplied by the highly exothermic reaction of hydrogen with a small amount of elemental fluorine which is added to the uranium hexafluoride stream. When gases uranium hexafluoride and hydrogen react in a vertical monel pipe reactor, the green product, UF 4 has 2.5g/cc in bulk density and is partly contaminated by incomplete reduction products (UF 5 ,U 2 F 9 ) and the corrosion product, presumably, of monel pipe of the reactor itself, but its assay (93% of UF 4 ) is acceptable for the preparation of uranium metal with magnesium metal. Remaining problems are the handling of uranium hexafluoride, which is easily clogging the flowmeter and gas feeding lines because of extreme sensitivity toward moisture, and a development of gas nozzel for free flow of uranium hexafluoride gas. (Author)

Surface area and chemical reactivity characteristics of uranium metal corrosion products

International Nuclear Information System (INIS)

Totemeier, T. C.

1998-01-01

The results of an initial characterization of hydride-containing corrosion products from uranium metal Zero Power Physics Reactor (ZPPR) fuel plates are presented. Sorption analyses using the BET method with a Kr adsorbate were performed to measure the specific areas of corrosion product samples. The specific surface areas of the corrosion products varied from 0.66 to 1.01 m 2 /g. The reactivity of the products in Ar-9%O 2 and Ar-20%O 2 were measured at temperatures between 35 C and 150 C using a thermo-gravimetric analyzer. Ignition of the products occurred at temperatures of 150 C and above. The oxidation rates below ignition were comparable to rates observed for uranium metal

Recent developments in Australia's uranium mining industry

International Nuclear Information System (INIS)

Lambert, I.B.; McKay, A.D.

1998-01-01

Australia's economic, demonstrated resources of uranium (U) at the end of 1996 amounted to 622,000 tonnes U, the largest of any country. Uranium is currently produced at two mining/milling operations in Australia - Ranger in the Alligator Rivers Region of the Northern Territory, and Olympic Dam in South Australia. Improved market conditions and recent changes to Government policies have encouraged Australian companies to commit to the expansion of existing operations and the development of new uranium mines. Australia's annual production is likely to increase from its present level of 6000 tonncs (t) U 3 O 8 to approximately 12 000 t U 3 O 8 by the year 2000. (author)

Production of uranium peroxide

International Nuclear Information System (INIS)

Caropreso, F.E.; Kreuz, D.F.

1977-01-01

A process is claimed of recovering uranium values as uranium peroxide from an aqueous uranyl solution containing dissolved vanadium and sodium impurities by treating the uranyl solution with hydrogen peroxide in an amount sufficient to have an excess of at least 0.5 parts H 2 O 2 per part of vanadium (V 2 O 5 ) above the stoichiometric amount required to form the uranium peroxide, the hydrogen peroxide treatment is carried out in three sequential phases consisting of I, a precipitation phase in which the hydrogen peroxide is added to the uranyl solution to precipitate the uranium peroxide and the pH of the reaction medium maintained in the range of 2.5 to 5.5 for a period of from about 1 to 60 minutes after the hydrogen peroxide addition; II, a digestion phase in which the pH of the reaction medium is maintained in the range of 3.0 to 7.0 for a period of about 5 to 180 minutes and III, a final phase in which the pH of the reaction medium is maintained in the range of 4.0 to 7.0 for a period of about 1 to 60 minutes during which time the uranium peroxide is separated from the reaction solution containing the dissolved vanadium and sodium impurities. The excess hydrogen peroxide is maintained during the entire treatment up until the uranium peroxide is separated from the reaction medium

Managing the Ranger uranium mine in the Alligator Rivers Region -there is much more to this business enterprise than just production

International Nuclear Information System (INIS)

Leggate, J.

1984-01-01

Environmental protection is very closely and continuously regulated at the Ranger uranium mine. Since the commencement of operations at Ranger the company has operated within these regulations and demonstrated clearly that yellowcake can be produced efficiently, economically and safely. The company also recognises that in order to ensure continuity of production, it will have to continue to operate within these strictly supervised regulations

Process for decontamination of surfaces in an facility of natural uranium hexafluoride production (UF6)

International Nuclear Information System (INIS)

Almeida, Claudio C. de; Silva, Teresinha M.; Rodrigues, Demerval L.; Carneiro, Janete C.G.G.

2017-01-01

The experience acquired in the actions taken during the decontamination process of an IPEN-CNEN / SP Nuclear and Energy Research Institute facility, for the purpose of making the site unrestricted, is reported. The steps of this operation involved: planning, training of facility operators, workplace analysis and radiometric measurements. The facility had several types of equipment from the natural uranium hexafluoride (UF 6 ) production tower and other facility materials. Rules for the transportation of radioactive materials were established, both inside and outside the facility and release of materials and installation

Uranium in Niger; L'uranium au Niger

Energy Technology Data Exchange (ETDEWEB)

Gabelmann, E

1978-03-15

This document presents government policy in the enhancement of uranium resources, existing mining companies and their productions, exploitation projects and economical outcome related to the uranium mining and auxiliary activities. [French] Le document presente la politique de l'Etat dans le cadre de la mise en valeur des ressources d'uranium, les societes minieres existantes et leurs productions, les projets d'exploitation d'uranium et les retombees economiques liees aux activites uraniferes et connexes.

Remediation of a uranium-contaminated quarry utilizing submersible, remotely operated vehicles

International Nuclear Information System (INIS)

Fleming, K.N.

1992-01-01

The Kerr Hollow Quarry (KHQ) Disposal Site on the Oak Ridge (Tennessee) Reservation was previously used to treat and dispose of pyrophoric and water-reactive wastes contaminated with small quantities of radioactive materials (almost exclusively uranium and uranium daughters) from processes at the Department of Energy-owned, Oak Ridge Y-12 Plant and Oak Ridge National Laboratory. This paper describes remediation techniques utilizing a small, remotely operated submarine with an attached camera to visually locate waste containers, determine whether containers have been breached, transport small containers, and direct a larger remotely operated grappling machine to move larger waste for shredding operations. Most of the solid waste is reduced under water by a metal shredder. Non-shreddable items (e. g. , gas cylinders and larger structures) are mechanically breached under water to allow the contents to fully react. The waste is then removed from the water, monitored, the material is segregated, and transported to a temporary waste storage area until disposal

Uranium

International Nuclear Information System (INIS)

Poty, B.; Cuney, M.; Bruneton, P.; Virlogeux, D.; Capus, G.

2010-01-01

With the worldwide revival of nuclear energy comes the question of uranium reserves. For more than 20 years, nuclear energy has been neglected and uranium prospecting has been practically abandoned. Therefore, present day production covers only 70% of needs and stocks are decreasing. Production is to double by 2030 which represents a huge industrial challenge. The FBR-type reactors technology, which allows to consume the whole uranium content of the fuel, is developing in several countries and will ensure the long-term development of nuclear fission. However, the implementation of these reactors (the generation 4) will be progressive during the second half of the 21. century. For this reason an active search for uranium ores will be necessary during the whole 21. century to ensure the fueling of light water reactors which are huge uranium consumers. This dossier covers all the aspects of natural uranium production: mineralogy, geochemistry, types of deposits, world distribution of deposits with a particular attention given to French deposits, the exploitation of which is abandoned today. Finally, exploitation, ore processing and the economical aspects are presented. Contents: 1 - the uranium element and its minerals: from uranium discovery to its industrial utilization, the main uranium minerals (minerals with tetravalent uranium, minerals with hexavalent uranium); 2 - uranium in the Earth's crust and its geochemical properties: distribution (in sedimentary rocks, in magmatic rocks, in metamorphic rocks, in soils and vegetation), geochemistry (uranium solubility and valence in magmas, uranium speciation in aqueous solution, solubility of the main uranium minerals in aqueous solution, uranium mobilization and precipitation); 3 - geology of the main types of uranium deposits: economical criteria for a deposit, structural diversity of deposits, classification, world distribution of deposits, distribution of deposits with time, superficial deposits, uranium

Nuclear fuel cycle head-end enriched uranium purification and conversion into metal

International Nuclear Information System (INIS)

Bonini, A.; Cabrejas, J.; Lio, L. de; Dell'Occhio, L.; Devida, C.; Dupetit, G.; Falcon, M.; Gauna, A.; Gil, D.; Guzman, G.; Neuringer, P.; Pascale, A.; Stankevicius, A.

1998-01-01

The CNEA (Comision Nacional de Energia Atomica - Argentina) operated two facilities at the Ezeiza Atomic Center which supply purified enriched uranium employed in the production of nuclear fuels. At one of those facilities, the Triple Height Laboratory scraps from the production of MTR type fuel elements (mainly out of specification U 3 O 8 plates or powder) are purified to nuclear grade. The purification is accomplished by a solvent extraction process. The other facility, the Enriched Uranium Laboratory produces 90% enriched uranium metal to be used in Mo 99 production (originally the uranium was used for the manufacture of MTR fuel elements made of aluminium-uranium alloy). This laboratory also provided metallic uranium with a lower enrichment (20%) for a first uranium-silicon testing fuel element, and in the near future it is going to recommence 20% enriched uranium related activities in order to provide the metal for the silicon-based fuel elements production (according to the policy of enrichment reduction for MTR reactors). (author)

Reclamation of uranium mining and milling disturbances

International Nuclear Information System (INIS)

Farmer, E.E.; Schuman, G.E.

1987-01-01

Since 1945 the history of uranium mining and milling in the US has been a story of wide fluctuations in market prices and in mining and milling capacity. The late 1960's and the 1970's saw a sizeable reduction in the production of yellowcake because of an earlier over-supply, a leveling off of the military demand, and a failure of the nuclear electric power industry to create the anticipated commercial demand. The decline in the domestic production of yellowcake has continued through the early 1980's to the present. Today, there are five operating uranium mills in the US: one in Wyoming, two in Utah, one in New Mexico, and one in Texas. Of these five mills, three are operating on a reduced schedule, as little as three days a month. A significant portion of the current US production of uranium goes overseas to fulfill Japanese, French, and other European contracts. There is still a sizeable reclamation job to be accomplished on old uranium wastes, both tailings impoundments and overburden embankments. Before the Uranium Mill Tailings Control Act of 1978 (PL 95-604), reclamation was frequently omitted altogether, or else done in a haphazard fashion. We do not know the total area of unreclaimed, radioactive, uranium overburden wastes in the western US, but the area is large, probably several thousand hectares. Fortunately, these overburden wastes are almost entirely located in remote areas. Mill tailings are more difficult to reclaim than overburden, and tailings represent a more serious health hazards. There are approximately 25 million metric tons of unreclaimed uranium mill tailings, with variable health hazards, located in the US

On the separation of so-called non-volatile uranium fission products of uranium using the conversion of neutron-irradiated uranium dioxide and graphite

International Nuclear Information System (INIS)

Elhardt, W.

1979-01-01

The investigations are continued in the following work which arose from the concept of separating uranium fission products from uranium. This is achieved in that due to the lattice conversions occurring during the course of solid chemical reactions, fission products can easily pass from the uranium-contained solid to a second solid. The investigations carried out primarily concern the release behaviour of cerium and neodymium in the temperature region of 1200 to 1700 0 C. UO 2 + graphite, both in powder form, are selected as suitable reaction system having the preconditions needed for the lattice conversion for the release effect. The target aimed at from the practical aspect for the improved release of lanthanoids is achieved by an isobar test course - changing temperature from 1200 to 1500 0 C at constant pressure, with a cerium release of 75-80% and a neodynium release of 80-90% (maximum at 1400 0 C). The concepts on the mechanism of the fission product release are related to transport processes in crystal lattices, as well as chemical solid reactions and evaporation processes on the surface of UC 2 grains. (orig./RB) [de

Glances on uranium. Tome 2. Exploration, production

International Nuclear Information System (INIS)

Valsardieu, C.

1997-01-01

This book is an homage to all participants of uranium prospecting and mining exploitation who have contributed to satisfy the nuclear energy needs during the last 50 years. The first chapter describes the economical, administrative and environmental constraints of uranium mining projects. The second chapter describes the different steps of the exploration (permits, inventory, mineralisation, quality, resource estimation, quantifying), the direct and indirect exploratory techniques and methods (radiometry, geochemistry, drillings and well logging, mapping, tele-detection, geophysical surveys..) and the exploration costs. The third chapter deals with the legal, administrative, technical, socio-economical and financial aspects which must be taken into account in the risk evaluation of a mining project. Chapter 4 concerns the start up of the project while the development and production methods are detailed in chapter 5 (opencast and underground mining, in-situ lixiviation, ore processing, chemical extraction etc.). The last chapter is devoted to the environmental aspects of uranium mining: legal aspects, nuisances, dusts, contamination, the case of in-situ lixiviation, the rehabilitation of sites. (J.S.)

Uranium and thorium recovery from a sub-product of monazite industrial processing

International Nuclear Information System (INIS)

Gomiero, L.A.; Ribeiro, J.S.; Scassiotti Filho, W.

1994-01-01

In the monazite alkaline leaching industrial process for the production of rare earth elements, a by-product is formed, which has a high concentration of thorium and a lower but significant one of uranium. A procedure for recovery of the thorium and uranium contents in this by-product is presented. The first step of this procedure is the leaching with sulfuric acid, followed by uranium extraction from the acid liquor with a tertiary amine, stripping with a Na Cl solutions and precipitation as ammonium diuranate with N H 4 O H. In order to obtain thorium concentrates with higher purity, it is performed by means of the extraction of thorium from the acid liquor, with a primary amine, stripping by a Na Cl solution and precipitation as thorium hydroxide or oxalate. (author)

Radioecological investigations of uranium mill tailings systems: Final report for the period September 1, 1979 through April 30, 1987

International Nuclear Information System (INIS)

Whicker, F.W.; Ibrahim, S.A.

1987-01-01

This document is the final report on studies of the integrity and transport of uranium and radioactive progeny in active and reclaimed uranium mill tailings. The overall program was designed to provide basic information on the radioecology of 238 U, 230 Th, 226 Ra, 210 Pb and 210 Po, responses of plants and animals to the landscape disruptions associated with uranium production, and guidance for impact analysis, mitigation and regulation of the uranium industry. The studies reported were conducted at the Shirley Basin Uranium Mine, which is operated by the Pathfinder Mines Corporation. The mine/mill operation, located in southeastern Wyoming, is typical in terms of the ore body, mill process, and ecological setting of many uranium production centers in the western United States. The research was motivated originally by the general lack of knowledge on the transport of uranium and its radioactive daughter products through the environment, particularly through food chains in the immediate environs of uranium production operations. The work was also motivated by the relatively high contribution of uranium mining and milling to the radiation exposure of the general population from the nuclear fuel cycle

Decommissioning of nuclear facilities involving operations with uranium and thorium

International Nuclear Information System (INIS)

Shum, E.Y.; Neuder, S.M.

1990-01-01

When a licensed nuclear facility ceases operation, the U.S. Nuclear Regulatory Commission (NRC) ensures that the facility and its site are decontaminated to acceptable levels so they may safely be released for unrestricted public use. Because specific environmental standards or broad federal guidelines governing release of residual radioactive contamination have not been issued, NRC has developed ad hoc cleanup criteria for decommissioning nuclear facilities that involved uranium and thorium. Cleanup criteria include decontamination of buildings, equipment, and land. We will address cleanup criteria and their rationale; procedures for decommissioning uranium/thorium facilities; radiological survey designs and procedures; radiological monitoring and measurement; and cost-effectiveness to demonstrate compliance

Effects of cellulosic degradation products on uranium sorption in the geosphere

International Nuclear Information System (INIS)

Baston, G.M.N.; Berry, J.A.; Bond, K.A.; Boult, K.A.; Brownsword, M.; Linklater, C.M.

1994-01-01

The current design concept for intermediate- and some low-level radioactive waste disposal in the UK involves emplacement in a cementitious repository deep underground. The movement of radionuclides away from such a repository through the host rock formation towards the biosphere is expected to be retarded to a significant degree by sorption processes. One major issue being studied is the effect on uranium sorption of degradation products arising from organic waste matter, especially cellulosic materials. The sorption of uranium could be reduced by degradation products, either because of complexation, or through the organic materials competing for sorption sites. Because of the complexity of authentic degradation products, work has also been carried out using gluconate and iso-saccharinate as well-characterised simulants. In the presence of high concentrations of either the authentic or simulated degradation products, significant reductions in uranium sorption have been observed. However, in the presence of lower concentrations of these organic materials, such as would be present in the repository, sorption was reduced at most by only a small margin and, in some cases, the results suggested a slight increase. ((orig.))

Effects of cellulosic degradation products on uranium sorption in the geosphere

Energy Technology Data Exchange (ETDEWEB)

Baston, G.M.N. (AEA Technology, Harwell, Didcot, Oxon OX11 0RA (United Kingdom)); Berry, J.A. (AEA Technology, Harwell, Didcot, Oxon OX11 0RA (United Kingdom)); Bond, K.A. (AEA Technology, Harwell, Didcot, Oxon OX11 0RA (United Kingdom)); Boult, K.A. (AEA Technology, Harwell, Didcot, Oxon OX11 0RA (United Kingdom)); Brownsword, M. (AEA Technology, Harwell, Didcot, Oxon OX11 0RA (United Kingdom)); Linklater, C.M. (AEA Technology, Harwell, Didcot, Oxon OX11 0RA (United Kingdom))

1994-10-01

The current design concept for intermediate- and some low-level radioactive waste disposal in the UK involves emplacement in a cementitious repository deep underground. The movement of radionuclides away from such a repository through the host rock formation towards the biosphere is expected to be retarded to a significant degree by sorption processes. One major issue being studied is the effect on uranium sorption of degradation products arising from organic waste matter, especially cellulosic materials. The sorption of uranium could be reduced by degradation products, either because of complexation, or through the organic materials competing for sorption sites. Because of the complexity of authentic degradation products, work has also been carried out using gluconate and iso-saccharinate as well-characterised simulants. In the presence of high concentrations of either the authentic or simulated degradation products, significant reductions in uranium sorption have been observed. However, in the presence of lower concentrations of these organic materials, such as would be present in the repository, sorption was reduced at most by only a small margin and, in some cases, the results suggested a slight increase. ((orig.))

Uranium conversion; Urankonvertering

Energy Technology Data Exchange (ETDEWEB)

Oliver, Lena; Peterson, Jenny; Wilhelmsen, Katarina [Swedish Defence Research Agency (FOI), Stockholm (Sweden)

2006-03-15

FOI, has performed a study on uranium conversion processes that are of importance in the production of different uranium compounds in the nuclear industry. The same conversion processes are of interest both when production of nuclear fuel and production of fissile material for nuclear weapons are considered. Countries that have nuclear weapons ambitions, with the intention to produce highly enriched uranium for weapons purposes, need some degree of uranium conversion capability depending on the uranium feed material available. This report describes the processes that are needed from uranium mining and milling to the different conversion processes for converting uranium ore concentrate to uranium hexafluoride. Uranium hexafluoride is the uranium compound used in most enrichment facilities. The processes needed to produce uranium dioxide for use in nuclear fuel and the processes needed to convert different uranium compounds to uranium metal - the form of uranium that is used in a nuclear weapon - are also presented. The production of uranium ore concentrate from uranium ore is included since uranium ore concentrate is the feed material required for a uranium conversion facility. Both the chemistry and principles or the different uranium conversion processes and the equipment needed in the processes are described. Since most of the equipment that is used in a uranium conversion facility is similar to that used in conventional chemical industry, it is difficult to determine if certain equipment is considered for uranium conversion or not. However, the chemical conversion processes where UF{sub 6} and UF{sub 4} are present require equipment that is made of corrosion resistant material.

A Model to Reproduce the Response of the Gaseous Fission Product Monitor (GFPM) in a CANDU{sup R} 6 Reactor (An Estimate of Tramp Uranium Mass in a Candu Core)

Energy Technology Data Exchange (ETDEWEB)

Mostofian, Sara; Boss, Charles [AECL Atomic Energy of Canada Limited, 2251 Speakman Drive, Mississauga Ontario L5K 1B2 (Canada)

2008-07-01

In a Canada Deuterium Uranium (Candu) reactor, the fuel bundles produce gaseous and volatile fission products that are contained within the fuel matrix and the welded zircaloy sheath. Sometimes a fuel sheath can develop a defect and release the fission products into the circulating coolant. To detect fuel defects, a Gaseous Fission Product Monitoring (GFPM) system is provided in Candu reactors. The (GFPM) is a gamma ray spectrometer that measures fission products in the coolant and alerts the operator to the presence of defected fuel through an increase in measured fission product concentration. A background fission product concentration in the coolant also arises from tramp uranium. The sources of the tramp uranium are small quantities of uranium contamination on the surfaces of fuel bundles and traces of uranium on the pressure tubes, arising from the rare defected fuel element that released uranium into the core. This paper presents a dynamic model that reproduces the behaviour of a GFPM in a Candu 6 plant. The model predicts the fission product concentrations in the coolant from the chronic concentration of tramp uranium on the inner surface of the pressure tubes (PT) and the surface of the fuel bundles (FB) taking into account the on-power refuelling system. (authors)

Market outlook for Australian uranium producers

International Nuclear Information System (INIS)

Lindsay, M.

2001-01-01

Recent improvements in the uranium market and political changes in Australia presented the uranium producers with their best opportunity in over 15 years. The removal of the well known 'three mines policy' by the current government has encouraged Australian producers to develop new development plans. With the expansion of the existing operations at Ranger and Olympic Dam, and the potential operations of Jabiluka, Kintyre, Koongara, Honeymoon and Beverley, Australia expects to increase annual production to 11630 t U 3 O 8 by the end of the decade. It will then join Canada as a major supplier of uranium to the world's nuclear power utilities in the 21st century. Uranium exploration, which has been virtually nonexistent over the past 15 years, has once again been reactivated. This occurred because of the change in the Government, but also because the Aboriginal groups are once more allowing exploration on their land. (author)

Production of annular blanks for Mo-99 using natural uranium, LEU uranium, nickel and structural Al-3003 plates

International Nuclear Information System (INIS)

Lisboa, J.R.; Barrera, M.E.; Marin, J.

2010-01-01

The Tc-99m radioisotope for medical use is the one most used in nuclear medicine worldwide. In Chile the Tc-99m is applied in more than 90% of nuclear medicine studies. In order to supply the whole country with this radioisotope, in 2005-2007 the CCHEN developed its own production of Tc-99m generators from Mo-99 imported from Canada, which are prepared with the activity needed by the Chilean hospitals and clinics. As of 2007 Mo-99 was no longer imported, and since then the Tc-99m is produced only by neutron activation of the Mo. The present challenge is to produce Mo-99 by irradiating blanks that contain enriched uranium foils, with locally produced LEU. The annular blank consists of 2 concentric tubes of A1-3003 structural aluminum that, in an interior annular space, contain a LEU foil, covered on both sides by a nickel foil. This work presents the development of the production technology for annular blanks using natural uranium and U-325 enriched uranium. The structural components are made with A1-3003 aluminum alloy, the foils are 13 grams of uranium measuring 100 x 50 mm and 120-150 μ thick. The blank was assembled using a methodology to control, adapt and assemble the blank's different internal components. A foil of natural uranium and LEU uranium, and a nickel foil are included, used as a barrier for the escape of fission products. During the blank's expansion, for analysis alcohol as lubricant was used, allowing the expander to move smoothly through the inside of the blank. The blank was sealed by TIG welding with a pulsed AC current and a mixture of Ar-5% He gases. Two methods were used for the water tightness test; for high escape levels the temperature was used as a promoter of the ΔP provided by hot water and liquid nitrogen, for low escape levels high vacuum technology was used where the ΔP is provided by a high pressure helium atmosphere. The technology for the production of annular LEU blanks was achieved by applying innovations to technologies

Uranium hexafluoride handling

International Nuclear Information System (INIS)

1991-01-01

The United States Department of Energy, Oak Ridge Field Office, and Martin Marietta Energy Systems, Inc., are co-sponsoring this Second International Conference on Uranium Hexafluoride Handling. The conference is offered as a forum for the exchange of information and concepts regarding the technical and regulatory issues and the safety aspects which relate to the handling of uranium hexafluoride. Through the papers presented here, we attempt not only to share technological advances and lessons learned, but also to demonstrate that we are concerned about the health and safety of our workers and the public, and are good stewards of the environment in which we all work and live. These proceedings are a compilation of the work of many experts in that phase of world-wide industry which comprises the nuclear fuel cycle. Their experience spans the entire range over which uranium hexafluoride is involved in the fuel cycle, from the production of UF 6 from the naturally-occurring oxide to its re-conversion to oxide for reactor fuels. The papers furnish insights into the chemical, physical, and nuclear properties of uranium hexafluoride as they influence its transport, storage, and the design and operation of plant-scale facilities for production, processing, and conversion to oxide. The papers demonstrate, in an industry often cited for its excellent safety record, continuing efforts to further improve safety in all areas of handling uranium hexafluoride

Surface area and chemical reactivity characteristics of uranium metal corrosion products.

Energy Technology Data Exchange (ETDEWEB)

Totemeier, T. C.

1998-02-17

The results of an initial characterization of hydride-containing corrosion products from uranium metal Zero Power Physics Reactor (ZPPR) fuel plates are presented. Sorption analyses using the BET method with a Kr adsorbate were performed to measure the specific areas of corrosion product samples. The specific surface areas of the corrosion products varied from 0.66 to 1.01 m{sup 2}/g. The reactivity of the products in Ar-9%O{sub 2} and Ar-20%O{sub 2} were measured at temperatures between 35 C and 150 C using a thermo-gravimetric analyzer. Ignition of the products occurred at temperatures of 150 C and above. The oxidation rates below ignition were comparable to rates observed for uranium metal.

Nuclear purity and the production of uranium (1962); La purete nucleaire et la fabrication de l'uranium (1962)

Energy Technology Data Exchange (ETDEWEB)

Verte, P [Commissariat a l' Energie Atomique, Centre du Bouchet, Saclay (France). Centre d' Etudes Nucleaires

1962-07-01

When the production of 'nuclear grade' uranium is dealt with, it is difficult, the author of this study points out, to separate its chemical, technical, and economical bearings. While recalling the evolution of chemical processes in various countries and describing the technic of uranium manufacture in the plant of the French 'Commissariat a l'Energie Atomique' at Le Bouchet, the author outlines the effect of economical contingencies on the problems the chemists and engineer are faced with. The question of cost price is also considered here with particular attention. (author) [French] Lorsqu'il s'agit de la production d'uranium de 'qualite nucleaire', il est difficile, souligne l'auteur de cette etude, de separer les aspects chimique, technique et economique. Aussi, en retracant l'evolution des procedes chimiques dans divers pays et decrivant les techniques de fabrication de l'uranium a l'usine du Bouchet du Commissariat a l'Energie Atomique, l'auteur ne manque-t-il pas de rappeler les incidences de la conjoncture economique sur les problemes posees au chimiste et a l'ingenieur. La question du prix de revient, egalement, est traitee ici avec une attention particuliere. (auteur)

Status of domestic uranium industry

International Nuclear Information System (INIS)

Chenoweth, W.L.

1989-01-01

The domestic uranium industry continues to operate at a reduced level, due to low prices and increased foreign competition. For four years (1984-1987) the Secretary of Energy declared the industry to be nonviable. A similar declaration is expected for 1988. Exploration and development drilling, at the rate of 2 million ft/year, continue in areas of producing mines and recent discoveries, especially in northwestern Arizona, northwestern Nebraska, south Texas, Wyoming, and the Paradox basin of Colorado and Utah. Production of uranium concentrate continues at a rate of 13 to 15 million lb of uranium oxide (U 3 O 8 ) per year. Conventional mining in New Mexico, Arizona, Utah, Colorado, Wyoming, and Texas accounts for approximately 55% of the production. The remaining 45% comes from solution (in situ) mining, from mine water recovery, and as by-products from copper production and the manufacture of phosphoric acid. Solution mining is an important technique in Wyoming, Nebraska, and Texas. By-product production comes from phosphate plants in Florida and Louisiana and a copper mine in Utah. Unmined deposits in areas such as the Grants, New Mexico, district are being investigated for their application to solution mining technology. The discovered uranium resources in the US are quite large, and the potential to discover additional resources is excellent. However, higher prices and a strong market will be necessary for their exploitation

Uranium health physics

International Nuclear Information System (INIS)

1980-01-01

This report contains the papers delivered at the Summer School on Uranium Health Physics held in Pretoria on the 14 and 15 April 1980. The following topics were discussed: uranium producton in South Africa; radiation physics; internal dosimetry and radiotoxicity of long-lived uranium isotopes; uranium monitoring; operational experience on uranium monitoring; dosimetry and radiotoxicity of inhaled radon daughters; occupational limits for inhalation of radon-222, radon-220 and their short-lived daughters; radon monitoring techniques; radon daughter dosimeters; operational experience on radon monitoring; and uranium mill tailings management

Uranium in Canada: 1984 assessment of supply and requirements

International Nuclear Information System (INIS)

1985-09-01

The success of uranium exploration efforts in Canada has continued, resulting in an overall increase in domestic uranium resource estimates for the principal resource categories. In 1984, Canada's five primary uranium producers employed some 5,800 people at their mining and milling operations, and produced concentrates containing some 11 170 tU. In 1984 the resource estimates were (in tonnes U recoverable): measured - 54 000; indicated - 233 000; inferred - 264 000. Canada's projected annual primary uranium production capability will stabilize at some 12 000 tU through the remainder of the 1980s. Should market conditions warrant, additional production centres could be developed to raise production capability to a level of 15 000 tU by the latter half of the 1990s. Prognosticated resources exploitable at uranium prices of $300/kg U or less are estimated to amount to 292 000 tU. Speculative resources of interest at prices of $300/kg U or less, in areas assessed during 1984, are thought to total approximately one million tU. Uranium exploration expenditures in Canada in 1983 and 1984 were an estimated $41 and $35 million, respectively. Exploration drilling and surface development drilling in 1983 and 1984 were reported to be 153 000 m and 197 000 m, respectively, some 85 per cent of which was in Saskatchewan. Canada's known uranium resources, recoverable at uranium prices of $150/kg U or less, are more than sufficient to meet the 30-year fuelling requirements of those reactors in Canada that are either in operation now or committed or expected to be in-service by 1995. Over the longer term, there is significant potential for discovering additional uranium resources in Canada

PRODUCTION OF URANIUM METAL BY CARBON REDUCTION

Science.gov (United States)

Holden, R.B.; Powers, R.M.; Blaber, O.J.

1959-09-22

The preparation of uranium metal by the carbon reduction of an oxide of uranium is described. In a preferred embodiment of the invention a charge composed of carbon and uranium oxide is heated to a solid mass after which it is further heated under vacuum to a temperature of about 2000 deg C to produce a fused uranium metal. Slowly ccoling the fused mass produces a dendritic structure of uranium carbide in uranium metal. Reacting the solidified charge with deionized water hydrolyzes the uranium carbide to finely divide uranium dioxide which can be separated from the coarser uranium metal by ordinary filtration methods.

Tax neutrality and the Saskatchewan Uranium Royalty

International Nuclear Information System (INIS)

Campbell, H.F.; Wrean, D.L.

1984-01-01

The effect of the Saskatchewan Uranium Royalty (SUR) on the extraction plans of uranium mining companies operating in Saskatchewan are discussed. The SUR consists of a basic royalty on the value of production and a graduated rate of return tax. Companies are also subject to federal and provincial income taxes. A model, based on the Key Lake mine in Australia, is used to determine whether the tax regime operating in Saskatchewan has the property of neutrality and effects the optimal extraction rate. Results show that SUR is a relatively low-cost means of collecting an economic rent from uranium mining and results in a lower extraction rate contributing to environmental protection in the province. (U.K.)

Recent developments in Australia's uranium mining industry

International Nuclear Information System (INIS)

McKay, A.D.

2001-01-01

Uranium is produced at two mining/milling operations in Australia - Ranger in the Alligator Rivers Region of the Northern Territory, and Olympic Dam in South Australia. In 1996, Ranger produced 4138 tonnes (t) U 3 O 8 from stockpiled ore mined from Ranger No. 1 Orebody. The capacity of the Ranger mill is being expanded to 5000 tonnes per annum (tpa) U 3 O 8 to coincide with the commencement of mining from No. 3 Orebody in mid-1997. The Olympic Dam copper-uranium-gold-silver deposit is the world's largest deposit of low cost uranium. The operation currently has an annual production of 85,000 t copper, 1700 t U 3 O 8 and associated gold and silver. WMC Ltd proposes to expand annual production to 200 000 t copper and approximately 4600 t U 3 O 8 by end of 1999. The environmental impact of the expansion is being assessed jointly by both Commonwealth and South Australian Governments. A draft Environmental Impact Statement (EIS) was released in May. Since its election in March 1996, the Liberal/National Party Coalition Government has made a number of changes to the Commonwealth Government's policies relating to uranium mining, including removal of the former Government's 'three mines' policy, and relaxation of the guidelines for foreign investment in Australian uranium mines. These changes, together with an improved outlook for the uranium market, have resulted in proposals to develop new mines at Jabiluka (Northern Territory), Kintyre (Western Australia) and Beverley (South Australia). Energy Resources of Australia Ltd proposes to develop an underground mine at Jabiluka with the ore to be processed at Ranger mill. Initial production will be 1800 tpa U 3 O 8 which will increase to 4000 tpa U 3 O 8 by the 14th year. The draft EIS was released for public comment in October 1996, and the final EIS is to be released in June 1997. Canning Resources Ltd proposes to mine the Kintyre deposit by open cut methods commencing in 1999 with an annual production of 1200 tpa U 3 O 8

Uranium

International Nuclear Information System (INIS)

Hamdoun, N.A.

2007-01-01

The article includes a historical preface about uranium, discovery of portability of sequential fission of uranium, uranium existence, basic raw materials, secondary raw materials, uranium's physical and chemical properties, uranium extraction, nuclear fuel cycle, logistics and estimation of the amount of uranium reserves, producing countries of concentrated uranium oxides and percentage of the world's total production, civilian and military uses of uranium. The use of depleted uranium in the Gulf War, the Balkans and Iraq has caused political and environmental effects which are complex, raising problems and questions about the effects that nuclear compounds left on human health and environment.

Prediction of the net radon emission from a model open pit uranium mine

International Nuclear Information System (INIS)

Nielson, K.K.; Perkins, R.W.; Schwendiman, L.C.; Enderlin, W.I.

1979-04-01

Radon emission from a model open pit uranium mining operation has been estimated by applying radon exhalation fluxes measured in an open pit uranium mine to the various areas of the model mine. The model mine was defined by averaging uranium concentrations and production and procedural statistics for eight major open pit uranium mines in the Casper, Wyoming area. The resulting emission rates were 740 Ci/AFR during mining operations and 33 Ci/AFR/yr after abandonment of the mine

Uranium Industry Annual, 1992

International Nuclear Information System (INIS)

1993-01-01

The Uranium Industry Annual provides current statistical data on the US uranium industry for the Congress, Federal and State agencies, the uranium and electric utility industries, and the public. The feature article, ''Decommissioning of US Conventional Uranium Production Centers,'' is included. Data on uranium raw materials activities including exploration activities and expenditures, resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities including domestic uranium purchases, commitments by utilities, procurement arrangements, uranium imports under purchase contracts and exports, deliveries to enrichment suppliers, inventories, secondary market activities, utility market requirements, and uranium for sale by domestic suppliers are presented in Chapter 2

Uranium Industry Annual, 1992

Energy Technology Data Exchange (ETDEWEB)

1993-10-28

The Uranium Industry Annual provides current statistical data on the US uranium industry for the Congress, Federal and State agencies, the uranium and electric utility industries, and the public. The feature article, ``Decommissioning of US Conventional Uranium Production Centers,`` is included. Data on uranium raw materials activities including exploration activities and expenditures, resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities including domestic uranium purchases, commitments by utilities, procurement arrangements, uranium imports under purchase contracts and exports, deliveries to enrichment suppliers, inventories, secondary market activities, utility market requirements, and uranium for sale by domestic suppliers are presented in Chapter 2.

Resources changes: a key factor in a new uranium production economic cycle

International Nuclear Information System (INIS)

Capus, G.; Caumartin, P.

1996-01-01

Since the end of 1994, a change has been underway in the uranium market. As usual in such cases, surprise and disbelief first dominated, but the market actors have been adjusting quickly to what now appears to be a return to primary production as the predominant factor in uranium supply. It is a matter of fact that the fundamentals will determine the course of the uranium market, as with other cyclical commodity markets. Comparing 1995 with 1975, a time of rocketing prices and production, and forecasting another cycle with similar characteristics to the last one is tempting, but illusory. However, examining the relative conditions prevailing at these times provides keys that may be helpful in understanding future developments. (author)

Accelerator based production of fissile nuclides, threshold uranium price and perspectives

International Nuclear Information System (INIS)

Djordjevic, D.; Knapp, V.

1988-01-01

Accelerator breeder system characteristics are considered in this work. One such system which produces fissile nuclides can supply several thermal reactors with fissile fuel, so this system becomes analogous to an uranium enrichment facility with difference that fissile nuclides are produced by conversion of U-238 rather than by separation from natural uranium. This concept, with other long-term perspective for fission technology on the basis of development only one simpler technology. The influence of basic system characteristics on threshold uranium price is examined. Conditions for economically acceptable production are established. (author)

Solubility classification of airborne products from uranium ores and tailings piles

International Nuclear Information System (INIS)

Kalkwarf, D.R.

1979-01-01

Airborne products generated at uranium mills were assigned solubility classifications for use in the ICRP Task Group Lung Model. No significant difference was seen between the dissolution behavior of airborne samples and sieved ground samples of the same product. If the product contained radionuclides that dissolved at different rates, composite classifications were assigned to show the solubility class of each component. If the dissolution data indicated that a radionuclide was present in two chemical forms that dissolved at different rates, a mixed classification was assigned to show the percentage of radionuclide in each solubility class. Uranium-ore dust was assigned the composite classification: ( 235 U, 238 U) W; ( 226 Ra) 10% D, 90% Y; ( 230 Th, 210 Pb, 210 Po) Y. Tailings-pile dust was classified: ( 226 Ra) 10% D, 90% Y; ( 230 Th, 210 Pb, 210 Po) Y. Uranium octoxide was classified Y, uranium tetrafluoride was also classified Y, ammonium diuranate was classified D, and yellow-cake dust was classified ( 235 U, 238 U) 60% D, 40% W. The term yellow cake, however, covers a variety of materials which differ significantly in dissolution rate. Solubility classifications based on the dissolution half-times of particular yellow-cake products should, thus, be used when available. The D, W, and Y classifications refer to biological half-times for clearance from the human respiratory tract of 0 to 10 days, 11 to 100 days, and > 100 days, respectively

Canadian resources of uranium and thorium

International Nuclear Information System (INIS)

Griffith, J.W.; Roscoe, S.M.

1964-01-01

Canada has been one of the world's leading producers of uranium since the metal became important as a raw material in the development and production of atomic energy. One of the largest known deposits in the world is in Canada where present reserves represent about 37 per cent of the total among those countries that have published reserve statistics. The production of uranium has been characterized by features which are unique in Canadian mining, because the industry was created by the government at a time of emergency and, unlike other minerals, the sale of its product is controlled by the state. The rapid growth of the uranium-mining industry since World War II has been a remarkable achievement. In 1958, Canada was the world's leading producer of uranium and the value of U 3 O 8 produced in both 1958 and 1959 exceeded the value of any other Canadian-produced metal. As an export commodity, uranium ranked fourth in value in 1959 following newsprint, wheat, and lumber. Production from 25 mines in that year was 14 462 tonnes of U 3 O 8 valued at $345 million (all monetary values are in U.S. dollars). Since 1959, however, the decline in production, resulting from declining export markets, has been almost as rapid as the spectacular rise from 1953 to 1959. At the end of 1963 only seven mines were in production and by the end of 1965 only two mines are expected to remain in operation. (author)

Underground Milling of High-Grade Uranium Ore

Energy Technology Data Exchange (ETDEWEB)

Edwards, C., E-mail: chuck.edwards@amec.com [AMEC Americas Limited, Saskatoon, Saskatchewan (Canada)

2014-05-15

There are many safety and technical issues involved in the mining and progressing of high grade uranium ores such as those exploited in Northern Canada at present. With more of this type of mine due to commence production in the near future, operators have been looking at ways to better manage the situation. The paper describes underground milling of high-grade uranium ore as a means of optimising production costs and managing safety issues. In addition the paper presents some examples of possible process flowsheets and plant layouts that could be applicable to such operations. Finally an assessment of potential benefits from underground milling from a variety of viewpoints is provided. (author)

Small cell experiments for electrolytic reduction of uranium oxides to uranium metal using fluoride salts

International Nuclear Information System (INIS)

Haas, P.A.; Adcock, P.W.; Coroneos, A.C.; Hendrix, D.E.

1994-01-01

Electrolytic reduction of uranium oxide was proposed for the preparation of uranium metal feed for the atomic vapor laser isotope separation (AVLIS) process. A laboratory cell of 25-cm ID was operated to obtain additional information in areas important to design and operation of a pilot plant cell. Reproducible test results and useful operating and control procedures were demonstrated. About 20 kg of uranium metal of acceptable purity were prepared. A good supply of dissolved UO 2 feed at the anode is the most important controlling requirement for efficient cell operation. A large fraction of the cell current is nonproductive in that it does not produce a metal product nor consume carbon anodes. All useful test conditions gave some reduction of UF 4 to produce CF 4 in addition to the reduction of UO 2 , but the fraction of metal from the reduction of UF 4 can be decreased by increasing the concentration of dissolved UO 2 . Operation of large continuous cells would probably be limited to current efficiencies of less than 60 pct, and more than 20 pct of the metal would result from the reduction of UF 4

Methods for the exploration and recovering of uranium

International Nuclear Information System (INIS)

Kegel, K.E.

1982-01-01

The uranium reserves in the western world occur basically in two types of deposits a) vein type and vein like types b) sedimentary types, with the vein deposits providing only 5 percent of the actual uranium production. 85% of the known uranium reserves in the western world, amounting to about 5 million metric tons U occur in a relatively small number of countries (U.S.A., Canada, Australia, South Africa and Namibia, France, Niger and Gabun). Exploration on uranium deposits is carried out by using geophysical and geochemical methods. Radiometry, i.e. the determination of the radioactivity of the ground in a prospective area, is the main geophysical tool. In the mining of uranium ores, practically all mining methods, applied in other metal mining branches, are being used. The benefication of uranium ore is characterized by a large up-grading factor (i.e. the ratio between the uranium content in the concentrates and the uranium content in the ore) which is higher than in most other metal mining operations. In the field of health and safety in uranium mines, the radiation protection of the workers plays a paramount role. Strict rules exist for maximum values of certain elements in waste air and waste water of uranium mining operations, emitted into the environment. (orig.)

Method of converting uranium fluoride to intermediate product for uranium oxide manufacture with recycling or reusing valuable materials

International Nuclear Information System (INIS)

Baran, V.; Moltasova, J.

1982-01-01

Uranium fluoride is acted upon by water with nitrate containing a cation capable of binding fluoride ions. The uranium is extracted, for instance, with tributyl phosphate with the generated organic phase containing the prevalent proportion of uranium and representing the required intermediate product and the aqueous phase from which is isolated the fluorine component which may be used within the fuel cycle. The nitrate component of the aqueous phase is recycled following treatment. It is also possible to act on uranium fluoride directly with an aqueous solution. Here the cations of nitrate form with the fluorides soluble nondissociated complexes and reduce the concentration of free fluoride ions. The nitrate +s mostly used in an amount corresponding to its solubility in the system prior to the introduction of UF 6 . The uranium from the solution with the reduced concentration of free fluoride ions is extracted into the reaction system under such conditions as to make the prevalent majority of fluorides and an amount of uranium smaller than 5x10 -2 mol/l remain in the aqueous phase and that such an amount of fluorides should remain in the organic phase which is smaller than corresponds to the fluorine/uranium molar ratio in the organic phase. Uranium contained in the organic phase is processed into uranium oxide, with advantage into UO 2 . From the isolated compounds of fluorine and the cation of the nitrate gaseous HF is released which is used either inside or outside of the fuel cycle. (J.P.)

Case study of forecasting uranium supply and demand

International Nuclear Information System (INIS)

Noritake, Kazumitsu

1992-01-01

PNC collects and analyzes information about uranium market trend, world uranium supply and demand, and world uranium resources potential in order to establish the strategy of uranium exploration. This paper outlines the results obtained to forecast uranium supply and demand. Our forecast indicates that 8,500 tU, accounting for one-sixth of the demand in the year 2001, must be met by uranium produced by mines to be newly developed. After 2019, demand cannot be met by the 123 mines currently in operation or expected to have gone into production by this year. The projected shortage must therefore be covered by uranium to be newly discovered. To preclude this occurrence, uranium exploration will have to be steadily continued in order to ensure future new uranium resources, to alleviate anxiety about future supply, and to prevent sharp price hikes. (author)

Evaluation of regional effects of effluents from uranium production in New Mexico

International Nuclear Information System (INIS)

Wilson, D.W.

1977-01-01

The Grants Uranium Region is a 2500 mile area of northcentral New Mexico which has produced about 40 percent of all domestic uranium, and holds over one-half of the current reserves. The increasing demand for uranium to fuel commercial nuclear power plants is resulting in rapid growth of the uranium industry and economic, social, and environmental changes are occurring. One of the environmental issues of this region is the concern for eventually unacceptable levels of air and water pollution from effluents from uranium mill tailings piles. This study addresses these potential impacts in relation to industrial environmental control practices, siting features, and other regional/temporal variables, including rates of production, locations and sizes of new mills, and population distributions

Uranium 2000 : International symposium on the process metallurgy of uranium

International Nuclear Information System (INIS)

Ozberk, E.; Oliver, A.J.

2000-01-01

The International Symposium on the Process Metallurgy of Uranium has been organized as the thirtieth annual meeting of the Hydrometallurgy Section of the Metallurgical Society of the Canadian Institute of Mining, Metallurgy and Petroleum (CIM). This meeting is jointly organized with the Canadian Mineral Processors Division of CIM. The proceedings are a collection of papers from fifteen countries covering the latest research, development, industrial practices and regulatory issues in uranium processing, providing a concise description of the state of this industry. Topics include: uranium industry overview; current milling operations; in-situ uranium mines and processing plants; uranium recovery and further processing; uranium leaching; uranium operations effluent water treatment; tailings disposal, water treatment and decommissioning; mine decommissioning; and international regulations and decommissioning. (author)

Development of uranium industry in Romania

International Nuclear Information System (INIS)

Iuhas, Tiberiu

2000-01-01

The management of the uranium resources is performed in Romania by the National Uranium Company. The tasks to be done are: 1. management and protection of rare and radioactive metal ores in the exploitation areas; 2. mining, preparation, refining and trading the radioactive ores, as well as reprocessing the uranium stock from the uranium concentrate in the national reserve; 3. performing geologic and technologic studies in the exploitation areas; 4. performing studies and projects concerning the maintenance of the present facilities and unearthing new ores; 5. building industrial facilities; 6. carrying out technological transport; 7. importation-exportation operations; 8. performing micro-production activity in experimental research units; 9. personnel training; 10. medical assistance for the personnel; 11. environment protection. The company is organized as follows: 1.three branches for uranium ore mining, located at Suceava, Bihor and Banat; 2. one branch for geologic survey, located at Magurele; 3. one branch for uranium ore preparation and concentration and for refining uranium concentrates, located at Feldioara; 4. One group for mine conservation, closure and ecology, located at Bucuresti. The final product, sintered powder of UO 2 produced at Feldioara plant, was tested in 1994 by the Canadian partner and met successfully the required standards. The Feldioara plant was certified as supplier of raw material for CANDU nuclear fuel production and as such, Romania is the only authorized producer of CANDU nuclear fuel in Europe and the second in the world, after Canada. Maintaining the uranium production in Romania is justified by the existence of uranium ore resources, the declining of natural gas resources, lower costs per kWh for electric nuclear power as compared to fossil-fuel power production, the possibility for Romania to become an important supplier of CANDU nuclear fuel, the low environmental impact and high costs for total shutdown of activity, high

New developments in uranium exploration, resources, production and demand

International Nuclear Information System (INIS)

1992-06-01

In view of the economic importance, the International Atomic Energy Agency and the Nuclear Energy Agency of the OECD have had a long standing interest in uranium exploration, resources, production and demand. It was the objective of this Technical Committee Meeting to bring together specialists in the field and to collect information on new developments, especially from countries which in the past considered uranium a strategic commodity and the related information as confidential or even secret. Separate abstracts were prepared for each of the 29 papers in this volume. Refs, figs, tabs, charts and maps

Uranium series geochemistry in aquifers: quantification of transport mechanisms of uranium and daughter products: the chalk aquifer (Champagne, France)

International Nuclear Information System (INIS)

Hubert, A.

2005-09-01

With the increase of contaminant flux of radionuclides in surface environment (soil, river, aquifer...), there is a need to understand and model the processes that control the distribution of uranium and its daughter products during transport within aquifers. We have used U-series disequilibria as an analogue for the transport of uranium and its daughter products in aquifer to understand such mechanisms. The measurements of uranium ( 234 U et 238 U), thorium ( 230 Th et 232 Th), 226 Ra and 222 Rn isotopes in the solid and liquid phases of the chalk aquifer in Champagne (East of France) allows us to understand the processes responsible for fractionation within the uranium decay chain. Fractionations are induced by physical and chemical properties of the elements (leaching, adsorption) but also by radioactive properties (recoil effect during α-decay). For the first time a comprehensive sampling of the solid phase has been performed, allowing quantifying mechanisms responsible for the long term evolution of the aquifer. A non steady state 1D model has been developed which takes into account leaching, adsorption processes as well as radioactive filiation and α-recoil effect. Retardation coefficients have been calculated for uranium, thorium and radium. The aquifer is characterised by a double porosity, and the contribution of fracture and matrix porosity on the water/rock interaction processes has been estimated. (author)

Restructuring of uranium industry in Romania

International Nuclear Information System (INIS)

Comsa, O; Meglea, C; Paraschiva, V.; Popescu, C.; Gheorghe, A.; Meglea, S.

2001-01-01

A project is described which aims at evaluation of uranium industry and assessment of the technical options for lowering production costs for uranium ore and, implicitly, for nuclear fuel. The main objective is defining the optimal technical and organisational solutions leading to a functional restructuring of this activity, as well as, to implementing modern techniques, technologies and procedures, and, at the same time to lowering the economical and environmental costs. This project is performed in co-operation with IAEA in the frame of TC-ROM/3/003, 'Restructuring the Uranium Mining Industry' project. The following results of carrying out this project are expected: refurbishment of processes and technological procedures, re-dimensioning uranium industry in accordance with the dimensions of nuclear power programme, reducing the environmental impact and lowering the uranium cost

The recovery of uranium, gold and sulphur from residues from South African mines

International Nuclear Information System (INIS)

Toens, P.D.

1978-10-01

The slimes dams resulting from the operations of gold and gold/uranium mines situated within the Witwatersrand Basin contain low concentrations of gold, uranium and pyrite. As a result of a marked increase in the prices of both gold and uranium in recent years, two schemes involving the recovery of these minerals also the manufacture of sulphuric acid as a by-product are operating profitably. Further schemes are under investigation [af

Deradiating the former uranium capital

International Nuclear Information System (INIS)

Merz, B.

1987-01-01

The city that once proclaimed itself The Uranium Capital of America is in the process of divorcing itself from the radioactive element - literally as well as symbolically. The last vestiges of uranium are being shoveled from the community. The removal is part of the federal Department of Energy's (DOE) Remedial Action program. It was established in 1972 to clean up areas of the country in which radiation exposure in excess of normal background levels could be attributed to wastes from DOE-operated uranium processing plants. Grand Junction was the first area to qualify. A good portion of the city is built on radioactive tailings - by-products of a uranium-processing industry. The DOE and the Environmental Protection Agency established guidelines for action levels of radiation. The standards were extrapolated from data from studies of lung cancer incidence in uranium miners in Europe and the US

The Y-12 National Security Complex Foreign Research Reactor Uranium Supply Production

Energy Technology Data Exchange (ETDEWEB)

Nelson, T. [Nuclear Technology and Nonproliferation Programs, B and W Y-12, L.L.C., Y-12 National Security Complex, Oak Ridge, Tennessee (United States); Keller, A.P. [Disposition and Supply Programs, B and W Y-12, L.L.C., Y-12 National Security Complex, Oak Ridge, Tennessee (United States)

2011-07-01

The Foreign Research Reactor (FRR) Uranium Supply Program at the Y-12 National Security Complex supports the nonproliferation objectives of the National Nuclear Security Administration (NNSA) HEU Disposition, the Reduced Enrichment Research and Test Reactors (RERTR), and the United States (U.S.) FRR Spent Nuclear Fuel (SNF) Acceptance Programs. The FRR Supply Program supports the important U.S. government nuclear nonproliferation commitment to serve as a reliable and cost-effective uranium supplier for those foreign research reactors that are converting or have converted to Low-Enriched Uranium (LEU) fuel under the RERTR Program. The NNSA Y-12 Site Office maintains the prime contracts with foreign government agencies for the supply of LEU for their research reactors. The LEU is produced by down blending Highly Enriched Uranium (HEU) that has been declared surplus to the U.S. national defense needs. The down blending and sale of the LEU supports the Surplus HEU Disposition Program Record of Decision to make the HEU non-weapons usable and to recover the economic value of the uranium to the extent feasible. In addition to uranium metal feedstock for fuel fabrication, Y-12 can produce LEU in different forms to support new fuel development or target fabrication for medical isotope production. With production improvements and efficient delivery preparations, Y-12 continues to successfully support the global research reactor community. (author)

Discussion for management of ventilation system in uranium mines

International Nuclear Information System (INIS)

Li Xianjie; Ren Jianjun; Hu Penghua

2014-01-01

Radon exhaustion and ventilation are surely regarded as key links for safety production and radiation protection in underground uranium mines, and the crucial point to achieve safety production goals lies in timely and accurately adjusting and controlling of ventilation technical measures and ventilation system management with the changing operation conditions of mines. This paper proposes corresponding countermeasures based on the respectively systematical analysis of daily ventilation management, ventilation facilities and structures management, and ventilation system information management in uranium mines. Furthermore, standardized management approaches and suggestions are put forward to realize standardization of uranium mines' ventilation management and radon exhaustion technique. (authors)

Uranium concentration monitor manual: 2300 system

International Nuclear Information System (INIS)

Russo, P.A.; Sprinkle, J.K. Jr.; Stephens, M.M.

1985-04-01

This manual describes the design, operation, and procedures for measurement control for the automated uranium concentration monitor on the 2300 solvent extraction system at the Oak Ridge Y-12 Plant. The nonintrusive monitor provides a near-real time readout of uranium concentration at two locations simultaneously in the solvent extraction system for process monitoring and control. Detectors installed at the top of the extraction column and at the bottom of the backwash column acquire spectra of gamma rays from the solvent extraction solutions in the columns. Pulse-height analysis of these spectra gives the concentration of uranium in the organic product of the extraction column and in the aqueous product of the solvent extraction system. The visual readouts of concentrations for process monitoring are updated every 2 min for both detection systems. Simultaneously, the concentration results are shipped to a remote computer that has been installed by Y-12 to demonstrate automatic control of the solvent extraction system based on input of near-real time process operation information. 8 refs., 13 figs., 4 tabs

Uranium mining

International Nuclear Information System (INIS)

Cheeseman, E.W.

1980-01-01

The international uranium market appears to be currently over-supplied with a resultant softening in prices. Buyers on the international market are unhappy about some of the restrictions placed on sales by the government, and Canadian sales may suffer as a result. About 64 percent of Canada's shipments come from five operating Ontario mines, with the balance from Saskatchewan. Several other properties will be producing within the next few years. In spite of the adverse effects of the Three Mile Island incident and the default by the T.V.A. of their contract, some 3 600 tonnes of new uranium sales were completed during the year. The price for uranium had stabilized at US $42 - $44 by mid 1979, but by early 1980 had softened somewhat. The year 1979 saw the completion of major environmental hearings in Ontario and Newfoundland and the start of the B.C. inquiry. Two more hearings are scheduled for Saskatchewan in 1980. The Elliot Lake uranium mining expansion hearings are reviewed, as are other recent hearings. In the production of uranium for nuclear fuel cycle, environmental matters are of major concern to the industry, the public and to governments. Research is being conducted to determine the most effective method for removing radium from tailings area effluents. Very stringent criteria are being drawn up by the regulatory agencies that must be met by the industry in order to obtain an operating licence from the AECB. These criteria cover seepages from the tailings basin and through the tailings retention dam, seismic stability, and both short and long term management of the tailings waste management area. (auth)

Development of the Alligator Rivers uranium deposits

International Nuclear Information System (INIS)

Bath, L.J.; Farthing, J.W.; Warner, R.K.

1980-01-01

The Alligator Rivers Uranium Province in the Northern Territory of Australia has proven uranium deposits at Jabiluka, Ranger, Koongarra and Nabarlek which contain more than 80% of the country's low-cost reasonably assured uranium resources estimated to be 290,000 t U. Following the Government's decision in 1977 to proceed with the further development of Australia's uranium resources, the region is destined to become a major producer of U 3 O 8 for export. At the time of the decision provision was made for strict controls to protect the environment, the granting of Aboriginal land rights and the creation of a major national park. The paper describes the progress made to achieve these objectives. The open-cut mining methods to be used at Ranger, Koongarra and Nabarlek are described, as well as the underground mining operations proposed for Jabiluka. Each of the treatment plants will use the conventional acid leach, solvent extraction purification process for uranium recovery. The characteristics of the treatment operations are outlined. The water-management schemes, tailings disposal methods and procedures for environment protection are also discussed. The proposed initial production capacities of the operations are: Jabiluka 2540 (expanding to 7630 in the fifth year of production); Ranger 2540 (expanding to 5080 when commercially practicable); Koongarra 850; and Nabarlek 920 t U/a. Both Nabarlek and Ranger have been granted Government development approval and construction is proceeding at each site with the expectation that normal commercial production will commence towards the end of 1980 and 1981, respectively. Planning for the Jabiluka and Koongarra projects has reached an advanced stage; each are undergoing environmental procedures and will have to reach agreement with the Aboriginals on environmental and other matters before site work can commence. (author)

Possibilities of using metal uranium fuel in heavy water reactors

International Nuclear Information System (INIS)

Djuric, B.; Mihajlovic, A.; Drobnjak, Dj.

1965-11-01

There are serious economic reasons for using metal uranium in heavy water reactors, because of its high density, i.e. high conversion factor, and low cost of fuel elements production. Most important disadvantages are swelling at high burnup and corrosion risk. Some design concepts and application of improved uranium obtained by alloying are promising for achievement of satisfactory stability of metal uranium under reactor operation conditions [sr

Resin-based preparation of HTGR fuels: operation of an engineering-scale uranium loading system

International Nuclear Information System (INIS)

Haas, P.A.

1977-10-01

The fuel particles for recycle of 233 U to High-Temperature Gas-Cooled Reactors are prepared from uranium-loaded carboxylic acid ion exchange resins which are subsequently carbonized, converted, and refabricated. The development and operation of individual items of equipment and of an integrated system are described for the resin-loading part of the process. This engineering-scale system was full scale with respect to a hot demonstration facility, but was operated with natural uranium. The feed uranium, which consisted of uranyl nitrate solution containing excess nitric acid, was loaded by exchange with resin in the hydrogen form. In order to obtain high loadings, the uranyl nitrate must be acid deficient; therefore, nitric acid was extracted by a liquid organic amine which was regenerated to discharge a NaNO 3 or NH 4 NO 3 solution waste. Water was removed from the uranyl nitrate solution by an evaporator that yielded condensate containing less than 0.5 ppM of uranium. The uranium-loaded resin was washed with condensate and dried to a controlled water content via microwave heating. The loading process was controlled via in-line measurements of the pH and density of the uranyl nitrate. The demonstrated capacity was 1 kg of uranium per hour for either batch loading contractors or a continuous column as the resin loading contractor. Fifty-four batch loading runs were made without a single failure of the process outlined in the chemical flowsheet or any evidence of inability to control the conditions dictated by the flowsheet

Irradiated uranium reprocessing

International Nuclear Information System (INIS)

Gal, I.

1961-12-01

Task concerned with reprocessing of irradiated uranium covered the following activities: implementing the method and constructing the cell for uranium dissolving; implementing the procedure for extraction of uranium, plutonium and fission products from radioactive uranium solutions; studying the possibilities for using inorganic ion exchangers and adsorbers for separation of U, Pu and fission products

The current situation of uranium mining in Hungary

International Nuclear Information System (INIS)

Erdi-Krausz, G.

1997-01-01

The paper describes the history of uranium production in Hungary. It focuses on the Mecsek Ore Mining Company, now known as Mecsekuran Limited, and its relationship with the Hungarian Government. From the start of uranium production in 1963 until May 1989 all production was exported to the Soviet Union under a bilateral contract. In exchange the Soviet Union agreed to provide fabricated fuel for the future Hungarian nuclear power plant. In May 1989 the Government of Hungary announced closure of its uranium mining operations because of the high cost of production. The paper describes the history of events since 1989, as well as the current plans to terminate all uranium production by 31 December 1997. The Mecsek Mountains lie in the southern part of Hungary, west from the Danube, about 30 km from the former Yugoslavian border, and north from the city of Pecs. Its eastern side is built up from medieval limestone and dolomites, while the western part is from sandstone and clay from the geological Paleozoic. In the eastern part high quality cokeable coal has been mined for more than 200 years, east from the city of Pecs; and in the western part uranium ore was discovered and the mining began only a few decades ago. (author)

Canadian resources of uranium and thorium

Energy Technology Data Exchange (ETDEWEB)

Griffith, J W; Roscoe, S M [Dept. of Mines and Technical Surveys, Ottawa, Ontario (Canada)

1964-07-01

Canada has been one of the world's leading producers of uranium since the metal became important as a raw material in the development and production of atomic energy. One of the largest known deposits in the world is in Canada where present reserves represent about 37 per cent of the total among those countries that have published reserve statistics. The production of uranium has been characterized by features which are unique in Canadian mining, because the industry was created by the government at a time of emergency and, unlike other minerals, the sale of its product is controlled by the state. The rapid growth of the uranium-mining industry since World War II has been a remarkable achievement. In 1958, Canada was the world's leading producer of uranium and the value of U{sub 3}O{sub 8} produced in both 1958 and 1959 exceeded the value of any other Canadian-produced metal. As an export commodity, uranium ranked fourth in value in 1959 following newsprint, wheat, and lumber. Production from 25 mines in that year was 14 462 tonnes of U{sub 3}O{sub 8} valued at $345 million (all monetary values are in U.S. dollars). Since 1959, however, the decline in production, resulting from declining export markets, has been almost as rapid as the spectacular rise from 1953 to 1959. At the end of 1963 only seven mines were in production and by the end of 1965 only two mines are expected to remain in operation. (author)

Rehabilitation of uranium tailings impoundments

International Nuclear Information System (INIS)

Crawley, A.H.

1983-01-01

Under Australian environmental controls relating to the management of uranium tailings, it is no longer acceptable practice to search for a rehabilitation strategy at the end of production when the generation of tailings has ceased. The uranium projects currently in production and those being proposed are tightly regulated by the authorities. The waste management plans must consider site specific factors and must include selection of appropriate disposal sites and design for long term containment. The final encapsulation in engineered facilities must take into account the probable routes to the environment of the tailings. Rehabilitation shoud be undertaken by the mining and milling operators to standards approved by appropriate authorities. Appropriate administrative arrangements are required, by way of technical committees and financial bonds to ensure that agreed standards of rehabilitation may be achieved. Past and present experience with the rehabilitation of uranium tailings impoundments in Australia is discussed

New route for uranium concentrate production from Caetite ore, Bahia State, Brazil; dynamic leaching - direct precipitation

Energy Technology Data Exchange (ETDEWEB)

Morais, Carlos A. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mail: cmorais@cdtn.br; Gomiero, Luiz A.; Scassiotti Filho, Walter [Industrias Nucleares do Brasil S.A. (INB), Caetite, BA (Brazil)]. E-mails: gomiero@inb.gov.br; scassiotti@inb.gov.br

2007-07-01

The common uranium concentrate production consists of ore leaching, uranium purification/concentration by solvent extraction and uranium precipitation as ammonium diuranate steps. In the present work, a new route of uranium concentrate production from Caetite, BA-Brazil ore was investigated. The following steps were investigated: dynamic leaching of the ground ore with sulfuric acid; sulfuric liquor pre-neutralization until pH 3.7; uranium peroxide precipitation. The study was carried out in bath and continuous circuits. In the dynamic leaching of ground ore in agitated tanks the uranium content in the leached ore may be as low as 100 {mu}g/g U{sub 3}O{sub 8}, depending on grinding size. In the pre-neutralization step, the iron content in the liquor is decreased in 99 wt.%, dropping from 3.62 g/L to 0.030 g/L. The sulfate content in the liquor reduces from 46 g/L to 22 g/L. A calcinated final product assaying 99.7 wt.% U{sub 3}O{sub 8} was obtained. The full process recovery was over 94%. (author)

Status Report from Australia [Processing of Low-Grade Uranium Ores

Energy Technology Data Exchange (ETDEWEB)

Stewart, J R [Australian Atomic Energy Commission, Coogee, NSW (Australia)

1967-06-15

During the period 1954-59, five plants for the production of uranium chemical concentrates (yellowcake) were constructed in Australia. Only one of these is in operation at the present time, but two more have been kept on a 'care-and-maintenance' basis pending revival of the market for uranium. The other two were disbanded after completion of contract production. Brief details of each of the plants are given.

Recovery of uranium in the production of concentrated phosphoric acid by a hemihydrate process

International Nuclear Information System (INIS)

Nakajima, S.; Miyamoto, M.

1983-01-01

Nissan Chemical Industries as manufacturers of phosphoric acid have studied the recovery of uranium, based on a concentrated phosphoric acid production process. The process consists of two stages, a hemihydrate stage with a formation of hemihydrate and a filtration section, followed by a dihydrate stage with hydration and a filtration section. In the hemihydrate stage, phosphate is treated with a mixture of phosphoric acid and sulphuric acid to produce phosphoric acid and hydrous calcium sulphate; the product is recovered in the filtration section and its concentration is 40-50% P 2 O 3 . In the dihydrate stage, the hemihydrate is transformed by re-dissolution and hydration, producing hydrous calcium sulphate, i.e. gypsum. This process therefore comprises two parts, each with different acid concentrations. As the extraction of uranium is easier in the case of a low concentration of phosphoric acid, the process consists of the recovery of uranium starting from the filtrate of the hydration section. The tests have shown that the yield of recovery of uranium was of the order of 80% disregarding the handling losses and no disadvantageous effect has been found in the combination of the process of uranium extraction with the process of concentrated phosphoric acid production. Compared with the classical process where uranium is recovered from acid with 30% P 2 O 5 , the process of producing high-concentration phosphoric acid such as the Nissan process, in which the uranium recovery is effected from acid with 15% P 2 O 5 from the hydration section, presents many advantages [fr

Reducing emissions from uranium dissolving

International Nuclear Information System (INIS)

Griffith, W.L.; Compere, A.L.; Huxtable, W.P.; Googin, J.M.

1992-10-01

This study was designed to assess the feasibility of decreasing NO x emissions from the current uranium alloy scrap tray dissolving facility. In the current process, uranium scrap is dissolved in boiling nitric acid in shallow stainless-steel trays. As scrap dissolves, more metal and more nitric acid are added to the tray by operating personnel. Safe geometry is assured by keeping liquid level at or below 5 cm, the depth of a safe infinite slab. The accountability batch control system provides additional protection against criticality. Both uranium and uranium alloys are dissolved. Nitric acid is recovered from the vapors for reuse. Metal nitrates are sent to uranium recovery. Brown NO x fumes evolved during dissolving have occasionally resulted in a visible plume from the trays. The fuming is most noticeable during startup and after addition of fresh acid to a tray. Present environmental regulations are expected to require control of brown NO x emissions. A detailed review of the literature, indicated the feasibility of slightly altering process chemistry to favor the production of NO 2 which can be scrubbed and recycled as nitric acid. Methods for controlling the process to manage offgas product distribution and to minimize chemical reaction hazards were also considered

International symposium on the uranium production cycle and the environment. Book of extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-10-01

This document contains 74 extended synopses of the presentations delivered at the meeting. The five sessions of the meeting covered various aspects of uranium mining and energy production including global aspects of sustainable development, uranium supply and nuclear energy; socio-economic and environmental impacts; safety considerations; production technology; waste management and decommissioning; and regulatory affairs. Each of the presentations was indexed separately.

International symposium on the uranium production cycle and the environment. Book of extended synopses

International Nuclear Information System (INIS)

2000-10-01

This document contains 74 extended synopses of the presentations delivered at the meeting. The five sessions of the meeting covered various aspects of uranium mining and energy production including global aspects of sustainable development, uranium supply and nuclear energy; socio-economic and environmental impacts; safety considerations; production technology; waste management and decommissioning; and regulatory affairs. Each of the presentations was indexed separately

A solvent proceed for the extraction of the irradiate uranium and plutonium in the reactor core; Un procede par solvant pour l'extraction du plutonium de l'uranium irradie dans les piles

Energy Technology Data Exchange (ETDEWEB)

Goldschmidt, B; Regnaut, P; Prevot, I [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

Description of the conditions of plutonium, fission products and of uranium separation by selective extraction of the nitrates by organic solvent, containing a simultaneous extraction of plutonium and uranium, followed by a plutonium re-extraction after reduction, and an uranium re-extraction. The rates of decontamination being insufficient in this first stage, we also describes the processes of decontamination permitting separately to get the rates wanted for uranium and plutonium. Finally, we describes the beginning of the operation that consists in a nitric dissolution of the active uranium while capturing the products of gaseous fission, as well as the final concentration of the products of fission in a concentrated solution. (authors) [French] Description des conditions de separation du plutonium, des produits de fission et de l'uranium au moyen d'une extraction selective des nitrates par solvant organique, comprenant une extraction simultanee du plutonium et de l'uranium, suivie d'une reextraction du plutonium apres reduction, et d'une reextraction de l'uranium. Les taux de decontamination etant insuffisants dans ce premier stade, on decrit egalement les processus de decontamination permettant separement d'obtenir les taux desires pour l'uranium et le plutonium. Enfin, on decrit aussi le debut de l'operation qui consiste en une dissolution nitrique de l'uranium actif en captant les produits de fission gazeux, ainsi que la concentration finale des produits de fission sous forme de solution concentree. (auteurs)

Uranium extraction at Rossing

International Nuclear Information System (INIS)

Kesler, S.B.; Fahrbach, D.O.E.

1982-01-01

Rossing Uranium Ltd. operates a large open pit uranium mine and extraction plant at a remote site in the Namib desert. Production started at the plant in 1978. A ferric leach process was introduced later, and the new leach plant began commissioning in October 1981. The process has proved to be reliable and easily controlled. Ferric iron is supplied through recovery from the acid plant calcine, and levels can be maintained above the design levels. Leach extractions were increased more than expected when this process was adopted, and the throughput has been considerably reduced, allowing cost savings in mining and milling

Method for converting uranium oxides to uranium metal

Science.gov (United States)

Duerksen, Walter K.

1988-01-01

A process is described for converting scrap and waste uranium oxide to uranium metal. The uranium oxide is sequentially reduced with a suitable reducing agent to a mixture of uranium metal and oxide products. The uranium metal is then converted to uranium hydride and the uranium hydride-containing mixture is then cooled to a temperature less than -100.degree. C. in an inert liquid which renders the uranium hydride ferromagnetic. The uranium hydride is then magnetically separated from the cooled mixture. The separated uranium hydride is readily converted to uranium metal by heating in an inert atmosphere. This process is environmentally acceptable and eliminates the use of hydrogen fluoride as well as the explosive conditions encountered in the previously employed bomb-reduction processes utilized for converting uranium oxides to uranium metal.

Recovery of uranium from crude uranium tetrafluoride

Energy Technology Data Exchange (ETDEWEB)

Ghosh, S K; Bellary, M P; Keni, V S [Chemical Engineering Division, Bhabha Atomic Research Centre, Mumbai (India)

1994-06-01

An innovative process has been developed for recovery of uranium from crude uranium tetrafluoride cake. The process is based on direct dissolution of uranium tetrafluoride in nitric acid in presence of aluminium hydroxide and use of solvent extraction for removal of fluorides and other bulk impurities to make uranium amenable for refining. It is a simple process requiring minimum process step and has advantage of lesser plant corrosion. This process can be applied for processing of uranium tetrafluoride generated from various sources like uranium by-product during thorium recovery from thorium concentrate, first stage product of uranium recovery from phosphoric acid by OPPA process and off grade uranium tetrafluoride material. The paper describes the details of the process developed and demonstrated on bench and pilot scale and its subsequent modification arising out of bulky solid waste generation. The modified process uses a lower quantity of aluminium hydroxide by allowing a lower dissolution of uranium per cycle and recycles the undissolved material to the next cycle, maintaining the overall recovery at high level. This innovation has reduced the solid waste generated by a factor of four at the cost of a slightly larger dissolution vessel and its increased corrosion rate. (author). 4 refs., 1 fig., 3 tabs.

Recovery of uranium from crude uranium tetrafluoride

International Nuclear Information System (INIS)

Ghosh, S.K.; Bellary, M.P.; Keni, V.S.

1994-01-01

An innovative process has been developed for recovery of uranium from crude uranium tetrafluoride cake. The process is based on direct dissolution of uranium tetrafluoride in nitric acid in presence of aluminium hydroxide and use of solvent extraction for removal of fluorides and other bulk impurities to make uranium amenable for refining. It is a simple process requiring minimum process step and has advantage of lesser plant corrosion. This process can be applied for processing of uranium tetrafluoride generated from various sources like uranium by-product during thorium recovery from thorium concentrate, first stage product of uranium recovery from phosphoric acid by OPPA process and off grade uranium tetrafluoride material. The paper describes the details of the process developed and demonstrated on bench and pilot scale and its subsequent modification arising out of bulky solid waste generation. The modified process uses a lower quantity of aluminium hydroxide by allowing a lower dissolution of uranium per cycle and recycles the undissolved material to the next cycle, maintaining the overall recovery at high level. This innovation has reduced the solid waste generated by a factor of four at the cost of a slightly larger dissolution vessel and its increased corrosion rate. (author)

Global Uranium Supply Ensured for Long Term, New Report Shows

International Nuclear Information System (INIS)

2012-01-01

(tU) at the end of 2010 to between 98 000 tU and 136 000 tU by 2035. The currently defined uranium resource base is more than adequate to meet high-case requirements through 2035 and well into the foreseeable future. Although ample resources are available, meeting projected demand will require timely investments in uranium production facilities. This is because of the long lead times (typically in the order of ten years or more in most producing countries) required to develop production facilities that can turn resources into refined uranium ready for nuclear fuel production. With uranium production ready to expand to new countries, efforts are being made to develop transparent and well-regulated operations similar to those used elsewhere to minimise potential environmental and local health impacts. Although not the primary focus of the Red Book, activity updates on the environmental aspects of the uranium production cycle are included in the national reports in this edition. While the status of supply and demand is considered from the perspective of technologies in use today, the deployment of advanced reactors and fuel cycle technologies can also positively affect the long-term availability of uranium, conceivably extending the time horizon of the currently defined resource base to thousands of years. These are some of the findings in the just-published Uranium 2011: Resources, Production and Demand, a joint study by the OECD/NEA and the IAEA, carried out in co-operation with their member countries. This is the 24th edition of this periodic assessment (currently every two years) which has been published since the mid-1960s. (IAEA)

Prediction of the net radon emission from a model open pit uranium mine

International Nuclear Information System (INIS)

Nielson, K.K.; Perkins, R.W.; Schwendiman, L.C.; Enderlin, W.I.

1979-09-01

Radon emission from a model open pit uranium mining operation has been estimated by applying radon exhalation fluxes measured in an open pit uranium mine to the various areas of the model mine. The model mine was defined by averaging uranium concentrations, mine dimensions, production and procedural statistics for eight major open pit uranium mines in the Casper, Wyoming area. The resulting emission rates were 630 Ci/RRY (1 RRY one = 1000-MW(e) reactor operating for 1 year) during mining operations and 26 Ci/RRY/y after abandoment of the mine assuming 100% recovery of U 3 O 8 from the ore, or 700 Ci/RRY and 29 Ci/RRY/y assuming 90.5% recovery

Uranium industry annual, 1991

International Nuclear Information System (INIS)

1992-10-01

In the Uranium Industry Annual 1991, data on uranium raw materials activities including exploration activities and expenditures, resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities including domestic uranium purchases, commitments by utilities, procurement arrangements, uranium imports under purchase contracts and exports, deliveries to enrichment suppliers, inventories, secondary market activities, utility market requirements, and uranium for sale by domestic suppliers are presented in Chapter 2. A feature article entitled ''The Uranium Industry of the Commonwealth of Independent States'' is included in this report

Conversion and Blending Facility highly enriched uranium to low enriched uranium as oxide. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-05

This Conversion and Blending Facility (CBF) will have two missions: (1) convert HEU materials into pure HEU oxide and (2) blend the pure HEU oxide with depleted and natural uranium oxide to produce an LWR grade LEU product. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. To the extent practical, the chemical and isotopic concentrations of blended LEU product will be held within the specifications required for LWR fuel. Such blended LEU product will be offered to the United States Enrichment Corporation (USEC) to be sold as feed material to the commercial nuclear industry. Otherwise, blended LEU will be produced as a waste suitable for storage or disposal.

Uranium supply analysis: Evolution of concepts

International Nuclear Information System (INIS)

Williams, R.M.

1998-01-01

Considerable effort has been expended during the last 15 years to develop improved methods of analysing current and future mineral supply, with the objectives of providing illustrations of mineral supply possibilities that are more meaningful and easily understood. Significant contributions toward these objectives have been made in the course of studies on world uranium supply, which took place in the 1970s prompted by concern about the future availability of mineral fuels. The Nuclear Energy Agency (NEA) of the Organization for Economic Co-operation and Development (OECD), and the International Atomic Energy Agency (IAEA) have played a key role in these efforts, through their biennial assessments of world uranium supply. There has been a pronounced shift in emphasis in the NEA/IAEA assessments away from resource estimates by themselves as a measure of supply, because of a growing awareness that, in isolation, resource estimates cannot provide a truly meaningful illustration of uranium availability. Indeed, resource estimates taken out of context can lead to false conclusions about resource adequacy. Successive NEA/IAEA studies have made increasing use of projections of production capability that show the possible availability of uranium from different categories of resources and production centres over specified time-frames. It is believed that such supply scenarios provide a much more meaningful illustration of uranium availability for both short and long-term planning purposes. As part of the effort to introduce such an approach to NEA/IAEA uranium supply analyses, the IAEA has prepared a manual which provides general guidelines for preparing projections of production capability. It is hoped that these efforts will contribute to a better understanding of the constraints on uranium supply and to the wider acceptance of projections of production capability as measures of resource adequacy. (author)

Continuing investigations for technology assessment of 99Mo production from LEU [low enriched Uranium] targets

International Nuclear Information System (INIS)

Vandergrift, G.F.; Kwok, J.D.; Marshall, S.L.; Vissers, D.R.; Matos, J.E.

1987-01-01

Currently much of the world's supply of /sup 99m/Tc for medical purposes is produced from 99 Mo derived from the fissioning of high enriched uranium (HEU). The need for /sup 99m/Tc is continuing to grow, especially in developing countries, where needs and national priorities call for internal production of 99 Mo. This paper presents the results of our continuing studies on the effects of substituting low enriched Uranium (LEU) for HEU in targets for the production of fission product 99 Mo. Improvements in the electrodeposition of thin films of uranium metal are reported. These improvements continue to increase the appeal for the substitution of LEU metal for HEU oxide films in cylindrical targets. The process is effective for targets fabricated from stainless steel or hastaloy. A cost estimate for setting up the necessary equipment to electrodeposit uranium metal on cylindrical targets is reported. Further investigations on the effect of LEU substitution on processing of these targets are also reported. Substitution of uranium silicides for the uranium-aluminum alloy or uranium aluminide dispersed fuel used in other current target designs will allow the substitution of LEU for HEU in these targets with equivalent 99 Mo-yield per target and no change in target geometries. However, this substitution will require modifications in current processing steps due to (1) the insolubility of uranium silicides in alkaline solutions and (2) the presence of significant quantities of silicate in solution. Results to date suggest that both concerns can be handled and that substitution of LEU for HEU can be achieved

REIMEP-22 inter-laboratory comparison: "U Age Dating - Determination of the production date of a uranium certified test sample"

OpenAIRE

VENCHIARUTTI CELIA; VARGA ZSOLT; RICHTER Stephan; JAKOPIC Rozle; MAYER Klaus; AREGBE Yetunde

2015-01-01

The REIMEP-22 inter-laboratory comparison aimed at determining the production date of a uranium certified test sample (i.e. the last chemical separation date of the material). Participants in REIMEP-22 on "U Age Dating - Determination of the production date of a uranium certified test sample" received one low-enriched 20 mg uranium sample for mass spectrometry measurements and/or one 50 mg uranium sample for D-spectrometry measurements, with an undisclosed value for the production date. They ...

In-situ uranium mining: reservoir engineering aspects of leaching and restoration

International Nuclear Information System (INIS)

Kabir, M.I.

1982-01-01

To establish the feasibility of in-situ mining of uranium, a push-pull test of an in-situ uranium leaching process, which consists of a single injection/production test well and two observation wells, was designed to evaluate the parameters which govern the uranium production and restorability of a solution mined zone. The test procedure itself consists of injection (push cycle) of a preflush followed by lixiviant, a brief soak period (soak cycle), and subsequent production (pull cycle) into the same well. Based on computer modeling, procedures are defined which permit, for a properly designed test, the determination of both restoration and leaching parameters. The test procedure and design recommendations are also outlined. Two numerical simulators which model field scale uranium production and restoration operations are presented. These simulators are able to accommodate various well patterns and irregular reservoir boundaries, physical dispersion, directional permeability variations (if present), and a variety of injection/production strategies. A streamline-concentration balance technique has been used to develop the models. The assumption of time invariant boundary conditions and no transverse dispersion between the streamlines reduces the two dimensional problem to a bundle of one dimensional ones. It has been further shown that the production well effluent histories can easily be obtained by superposing the solution of the concentration balance equations for a single streamline, and thus reducing computation time significantly. Finally, the simulators have been used to study various reservoir engineering aspects to optimize in-situ uranium production from field scale operations

In-situ uranium mining: reservoir engineering aspects of leaching and restoration

Energy Technology Data Exchange (ETDEWEB)

Kabir, M.I.

1982-01-01

To establish the feasibility of in-situ mining of uranium, a push-pull test of an in-situ uranium leaching process, which consists of a single injection/production test well and two observation wells, was designed to evaluate the parameters which govern the uranium production and restorability of a solution mined zone. The test procedure itself consists of injection (push cycle) of a preflush followed by lixiviant, a brief soak period (soak cycle), and subsequent production (pull cycle) into the same well. Based on computer modeling, procedures are defined which permit, for a properly designed test, the determination of both restoration and leaching parameters. The test procedure and design recommendations are also outlined. Two numerical simulators which model field scale uranium production and restoration operations are presented. These simulators are able to accommodate various well patterns and irregular reservoir boundaries, physical dispersion, directional permeability variations (if present), and a variety of injection/production strategies. A streamline-concentration balance technique has been used to develop the models. The assumption of time invariant boundary conditions and no transverse dispersion between the streamlines reduces the two dimensional problem to a bundle of one dimensional ones. It has been further shown that the production well effluent histories can easily be obtained by superposing the solution of the concentration balance equations for a single streamline, and thus reducing computation time significantly. Finally, the simulators have been used to study various reservoir engineering aspects to optimize in-situ uranium production from field scale operations.

Uranium

International Nuclear Information System (INIS)

1982-01-01

The development, prospecting, research, processing and marketing of South Africa's uranium industry and the national policies surrounding this industry form the headlines of this work. The geology of South Africa's uranium occurences and their positions, the processes used in the extraction of South Africa's uranium and the utilisation of uranium for power production as represented by the Koeberg nuclear power station near Cape Town are included in this publication

In situ leach uranium mining. Proceedings of a technical committee meeting. Working material

International Nuclear Information System (INIS)

2002-03-01

At the beginning of 1996 there were 437 nuclear power plants in operation with a combined electricity generating capacity of 344 GWe (net gigawatts electric). This represents nearly a 100% increase over the last decade. In 1995 over 2228 TWh (terawatt hours) electricity were generated, equivalent to about 17% of the world's total electricity. To achieve this, about 61 400 tonnes U were required as nuclear fuel. The 15 year decline of the spot uranium price, as indicated by Nuexco Exchange Value (NEV) and other indices, which reached an all time low annual average in 1994 of $18.33/kg U ($7.05/pound U 3 O 8 ), has had a profound impact on uranium related activities. This led to the massive reduction and realignment of all uranium related activities as the worldwide uranium market adjusted from over-production. Because of the economic advantages of properly run in situ leach technology on carefully selected uranium orebodies, relatively more ISL mining facilities have been kept in operation than conventional mining operations. In 1995 world uranium production of about 34 000 t uranium met only about 55% of world requirements. An estimated 16% of production came from ISL mining. In 1996 ISL mining was estimated to have produced over 5600 tU, or over 15% of estimated world production of 36 400 tU. The importance of ISL mining is expected to increase, as the technology has economic and environmental advantages for producing uranium from carefully selected deposits when projects are properly designed and operated by experienced personnel. Several countries host sandstone type uranium deposits, the only type where commercial ISL projects have been developed. ISL uranium mining technology was developed independently in the USA and the former Soviet Union and associated non-WOCA (world outside centrally planned economic areas) countries starting in the 1960s and 1970s. Since the opening of relations between the two areas in the early 1990s there has been a high level of

Are uranium resources sufficient to face the expected revival of nuclear electricity production in the world?

International Nuclear Information System (INIS)

Seyve, C.

2007-11-01

This article proposes a table containing assessments of uranium resources in 2005 in different countries, and comments the evolution of uranium prices between 1968 and 2008. It discusses whether it would be possible to cope with a dramatic increase of uranium prices, whether it would be already possible to save uranium with the same level of electricity production, whether there is still some uranium resources to be discovered, whether we could rely on non conventional uranium sources (phosphates, sea water), and the role of future reactors

International Training Centre, WNU — School of Uranium Production (Three Years Experience)

Energy Technology Data Exchange (ETDEWEB)

Trojáček, J., E-mail: trojacek@diamo.cz [WNU-SUP. DIAMO, Straz pod Ralskem (Czech Republic)

2014-05-15

Following a joint meeting of the IAEA, OECD/NEA Uranium Group and the World Nuclear Association, in 2004 the shortage of skilled professional staff to support the expansion of the global uranium industry was a major topic of discussion. As a consequence of the concerns expressed at that meeting, in 2006 the World Nuclear University-School of Uranium Production was set up with the cooperation of the DIAMO State Enterprise at their site in the Czech Republic. The facility is now up and running and provides a range of technical training activities to help strengthen the skills base amongst all uranium producing countries, both current and future. The paper describes the history of the school so far and the range of activities on offer. (author)

Inherently safe in situ uranium recovery

Science.gov (United States)

Krumhansl, James L; Brady, Patrick V

2014-04-29

An in situ recovery of uranium operation involves circulating reactive fluids through an underground uranium deposit. These fluids contain chemicals that dissolve the uranium ore. Uranium is recovered from the fluids after they are pumped back to the surface. Chemicals used to accomplish this include complexing agents that are organic, readily degradable, and/or have a predictable lifetime in an aquifer. Efficiency is increased through development of organic agents targeted to complexing tetravalent uranium rather than hexavalent uranium. The operation provides for in situ immobilization of some oxy-anion pollutants under oxidizing conditions as well as reducing conditions. The operation also artificially reestablishes reducing conditions on the aquifer after uranium recovery is completed. With the ability to have the impacted aquifer reliably remediated, the uranium recovery operation can be considered inherently safe.

Perceptions and Realities in Modern Uranium Mining - Extended Summary

International Nuclear Information System (INIS)

2014-01-01

Uranium mining and milling has evolved significantly over the years. By comparing currently leading approaches with outdated practices, the report demonstrates how uranium mining can be conducted in a way that protects workers, the public and the environment. Innovative, modern mining practices combined with strictly enforced regulatory standards are geared towards avoiding past mistakes made primarily during the early history of the industry when maximising uranium production was the principal operating consideration. Today's leading practices in uranium mining aim at producing uranium in an efficient and safe manner that limits environmental impacts to acceptable standards. As indicated in the report, the collection of baseline environmental data, environmental monitoring and public consultation throughout the life cycle of the mine enables verification that the facility is operating as planned, provides early warning of any potentially adverse impacts on the environment and keeps stakeholders informed of developments. Leading practice also supports planning for mine closure before mine production is licensed to ensure that the mining lease area is returned to an environmentally acceptable condition. The report highlights the importance of mine workers being properly trained and well equipped, as well as that of ensuring that their work environment is well ventilated so as to curtail exposure to radiation and hazardous materials and thereby minimise health impacts. (authors)

The structure of Canada's uranium industry and its future market prospects

International Nuclear Information System (INIS)

1981-01-01

Production of uranium in Canada began in the 1940s to supply the needs of US weapons development. After 1966 a growing demand for uranium for nuclear power production stimulated exploration, and since then the health of the Canadian uranium industry has been tied to the state of the nuclear power industry. Uranium exploration in Canada is carried out mainly by private enterprise, although the federal and two provincial governments compete through crown corporations. Seven companies produce ore, and six have processing plants. Expansion is underway at several existing operations, and some new projects are underway. The industry is strongly dependent on export markets; only about 15 percent of Canadian production is used in the country. There is one uranium refinery which produces UO 2 powder for CANDU reactor fuel and UF 6 for export. The uranium hexafluoride facility is being expanded. Federal government policy affects the uranium industry in the fields of regulation, ownership, safeguards, protection of the domestic industry, and international marketing. The short-term outlook for the industry is deteriorating, with declining uranium prices, but prospects seem considerably brighter in the longer term. Canada has about 12 percent of the world's uranium reserves, and is the second-largest producer. Discovery potential is believed to be excellent

Thorium and Uranium in the Rock Raw Materials Used For the Production of Building Materials

Science.gov (United States)

Pękala, Agnieszka

2017-10-01

Thorium and uranium are constant components of all soils and most minerals thereby rock raw materials. They belong to the particularly dangerous elements because of their natural radioactivity. Evaluation of the content of the radioactive elements in the rock raw materials seems to be necessary in the early stage of the raw material evaluation. The rock formations operated from deposits often are accumulated in landfills and slag heaps where the concentration of the radioactive elements can be many times higher than under natural conditions. In addition, this phenomenon may refer to buildings where rock raw materials are often the main components of the construction materials. The global control system of construction products draws particular attention to the elimination of used construction products containing excessive quantities of the natural radioactive elements. In the presented study were determined the content of thorium and uranium in rock raw materials coming from the Bełachatów lignite deposit. The Bełchatów lignite deposit extracts mainly lignite and secondary numerous accompanying minerals with the raw material importance. In the course of the field works within the framework of the carried out work has been tested 92 samples of rocks of varied petrographic composition. There were carried out analyses of the content of the radioactive elements for 50 samples of limestone of the Jurassic age, 18 samples of kaolinite clays, and 24 samples of siliceous raw materials, represented by opoka-rocks, diatomites, gaizes and clastic rocks. The measurement of content of the natural radioactive elements thorium and uranium based on measuring the frequency counts of gamma quantum, recorded separately in measuring channels. At the same time performed measurements on volume patterns radioactive: thorium and uranium. The studies were carried out in Mazar spectrometer on the powdered material. Standardly performed ten measuring cycles, after which were calculated

Department of Energy depleted uranium recycle

International Nuclear Information System (INIS)

Kosinski, F.E.; Butturini, W.G.; Kurtz, J.J.

1994-01-01

With its strategic supply of depleted uranium, the Department of Energy is studying reuse of the material in nuclear radiation shields, military hardware, and commercial applications. the study is expected to warrant a more detailed uranium recycle plan which would include consideration of a demonstration program and a program implementation decision. Such a program, if implemented, would become the largest nuclear material recycle program in the history of the Department of Energy. The bulk of the current inventory of depleted uranium is stored in 14-ton cylinders in the form of solid uranium hexafluoride (UF 6 ). The radioactive 235 U content has been reduced to a concentration of 0.2% to 0.4%. Present estimates indicate there are about 55,000 UF 6 -filled cylinders in inventory and planned operations will provide another 2,500 cylinders of depleted uranium each year. The United States government, under the auspices of the Department of Energy, considers the depleted uranium a highly-refined strategic resource of significant value. A possible utilization of a large portion of the depleted uranium inventory is as radiation shielding for spent reactor fuels and high-level radioactive waste. To this end, the Department of Energy study to-date has included a preliminary technical review to ascertain DOE chemical forms useful for commercial products. The presentation summarized the information including preliminary cost estimates. The status of commercial uranium processing is discussed. With a shrinking market, the number of chemical conversion and fabrication plants is reduced; however, the commercial capability does exist for chemical conversion of the UF 6 to the metal form and for the fabrication of uranium radiation shields and other uranium products. Department of Energy facilities no longer possess a capability for depleted uranium chemical conversion

Uranium industry annual 1996

International Nuclear Information System (INIS)

1997-04-01

The Uranium Industry Annual 1996 (UIA 1996) provides current statistical data on the US uranium industry's activities relating to uranium raw materials and uranium marketing. The UIA 1996 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. Data on uranium raw materials activities for 1987 through 1996 including exploration activities and expenditures, EIA-estimated reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities for 1994 through 2006, including purchases of uranium and enrichment services, enrichment feed deliveries, uranium fuel assemblies, filled and unfilled market requirements, uranium imports and exports, and uranium inventories are shown in Chapter 2. A feature article, The Role of Thorium in Nuclear Energy, is included. 24 figs., 56 tabs

Uranium industry annual 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

The Uranium Industry Annual 1996 (UIA 1996) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing. The UIA 1996 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. Data on uranium raw materials activities for 1987 through 1996 including exploration activities and expenditures, EIA-estimated reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities for 1994 through 2006, including purchases of uranium and enrichment services, enrichment feed deliveries, uranium fuel assemblies, filled and unfilled market requirements, uranium imports and exports, and uranium inventories are shown in Chapter 2. A feature article, The Role of Thorium in Nuclear Energy, is included. 24 figs., 56 tabs.

Uranium of Kazakhstan

International Nuclear Information System (INIS)

Tsalyuk, Yu.; Gurevich, D.

2000-01-01

Over 25 % of the world's uranium reserves are concentrated in Kazakhstan. So, the world's largest Shu-Sarysu uranium province is situated on southern Kazakhstan, with resources exceeding 1 billion tonnes of uranium. No less, than 3 unique deposits with resources exceeding 100,000 tonnes are situated here. From the economic point of view the most important thing is that these deposits are suitable for in-situ leaching, which is the cheapest, environmentally friendly and most efficient method available for uranium extracting. In 1997 the Kazatomprom National Joint-Stock Company united all Kazakhstan's uranium enterprises (3 mine and concentrating plants, Volkovgeologiya Joint-Stock Company and the Ulbinskij Metallurgical plant). In 1998 uranium production came to 1,500 tonnes (860 kg in 1997). In 1999 investment to the industry were about $ 30 million. Plans for development of Kazakhstan's uranium industry provide a significant role for foreign partners. At present, 2 large companies (Comeco (Canada), Cogema (France) working in Kazakhstan. Kazakatomprom continues to attract foreign investors. The company's administration announced that in that in next year they have plan to make a radical step: to sell 67 % of stocks to strategic investors (at present 100 % of stocks belongs to state). Authors of the article regard, that the Kazakhstan's uranium industry still has significant reserves to develop. Even if the scenario for the uranium industry could be unfavorable, uranium production in Kazakhstan may triple within the next three to four years. The processing of uranium by the Ulbinskij Metallurgical Plant and the production of some by-products, such as rhenium, vanadium and rare-earth elements, may provide more profits. Obviously, the sale of uranium (as well as of any other reserves) cannot make Kazakhstan a prosperous country. However, country's uranium industry has a god chance to become one of the most important and advanced sectors of national economy

Uranium hexafluoride handling. Proceedings

Energy Technology Data Exchange (ETDEWEB)

1991-12-31

The United States Department of Energy, Oak Ridge Field Office, and Martin Marietta Energy Systems, Inc., are co-sponsoring this Second International Conference on Uranium Hexafluoride Handling. The conference is offered as a forum for the exchange of information and concepts regarding the technical and regulatory issues and the safety aspects which relate to the handling of uranium hexafluoride. Through the papers presented here, we attempt not only to share technological advances and lessons learned, but also to demonstrate that we are concerned about the health and safety of our workers and the public, and are good stewards of the environment in which we all work and live. These proceedings are a compilation of the work of many experts in that phase of world-wide industry which comprises the nuclear fuel cycle. Their experience spans the entire range over which uranium hexafluoride is involved in the fuel cycle, from the production of UF{sub 6} from the naturally-occurring oxide to its re-conversion to oxide for reactor fuels. The papers furnish insights into the chemical, physical, and nuclear properties of uranium hexafluoride as they influence its transport, storage, and the design and operation of plant-scale facilities for production, processing, and conversion to oxide. The papers demonstrate, in an industry often cited for its excellent safety record, continuing efforts to further improve safety in all areas of handling uranium hexafluoride. Selected papers were processed separately for inclusion in the Energy Science and Technology Database.

Operational status of the uranium beam upgrade of the ATLAS accelerator

International Nuclear Information System (INIS)

Pardo, R.C.; Bollinger, L.M.; Nolen, J.A.

1993-01-01

The Positive-Ion Injector (PII) for ATLAS is complete. First beams from the new injector have been accelerated and used for experiments at ATLAS. The PH consists of an ECR ion source on a 350-kV platform and a low-velocity superconducting linac. The first acceleration of uranium for the experimental program has demonstrated the design goals of the project have been met. Since the summer of 1992, the new injecter has been used for the research program approximately 50% of the time. Longitudinal beam quality from the new injector has been measured to be significantly better than comparable beams from the tandem injecter. Changes to the mix of resonators in the main ATLAS accelerator to match better the velocity profile for heavy beams such as uranium are nearly complete and uranium energies up to 6.45 MeV per nucleon have been achieved. The operating experience of the new ATLAS facility will be discussed with emphasis on the measured beam quality as well as achieved beam energies and currents

The separation of plutonium from uranium and fission products on zirconium phosphate columns

Energy Technology Data Exchange (ETDEWEB)

Gal, I; Ruvarac, A [Institute of Nuclear Sciences Boris Kidric, Laboratorija za visoku aktivnost, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

In recent years special attention has been given to the ion-exchange properties of zirconium phosphate and similar compounds in aqueous solutions. These inorganic cation exchangers are stable in oxidizing media and at elevated temperatures. Their resistance to ionizing radiation makes them particularly suitable for work with radioactive solutions. On account of this we considered ir worthwhile to investigate the separation of plutonium from uranium and fission products on zirconium phosphate columns. We were interested in nitric and solutions containing macro-amounts of uranium (a few grams per litre), and micro-amounts of plutonium and long-lived fission products. To obtain a better insight into the ion-exchange behaviour of the different ionic species towards zirconium phosphate, we first determined the dependence of the distribution coefficients of uranium, plutonium and fission product cations on the aqueous nitric acid concentration. Then, taking the distribution data as a guide, we separated plutonium on small glass columns filled with zirconium phosphate and calculated the decontamination factors (author)

Draft environment statement related to operation of Moab uranium mill (Grand County, Utah)

International Nuclear Information System (INIS)

1977-11-01

This draft environmental impact statement was prepared by the staff of the U.S. Nuclear Regulatory Commission and issued by the Commission's Office of Nuclear Material Safety and Safeguards. The proposed action is the continuation of Source Material License SUA-917 issued to Atlas Corporation for the operation of the Atlas Uranium Mill in Grand County, Utah, near Moab (Docket No. 40-3453). This authorizes a 600-ton (450-MT) per day acid leach circuit (for recovery of vanadium as well as uranium) and a 600-ton (450-MT) per day alkaline leach circuit

Uranium

International Nuclear Information System (INIS)

Mackay, G.A.

1978-01-01

The author discusses the contribution made by various energy sources in the production of electricity. Estimates are made of the future nuclear contribution, the future demand for uranium and future sales of Australian uranium. Nuclear power growth in the United States, Japan and Western Europe is discussed. The present status of the six major Australian uranium deposits (Ranger, Jabiluka, Nabarlek, Koongarra, Yeelerrie and Beverley) is given. Australian legislation relevant to the uranium mining industry is also outlined

Uranium industry annual, 1986

International Nuclear Information System (INIS)

1987-01-01

Uranium industry data collected in the EIA-858 survey provide a comprehensive statistical characterization of annual activities of the industry and include some information about industry plans over the next several years. This report consists of two major sections. The first addresses uranium raw materials activities and covers the following topics: exploration activities and expenditures, resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment. The second major section is concerned with the following uranium marketing activities: uranium purchase commitments, uranium prices, procurement arrangements, uranium imports and exports, enrichment services, inventories, secondary market activities utility market requirements and related topics

Uranium market

International Nuclear Information System (INIS)

Rubini, L.A.; Asem, M.A.D.

1990-01-01

The historical development of the uranium market is present in two periods: The initial period 1947-1970 and from 1970 onwards, with the establishment of a commercial market. The world uranium requirements are derived from the corresponding forecast of nuclear generating capacity, with, particular emphasis to the brazilian requirements. The forecast of uranium production until the year 2000 is presented considering existing inventories and the already committed demand. The balance between production and requirements is analysed. Finally the types of contracts currently being used and the development of uranium prices in the world market are considered. (author)

Continuing investigations for technology assessment of 99Mo production from LEU [low enriched uranium] targets

International Nuclear Information System (INIS)

Vandegrift, G.F.; Kwok, J.D.; Marshall, S.L.; Vissers, D.R.; Matos, J.E.

1987-01-01

Currently much of the world's supply of 99m Tc for medical purposes is produced from 99 Mo derived from the fissioning of high enriched uranium (HEU). This paper presents the results of our continuing studies on the effects of substituting low enriched uranium (LEU) for HEU in targets for the production of fission product 99 Mo. Improvements in the electrodeposition of thin films of uranium metal continue to increase the appeal for the substitution of LEU metal for HEU oxide films in cylindrical targets. The process is effective for targets fabricated from stainless steel or zircaloy. Included is a cost estimate for setting up the necessary equipment to electrodeposit uranium metal on cylindrical targets. Further investigations on the effect of LEU substitution on processing of these targets are also reported. Substitution of uranium silicides for the uranium-aluminium alloy or uranium aluminide dispersed fuel used in current target designs will allow the substitution of LEU for HEU in these targets with equivalent 99 Mo-yield per target and no change in target geometries. However, this substitution will require modifications in current processing steps due to 1) the insolubility of uranium silicides in alkaline solutions and 2) the presence of significant quantities of silicate in solution. Results to date suggest that substitution of LEU for HEU can be achieved. (Author)

The balance of uranium supply and demand to 1990

International Nuclear Information System (INIS)

Erkes, P.

1980-01-01

The subject is discussed under the following headings: lead times in the nuclear industry; short term flexibilities -impact on demand of changes in tails assay and effect on supply of changed operating characteristics; supply-demand balance (Uranium Institute methodology); installed nuclear capacity forecast; enrichment capacity forecast; uranium production projections; estimates of uranium supply and demand until 1990; the effect of stockpiling; recent influences on the supply and demand balance; the Harrisburg experience; the International Fuel Cycle Evaluation (INFCE); the oil price spiral; conclusions. (U.K.)

Simulation of a flowing bed kiln for the production of uranium tetrafluoride; Simulation d'un four a lit coulant pour la production de tetrafluorure d'uranium

Energy Technology Data Exchange (ETDEWEB)

Dussoubs, B.; Patisson, F.; Ablitzer, D. [Ecole des Mines de Nancy, Lab. de Science et Genie des Materiaux et de Metallurgie, UMR 7584, 54 (France); Jourde, J. [Comurhex, Usine de Malvesi, 11 - Narbonne (France); Houzelot, J.L. [Ecole Nationale Superieure des Industries Chimiques (ENSIC), UPR 6811, 54 - Villers-les-Nancy (France)

2001-07-01

A flowing bed kiln is a gas-solid reactor used in the civil nuclear fuel cycle for the successive conversion of uranium trioxide (UO{sub 3}) into uranium dioxide (UO{sub 2}) and then into uranium tetrafluoride (UF{sub 4}). A numerical model is developed which simulate the behaviour of this reactor in permanent regime. This model describes the physico-chemical phenomena involved, and combines a mechanistic approach in the vertical area of the kiln (resolution by the finite volumes method) and a systemic approach in the horizontal area, like in the model of cascade mixers. The first results have been obtained for reference operating conditions of the industrial kiln. Some possible improvements of the optimum temperature progression inside the kiln are evoked. (J.S.)

Data base for a CANDU-PHW operating on a once-through natural uranium cycle

International Nuclear Information System (INIS)

1979-07-01

This report, prepared for INFCE, describes a standard 600 MW(e) CANDU-PHW reactor operating on a once-through natural uranium fuel cycle. Subsequently, data are given for an extrapolated 1000 MW(e) design (the nominal capacity adopted for the INFCE study) operating on the same fuel cycle. (author)

Uranium industry annual 1985

International Nuclear Information System (INIS)

1986-11-01

This report consists of two major sections. The first addresses uranium raw materials activities and covers the following topics: exploration activities and expenditures, resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment. The second major section is concerned with the following uranium marketing activities: uranium purchase commitments, uranium prices, procurement arrangements, uranium imports and exports, enrichment services, inventories, secondary market activities, utility market requirements, and related topics. A glossary and appendices are included to assist the reader in interpreting the substantial array of statistical data in this report and to provide background information about the survey