A new automatic analyzer for uranium determination

International Nuclear Information System (INIS)

Xia Buyun; Zhu Yaokun; Wang Bin; Cong Peiyan; Zhang Lan

1992-08-01

An intellectual automatic analyzer for uranium based on the principle of flow injection analysis (FIA) has been developed. It can directly determine the uranium solution in range of 0.02 to 500 mg/L without any pre-process. A chromatographic column with extractant, in which the trace uranium is concentrated and separated, has special ability to enrich uranium, is connected to the manifold of the analyzer. The analyzer is suited for trace uranium determination in varies samples. The 2-(5-bromo-2-pyridylazo)-5-diethyl-aminophenol (Br-PADAP) is used as color reagent. Uranium is determined in aqueous solution by adding cation surfactant, cetyl-pyridinium bromide (PCB). The rate of analysis is 30 to 90 samples per hour. The relative standard deviation of determination is 1% ∼ 2%. The analyzer has been used in factories and laboratory, and the results are satisfied. The determination range can easily be changed by using a multi-function auto-injection valve that changes the injection volume of the sample and channels. So, it could adopt varies FIA operation modes to meet the needs of FIA determination for other substance. The analyzer has universal functions

Uranium Newsletter. No. 1

International Nuclear Information System (INIS)

1987-03-01

The new Uranium Newsletter is presented as an IAEA annual newsletter. The organization of the IAEA and its involvement with uranium since its founding in 1957 is described. The ''Red Book'' (Uranium Resources, Production and Demand) is mentioned. The Technical Assistance Programme of the IAEA in this field is also briefly mentioned. The contents also include information on the following meetings: The Technical Committee Meeting on Uranium Deposits in Magmatic and Metamorphic Rocks, Advisory Group Meeting on the Use of Airborne Radiometric Data, and the Technical Committee Meeting on Metallogenesis. Recent publications are listed. Current research contracts in uranium exploration are mentioned. IAEA publications on uranium (in press) are listed also. Country reports from the following countries are included: Australia, Brazil, Canada, China (People's Republic of), Denmark, Finland, Germany (Federal Republic of), Malaysia, Philippines, Portugal, South Africa (Republic of), Spain, Syrian Arab Republic, United Kingdom, United States of America, Zambia, and Greece. There is also a report from the Commission of European Communities

Technologies for the treatment of effluents from uranium mines, mills and tailings. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2002-06-01

Effluent treatment is an important aspect of uranium mining and milling operations that continues through decommissioning and site rehabilitation. During the life of a mine, effluent treatment is an integral part of the operation with all effluent either being recycled to the mill or processed through a water treatment plant before being released into the environment. During decommissioning and rehabilitation, effluent treatment must continue either through a water treatment plant of by using passive treatment techniques. Because of the recent closing of several uranium mines or mining districts, particularly in eastern Europe, effluent treatment is becoming an ever increasing concern. Therefore the IAEA convened a technical committee meeting (TCM) so that experts from different countries could discuss information and knowledge on effluent treatment processes and methods. The papers presented at the meeting describe techniques for treatment of effluents from uranium production operations - both past and present. This publication contains ten papers presented at the meeting; each of the papers was indexed separately

Recent developments in uranium resources and production with emphasis on in situ leach mining. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2004-06-01

An important role of the International Atomic Energy Agency is establishing contacts between Member States in order to foster the exchange of scientific and technical information on uranium production technologies. In situ leach (ISL) mining is defined as, the extraction of uranium from the host sandstone by chemical solutions and the recovery of uranium at the surface. ISL extraction is conducted by injecting a suitable leach solution into the ore zone below the water table; oxidizing, complexing, and mobilizing the uranium; recovering the pregnant solutions through production wells; and, finally, pumping the uranium bearing solution to the surface for further processing. As compared with conventional mining, in situ leach is recognized as having economic and environmental advantages when properly employed by knowledgeable specialists to extract uranium from suitable sandstone type deposits. Despite its limited applicability to specific types of uranium deposits, in recent years ISL uranium mining has been producing 15 to 21 per cent of world output. In 2002, ISL production was achieved in Australia, China, Kazakhstan, the United States of America and Uzbekistan. Its importance is expected to increase with new projects in Australia, China, Kazakhstan and the Russian Federation. The Technical Meeting on Recent Development in Uranium Resources and Production with Special Emphasis on In Situ Leach Mining, was held in Beijing from 18 to 20 September 2002, followed by the visit of the Yili ISL mine, Xinjiang Autonomous Region, China, from 21 to 23 September 2002. The meeting, held in cooperation with the Bureau of Geology, China National Nuclear Cooperation, was successful in bringing together 59 specialists representing 18 member states and one international organization (OECD/Nuclear Energy Agency). The papers describe a wide variety of activities related to the theme of the meeting. Subjects such as geology, resources evaluation, licensing, and mine restoration were

Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

The International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended holding a Technical Committee Meeting on Water Channel Reactor Fuel including into this category fuels and pressure tubes/fuel channels for Atucha-I and II, BWR, CANDU, FUGEN and RBMK reactors. The IWGFPT considered that even if the characteristics of Atucha, CANDUs, BWRs, FUGEN and RBMKs differ considerably, there are also common features. These features include materials aspects, as well as core, fuel assembly and fuel rod design, and some safety issues. There is also some similarity in fuel power history and operating conditions (Atucha-I and II, FUGEN and RBMK). Experts from 11 countries participated at the meeting and presented papers on technology, performance, safety and design, and materials aspects of fuels and pressure tubes/fuel channels for the above types of water channel reactors. Refs, figs, tabs.

Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1998-01-01

The International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended holding a Technical Committee Meeting on Water Channel Reactor Fuel including into this category fuels and pressure tubes/fuel channels for Atucha-I and II, BWR, CANDU, FUGEN and RBMK reactors. The IWGFPT considered that even if the characteristics of Atucha, CANDUs, BWRs, FUGEN and RBMKs differ considerably, there are also common features. These features include materials aspects, as well as core, fuel assembly and fuel rod design, and some safety issues. There is also some similarity in fuel power history and operating conditions (Atucha-I and II, FUGEN and RBMK). Experts from 11 countries participated at the meeting and presented papers on technology, performance, safety and design, and materials aspects of fuels and pressure tubes/fuel channels for the above types of water channel reactors

Classification of uranium reserves/resources

International Nuclear Information System (INIS)

1998-08-01

Projections of future availability of uranium to meet present and future nuclear power requirements depend on the reliability of uranium resource estimates. Lack of harmony of the definition of the different classes of uranium reserves and resources between countries makes the compilation and analysis of such information difficult. The problem was accentuated in the early 1990s with the entry of uranium producing countries from the former Soviet Union, eastern Europe and China into the world uranium supply market. The need for an internationally acceptable reserve/resource classification system and terminology using market based criteria is therefore obvious. This publication was compiled from participant's contributions and findings of the Consultants Meetings on Harmonization of Uranium Resource Assessment Concepts held in Vienna from 22 to 25 June 1992, and two Consultants Meetings on the Development of a More Meaningful Classification of Uranium Resources held in Kiev, Ukraine on 24-26 April 1995 and 20-23 August 1996. This document includes 11 contributions, summary, list of participants of the Consultants Meetings. Each contribution has been indexed and provided with an abstract

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

Management of wastes from the refining and conversion of uranium ore concentrate to uranium hexafluoride

International Nuclear Information System (INIS)

1981-01-01

This report is the outcome of an IAEA Advisory Group Meeting on ''Waste Management Aspects in Relation to the Refining of Uranium Ore Concentrates and their Conversion to Uranium Hexafluoride'', which was held in Vienna from 17 to 21 December 1979. The report summarizes the main topics discussed at the meeting and gives an overview of uranium refining processes, being used in nuclear industry. The meeting was organized by the International Atomic Energy Agency, Radioactive Waste Management Section

Planning and management of uranium mine and mill closures. Proceedings of a technical committee meeting held in Liberec, Czech Republic, 3-6 May 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Technical Committee Meeting on Planning and Management of Uranium Mine and Mill Closures was held in Liberec, Czech Republic from 3 to 6 May 1994. A total of 30 participants from nine countries attended the meeting. Nineteen papers were presented. Most of these papers dealt with the concept of and experiences in planning for and the subsequent decommissioning and rehabilitation of uranium mines and mills in Australia, Canada, Czech Republic, Germany, Romania, Slovenia, Spain and the USA. Two papers discussed the government`s role and relevant regulations related to the closures, decommissioning and remediation of uranium production facilities. Of particular interest to the participants was a non-technical paper presented by the Mayor of the city of Andujar, Spain, describing the negative political and socio-economic impacts associated with closure and decommissioning of an uranium mine/mill facility. The highlights of the meeting were the field visits to the uranium production facilities and rehabilitation programme sites of DIAMO and WISMUT companies, located respectively in Straz, Czech Republic and Koenigstein, Germany. Refs, figs and tabs.

Channel sandstone and bar morphology of the Beaufort group uranium district near Beaufort West

International Nuclear Information System (INIS)

Stear, W.M.

1980-01-01

Sheet-like and lenticular sandstone bodies in the Lower Beaufort Group (Adelaide Subgroup) uranium district occur in megacyclic repetition as superimposed systems of ephemeral fluvial channels that display characteristics of complex lateral and vertical accretion. Channel sandstone bodies are defined on morphological grounds into two types. Sheet sandstone bodies are the commonest type and comprise the bulk of sandstone packages in arenaceous zones of megacycles. Composite sandstone sheets result from multilateral coalescence of individual sandstone bodies. Isolated lenticular sandstone units in argillaceous zones of megacycles comprise sheet and ribbon sandstone types. Multi-storeying is a prominent feature of most channel sandstone bodies and often results in local sandstone thickening. Bedforms relate to the formation of compound bars and record periods of dynamic accretion and erosion. Rarely preserved palaeosurfaces vividly illustrate the fluctuating hydrodynamic conditions that typified ephemeral fluvial sedimentation in a semi-arid environment during Lower Beaufort times

Channel sandstone and bar morphology of the Beaufort group uranium district near Beaufort West

Energy Technology Data Exchange (ETDEWEB)

Stear, W M

1980-01-01

Sheet-like and lenticular sandstone bodies in the Lower Beaufort Group (Adelaide Subgroup) uranium district occur in megacyclic repetition as superimposed systems of ephemeral fluvial channels that display characteristics of complex lateral and vertical accretion. Channel sandstone bodies are defined on morphological grounds into two types. Sheet sandstone bodies are the commonest type and comprise the bulk of sandstone packages in arenaceous zones of megacycles. Composite sandstone sheets result from multilateral coalescence of individual sandstone bodies. Isolated lenticular sandstone units in argillaceous zones of megacycles comprise sheet and ribbon sandstone types. Multi-storeying is a prominent feature of most channel sandstone bodies and often results in local sandstone thickening. Bedforms relate to the formation of compound bars and record periods of dynamic accretion and erosion. Rarely preserved palaeosurfaces vividly illustrate the fluctuating hydrodynamic conditions that typified ephemeral fluvial sedimentation in a semi-arid environment during Lower Beaufort times.

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...

Meeting of the French geological society - Uranium: geology, geophysics, chemistry. Book of abstracts

International Nuclear Information System (INIS)

Zakari, A.A.; Mima, S.; Bidaud, A.; Criqui, P.; Menanteau, P.; David, S.; Pagel, M.; Chagnes, A.; Cote, G.; Courtaud, B.; Thiry, J.; Miehe, J.M.; Gilbert, F.; Cuney, M.; Bruneton, P.; Ewington, D.; Vautrin-Ul, C.; Cannizzo, C.; Betelu, S.; Chausse, A.; Ly, J.; Bourgeois, D.; Maynadie, J.; Meyer, D.; Clavier, N.; Costin, D.T.; Cretaz, F.; Szenknect, S.; Ravaux, J.; Poinssot, C.; Dacheux, N.; Durupt, N.; Blanvillain, J.J.; Geffroy, F.; Aparicio, B.; Dubessy, J.; Nguyen-Trung, C.; Robert, P.; Uri, F.; Beaufort, D.; Lescuyer, J.L.; Morichon, E.; Allard, T.; Milesi, J.P.; Richard, A.; Rozsypal, C.; Mercadier, J.; Banks, D.A.; Boiron, M.C.; Cathelineau, M.; Dardel, J.; Billon, S.; Patrier, P.; Wattinne, A.; Vanderhaeghe, O.; Fabre, C.; Castillo, M.; Salvi, S.; Beziat, D.; Williams-Jones, A.E.; Trap, P.; Durand, C.; Goncalves, P.; Marquer, D.; Feybesse, J.L.; Richard, Y.; Orberger, B.; Hofmann, A.; Megneng, M.; Orberger, B.; Bouttemy, M.; Vigneron, J.; Etcheberry, A.; Perdicakis, M.; Prignon, N.; Toe, W.; Andre-Mayer, A.S.; Eglinger, A.; Jordaan, T.; Hocquet, S.; Ledru, P.; Selezneva, V.; Vendryes, G.; Lach, P.; Cuney, M.; Mercadier, J.; Brouand, M.; Duran, C.; Seydoux-Guillaume, A.M.; Bingen, B.; Parseval, P. de; Guillaume, D.; Bosse, V.; Paquette, J.L.; Ingrin, J.; Montel, J.M.; Giot, R.; Maucotel, F.; Hubert, S.; Gautheron, C.; Tassan-Got, L.; Pagel, M.; Barbarand, J.; Cuney, M.; Lach, P.; Bonhoure, J.; Leisen, M.; Kister, P.; Salaun, A.; Villemant, B.; Gerard, M.; Komorowski, J.C.; Michel, A.; Riegler, T.; Tartese, R.; Boulvais, P.; Poujols, M.; Gloaguen, E.; Mazzanti, M.; Mougel, V.; Nocton, G.; Biswas, B.; Pecaut, J.; Othmane, G.; Menguy, N.; Vercouter, T.; Morin, G.; Galoisy, L.; Calas, G.; Fayek, M.

2010-11-01

This document brings together the abstracts of the 39 presentations given at this meeting days on uranium, organized by the French geological society, and dealing with: 1 - Prospective study of the electronuclear technological transition; 2 - The front-end of the nuclear cycle: from the molecule to the process; 3 - Geophysics: recent changes; 4 - Use of well logging in uranium exploration; 5 - Genetical classification of thorium deposits; 6 - Genetical nomenclature of uranium sources; 7 - Uranium deposits linked to a Proterozoic discordance - retrospective; 8 - The use of spectral analysis techniques in uranium exploration: real-time mapping of clay alteration features; 9 - Development of functionalized silk-screened carbon electrodes for the analysis of uranium trace amounts; 10 - Study of the actinides solvation sphere in organic environment; 11 - Thermodynamic of uraniferous phases of interest for the nuclear cycle; 12 - Heap leaching of marginal minerals at Somair: from lab studies to the production of 700 t of uranium/year; 13 - Agglomeration phenomenology and role of iron in uranium heap leaching; 14 - Chloride uranyl complexes up to 300 deg. C along the saturation vapour curve: Raman spectroscopy analysis and metallogenic consequences; 15 - Weathering systems in the Shea Creek deposit (Athabasca, Canada): vertical variability of argillaceous weathering; 16 - Weathering systems in the Shea Creek deposit (Athabasca, Canada): contribution of irradiation defects in clays to the tracing of past uranium migrations; 17 - Uranium concentrations in mineralizing fluids of the Athabasca basin: analytical and experimental approach; 18 - Paleo-surfaces and metallic rooting: the autochthonous uranium of pre-Athabasca paleo-alterites, Canada; 19 - Distribution of argillaceous parageneses in the Imouraren deposit - Niger; 20 - Heat flux and radioelements concentration (U, Th, K) of precambrian basements: implications in terms of crust growth mechanisms, paleo

Recovering uranium from phosphates

Energy Technology Data Exchange (ETDEWEB)

Bergeret, M [Compagnie de Produits Chimiques et Electrometallurgiques Pechiney-Ugine Kuhlmann, 75 - Paris (France)

1981-06-01

Processes for the recovery of the uranium contained in phosphates have today become competitive with traditional methods of working uranium sources. These new possibilities will make it possible to meet more rapidly any increases in the demand for uranium: it takes ten years to start working a new uranium deposit, but only two years to build a recovery plant.

The latest figures on uranium

International Nuclear Information System (INIS)

Vance, R.

2010-01-01

According to the latest figures on uranium, soon to be published by the NEA, uranium resources, production and demand are all on the rise. Exploration efforts have increased recently in line with the expected expansion of nuclear energy in the coming years. Total identified resources have grown and are now sufficient to cover 100 years of supply at 2008 rates of consumption. Costs of production have, however, also increased. This article is based on the latest edition of the 'Red Book', Uranium 2009: Resources, Production and Demand, which presents the results of the most recent biennial review of world uranium market fundamentals and a statistical profile of the world uranium industry as of 1 January 2009. It contains official data provided by OECD Nuclear Energy Agency (NEA) and International Atomic Energy Agency (IAEA) member countries on uranium exploration, resources, production and reactor-related requirements. Projections of nuclear generating capacity and reactor-related uranium requirements through 2035 are also provided as well as a discussion of long-term uranium supply and demand issues. Despite recent declines stemming from the global financial crisis, world demand for electricity is expected to continue to grow significantly over the next several decades to meet the needs of an increasing population and economic growth. The recognition by an increasing number of governments that nuclear power can produce competitively priced, base-load electricity that is essentially free of greenhouse gas emissions, coupled with the role that nuclear can play in enhancing security of energy supply, increases the prospects for growth in nuclear generating capacity, although the magnitude of that growth remains to be determined. Regardless of the role that nuclear energy ultimately plays in meeting rising electricity demand, the uranium resource base is more than adequate to meet projected requirements. Meeting even high-case requirements to 2035 would consume less

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

Some Thoughts after the Inaugural Meeting of the International Forum on Sustainable Options in Uranium Production

International Nuclear Information System (INIS)

Tano, M.L.

2009-01-01

This paper examines the discussions at the inaugural meeting International Forum on Sustainable Options in Uranium Production and suggests that to be successful, IFSOUP should be organized as a network of disparate entities whose activities are related to a broad range of effects, including not only the actual mining, processing and regulation of uranium, but also social, cultural, economic, political, informational, educational, and other factors. The endeavor called IFSOUP is made up of those entities that are cooperating (consciously or deliberately) in some particular context and those whose behavior is expected to aid those actors who have chosen to cooperate. (authors)

Symposia for a Meeting on Ion Channels and Gap Junctions

CERN Document Server

Sáez, Juan

1997-01-01

Ion channels allow us to see nature in all its magnificence, to hear a Bach suite, to smell the aroma of grandmother's cooking, and, in this regard, they put us in contact with the external world. These ion channels are protein molecules located in the cell membrane. In complex organisms, cells need to communicate in order to know about their metabolic status and to act in a coordinate manner. The latter is also accomplished by a class of ion channels able to pierce the lipid bilayer membranes of two adjacent cells. These intercellular channels are the functional subunits of gap junctions. Accordingly, the book is divided in two parts: the first part is dedicated to ion channels that look to the external world, and the second part is dedicated to gap junctions found at cell interfaces. This book is based on a series of symposia for a meeting on ion channels and gap junctions held in Santiago, Chile, on November 28-30, 1995. The book should be useful to graduate students taking the first steps in this field as...

Analysis of uranium supply to 2050

International Nuclear Information System (INIS)

2001-05-01

The central theme of this report is to assess the adequacy of uranium resources to meet future requirements based on a range of opinions as to the future of nuclear power. The report discusses three demand cases that project uranium requirements from 2000 to 2050. The report also reviews the supply sources that are expected to be available to meet reactor uranium demand through to 2050. Supply is divided into two broad categories: secondary and primary supply. The report also assesses the adequacy of uranium resources to satisfy market based production requirements

Steady-state thermal hydraulic analysis and flow channel blockage accident analysis of JRR-3 silicide core

International Nuclear Information System (INIS)

Kaminaga, Masanori

1997-03-01

JRR-3 is a light water moderated and cooled, beryllium and heavy water reflected pool type research reactor using low enriched uranium (LEU) plate-type fuels. Its thermal power is 20 MW. The core conversion program from uranium-aluminum (UAl x -Al) dispersion type fuel (aluminide fuel) to uranium-silicon-aluminum (U 3 Si 2 -Al) dispersion type fuel (silicide fuel) is currently conducted at the JRR-3. This report describes about the steady-state thermal hydraulic analysis results and the flow channel blockage accident analysis result. In JRR-3, there are two operation mode. One is high power operation mode up to 20 MW, under forced convection cooling using the primary and the secondary cooling systems. The other is low power operation mode up to 200 kW, under natural circulation cooling between the reactor core and the reactor pool without the primary and the secondary cooling systems. For the analysis of the flow channel blockage accident, COOLOD code was used. On the other hand, steady-state thermal hydraulic analysis for both of the high power operation mode under forced convection cooling and low power operation under natural convection cooling, COOLOD-N2 code was used. From steady-state thermal hydraulic analysis results of both forced and natural convection cooling, fuel temperature, minimum DNBR etc. meet the design criteria and JRR-3 LEU silicide core has enough safety margin under normal operation conditions. Furthermore, flow channel blockage accident analysis results show that one channel flow blockage accident meet the safety criteria for accident conditions which have been established for JRR-3 LEU silicide core. (author)

Moving to world's best uranium address

International Nuclear Information System (INIS)

Noakes, Frank

2006-01-01

Most exploration dollars spent in South Australia are focused on exploiting uranium. This is for good reason as South Australia is the world's best address for uranium. Pressure to cut CO 2 emissions and the ballistic growth of the Chinese and Indian economies has heightened expectations that the worldwide use of uranium for power generation will mushroom beyond its current 17% market share. The recent Australia-China deal only seems to confirm this; hence uranium's growing popularity among miners and explorers. Such is the attractiveness of uranium-related floats, when Toro Energy sought $18m in March it was swamped with more than three times share application volume. In the north west, Southern Gold and Hindmarsh Resources are expectantly drilling for commercial uranium deposits all around the acreage that hosts the Challenger gold mine in the Gawler Craton. The first exploration drilling for uranium in quaternary-age river channels will take place in South Australia's far north in May. Red Metal says while older and deeper tertiary river channels in the area that host the Beverley uranium mine were explored for uranium, the younger near-surface channel has not had a single hole drilled for uranium. This is despite the area being one of the 'hottest radiogenic terrains in South Australia'. The company will target calcrete-style uranium mineralisation similar to the Yerrlirrie deposit in Western Australia (52,000t U308). Tasman Resources will start drilling to test seven uranium targets within 30km of Olympic Dam, the world's largest known uranium deposit, later this year. Tasman also holds tenements adjoining the Warrior uranium deposit near Tarcoola that contains known radiometric anomalies within the 40km-long Wynbring paleochannels. They are the fourth largest uranium explorer in South Australia. Alliance Resources and its JV partner Quasar Resources are exploring the Beverley 4 Mile uranium prospect at Arkaroola. Quasar is an affiliate of Heathgate Resources

Uranium resources and supply - demand to 2030

International Nuclear Information System (INIS)

Vance, R.

2010-01-01

Recent fluctuations in the market price for uranium have resulted in more activity in this sector over the past few years than in the preceding 20 years. Amidst this background, uranium demand is increasing. Construction of nuclear reactors is proceeding in some countries, ambitious expansion plans have been announced in others and the development of nuclear power programs to meet electricity demand and minimize greenhouse emissions in a cost effective manner is under consideration in many others. This paper reviews projections of nuclear growth and uranium demand and assesses the challenges faced by the uranium mining sector in meeting rising demand. Since the mid-1960 s, an international expert committee (the 'Uranium Group') formed by the OECD Nuclear Energy Agency and the International Atomic Energy Agency has published biennially comprehensive updates on global uranium resources, production and demand (the 'Red Book'). The most recent in this series, based on 2007 data and published in June 2008, includes a supply/demand projection to 2030. However, much has changed since the data were collected for this projection and an assessment of these changes and their impact on uranium production is included in this presentation. It is concluded that world identified uranium resources (5.45 million t U recoverable at costs up to US$130/kg U, or US$50/lb U 3 O 8 ) are adequate to meet projected future high case nuclear power requirements. However, recent financial market turmoil and lower uranium prices, the opaque nature of the uranium market itself, increased regulatory requirements, a scarcity of the required specialized labour and the fluctuating costs of raw materials makes the process of turning uranium resources in the ground into yellowcake in the can increasingly more challenging, particularly for new entrants. Considerable investment and expertise will be required to bring about the substantial increase in mine production required to meet future demand

National Uranium Resource Evaluation: Harrisburg Quadrangle, Pennsylvania

International Nuclear Information System (INIS)

Popper, G.H.P.

1982-08-01

The Harrisburg Quadrangle, Pennsylvania, was evaluated to identify geologic environments and delineate areas favorable for uranium deposits. The evaluation, based primarily on surface reconnaissance, was carried out for all geologic environments within the quadrangle. Aerial radiometric and hydrogeochemical and stream-sediment reconnaissance surveys provided the supplementary data used in field-work followup studies. Results of the investigation indicate that environments favorable for peneconcordant sandstone uranium deposits exist in the Devonian Catskill Formation. Near the western border of the quadrangle, this environment is characterized by channel-controlled uranium occurrences in basal Catskill strata of the Broad Top syncline. In the east-central portion of the quadrangle, the favorable environment contains non-channel-controlled uranium occurrences adjacent to the Clarks Ferry-Duncannon Members contact. All other geologic environments are considered unfavorable for uranium deposits

Application of uranium exploration data and techniques in environmental studies. Proceedings of a technical committee meeting held in Vienna, 9-12 November 1993

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

Exploration for mineral commodities, uranium included normally utilizes extensive, systematic geophysical and geochemical surveys covering very large areas, often entire countries. This information represents a great wealth of data that could be used to produce baseline information for environmental studies and monitoring. It is with this appreciation that IAEA convened a Technical Committee meeting with the purpose of bringing together experts in uranium exploration, geophysics and geochemistry to discuss and exchange information on the benefits of past exploration data and commonly applied techniques in environmental studies. The meeting on the Use of Uranium Exploration Data and Techniques in Environmental Studies was attended by 44 participants from 23 countries and one international organization. Thirty-two papers covering case histories on the use of old uranium exploration data to prepare exposure dose rate and radon potential maps, the use of airborne gamma ray spectrometric systems to monitor nuclear power plants and nuclear fuel cycle facilities, and the use of similar systems in response to emergency measures in the case of accidental releases were presented. Refs, figs and tabs.

Application of uranium exploration data and techniques in environmental studies. Proceedings of a technical committee meeting held in Vienna, 9-12 November 1993

International Nuclear Information System (INIS)

1995-10-01

Exploration for mineral commodities, uranium included normally utilizes extensive, systematic geophysical and geochemical surveys covering very large areas, often entire countries. This information represents a great wealth of data that could be used to produce baseline information for environmental studies and monitoring. It is with this appreciation that IAEA convened a Technical Committee meeting with the purpose of bringing together experts in uranium exploration, geophysics and geochemistry to discuss and exchange information on the benefits of past exploration data and commonly applied techniques in environmental studies. The meeting on the Use of Uranium Exploration Data and Techniques in Environmental Studies was attended by 44 participants from 23 countries and one international organization. Thirty-two papers covering case histories on the use of old uranium exploration data to prepare exposure dose rate and radon potential maps, the use of airborne gamma ray spectrometric systems to monitor nuclear power plants and nuclear fuel cycle facilities, and the use of similar systems in response to emergency measures in the case of accidental releases were presented. Refs, figs and tabs

Uranium in Canada

International Nuclear Information System (INIS)

1985-09-01

In 1974 the Minister of Energy, Mines and Resources (EMR) established a Uranium Resource Appraisal Group (URAG) within EMR to audit annually Canada's uranium resources for the purpose of implementing the federal government's uranium export policy. A major objective of this policy was to ensure that Canadian uranium supplies would be sufficient to meet the needs of Canada's nuclear power program. As projections of installed nuclear power growth in Canada over the long term have been successively revised downwards (the concern about domestic security of supply is less relevant now than it was 10 years ago) and as Canadian uranium supply capabilities have expanded significantly. Canada has maintained its status as the western world's leading exporter of uranium and has become the world's leading producer. Domestic uranium resource estimates have increased to 551 000 tonnes U recoverable from mineable ore since URAG completed its last formal assessment (1982). In 1984, Canada's five primary uranium producers employed some 5800 people at their mining and milling operations, and produced concentrates containing some 11 170 tU. It is evident from URAG's 1984 assessment that 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 that are either in opertaion now or committed or expected to be in-service by 1995. A substantial portion of Canada's identified uranium resources, recoverable within the same price range, is thus surplus to Canadian needs and available for export. Sales worth close to $1 billion annually are assured. Uranium exploration expenditures in Canada in 1983 and 1984 were an estimated $41 million and $35 million, respectively, down markedly from the $128 million reported for 1980. Exploration drilling and surface development drilling in 1983 and 1984 were reported to be 153 000 m and 197 000 m, respectively, some 85% of which was in

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...

Determination of uranium in bench test by L_Ⅲ-absorption edge method

International Nuclear Information System (INIS)

Song You; Zheng Weiming; Liu Guijiao; Chen Chen

2014-01-01

By independent research L_Ⅲ--absorption edge densimeter, an analytical method for uranium sample with the concentration from 20 g/L to 200 g/L was developed. The fitting area for uranium measurement was determined through experiment. The left fitting area was 1659-1856 channel, and the right one was 2063-2280 channel. The uranium L_Ⅲ--absorption edge was at 1995 channel. The results show that the influence of HNO_3 concentration lower than 9 mol/L, Al and Fe concentration lower than 10 g/L was negligibly small. The uranium measurement precision is better than 0.5%, and the instrument stability is good. Some samples in bench test of uranium recovery were determined. The results are satisfactory. (authors)

United States uranium enrichment policies

International Nuclear Information System (INIS)

Roberts, R.W.

1977-01-01

ERDA's uranium enrichment program policies governing the manner in which ERDA's enrichment complex is being operated and expanded to meet customer requirements for separative work, research and development activities directed at providing technology alternatives for future enrichment capacity, and establishing the framework for additional domestic uranium enrichment capacity to meet the domestic and foreign nuclear industry's growing demand for enrichment services are considered. The ERDA enrichment complex consists of three gaseous diffusion plants located in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. Today, these plants provide uranium enrichment services for commercial nuclear power generation. These enrichment services are provided under contracts between the Government and the utility customers. ERDA's program involves a major pilot plant cascade, and pursues an advanced isotope separation technique for the late 1980's. That the United States must develop additional domestic uranium enrichment capacity is discussed

Recycling of plutonium and uranium in water reactor fuel. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1997-05-01

The Technical Committee Meeting on Recycling of Plutonium and Uranium in Water Reactor Fuel was recommended by the International Working Group on Fuel Performance and Technology (IWGFPT). Its aim was to obtain an overall picture of MOX fabrication capacity and technology, actual performance of this kind of fuel, and ways explored to dispose of the weapons grade plutonium. The subject of this meeting had been reviewed by the International Atomic Energy Agency every 5 to 6 years and for the first time the problem of weapons grade plutonium disposal was included. The papers presented provide a summary of experience on MOX fuel and ongoing research in this field in the participating countries. The meeting was hosted by British Nuclear Fuels plc, at Newby Bridge, United Kingdom, from 3 to 7 July 1995. Fifty-six participants from twelve countries or international organizations took part. Refs, figs, tabs

Uranium deposits: northern Denver Julesburg basin, Colorado

International Nuclear Information System (INIS)

Reade, H.L.

1978-01-01

The Fox Hills Sandstone and the Laramie Formation (Upper Cretaceous) are the host rocks for uranium deposits in Weld County, northern Denver Julesburg basin, Colorado. The uranium deposits discovered in the Grover and Sand Creek areas occur in well-defined north--south trending channel sandstones of the Laramie Formation whereas the sandstone channel in the upper part of the Fox Hills Sandstone trends east--west. Mineralization was localized where the lithology was favorable for uranium accumulation. Exploration was guided by log interpretation methods similar to those proposed by Bruce Rubin for the Powder River basin, Wyoming, because alteration could not be readily identified in drilling samples. The uranium host rocks consist of medium- to fine-grained carbonaceous, feldspathic fluvial channel sandstones. The uranium deposits consist of simple to stacked roll fronts. Reserve estimates for the deposits are: (1) Grover 1,007,000 lbs with an average grade of 0.14 percent eU 3 O 8 ,2) Sand Creek 154,000 lbs with an average grade of 0.08 percent eU 3 O 8 , and 3) The Pawnee deposit 1,060,000 lbs with an average grade of 0.07 percent eU 3 O 8 . The configuration of the geochemical cells in the Grover and Sand Creek sandstones indicate that uraniferous fluids moved northward whereas in the Pawnee sandstone of the Fox Hills uraniferous fluids moved southward. Precipitation of uranium in the frontal zone probably was caused by downdip migration of oxygcnated groundwater high in uranium content moving through a favorable highly carbonaceous and pyritic host sandstone

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

Principles of modern uranium exploration

International Nuclear Information System (INIS)

King, J.W.

1974-01-01

The Athens Symposium followed the recommendations of a panel meeting in April 1970 on uranium exploration geology. It was attended by 220 participants representing 40 countries and two international organizations; 43 papers were presented. An overview of the supply challenge of uranium was given by Mr. Robert D. Nininger, of the USAEC, who acted as chairman of the Symposium. He outlined the major topics and problems to be discussed during the conference, with the aim of meeting this challenge: 'Uranium deposits in sandstone and quartz pebble conglomerates presently represent the preponderance of uranium resources. Yet there is a question whether geologic limitations on the occurrence of such deposits may preclude their discovery in numbers sufficient to meet the eventual resource needs. New types of deposits, low in grade but larger in size, representing the equivalent of the porphyry copper deposits, may supply the bulk of future resource additions. Further investigation is needed on the characteristics of such deposits and the means of their identification. Similarly, additional investigation is needed to determine whether limits on the more conventional deposits do, in fact, exist, and, if not, what advanced approaches to rapid identification of additional such deposits may be employed'

Lake Austin uranium deposit, Western Australia

International Nuclear Information System (INIS)

Heath, A.G.; Deutscher, R.L.; Butt, C.R.M.

1984-01-01

The Lake Austin uranium deposit is a calcrete type deposit in the Yilgarn Block, near Cue, in a catchment area of granitoids and greenstones. The uranium is in valley fill and the sediments of the Lake Austin playa. The mineralization occurs over 1 to 6 meter thickness close to the water table in calcrete overlying clays and/or weathered bedrock. The principal uranium mineral is carnotite. Waters in nearby channels have an uranium content of over 30 ppb. The chloride content of the water increases downstream in the nearby drainages, as does the uranium and vanadium content. (author)

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

Analysis on depositional system and discussion on ore-formation conditions of channel sandstone type uranium deposit. Taking Dongsheng area, Ordos meso-cenozoic basin as an example

International Nuclear Information System (INIS)

Wu Rengui; Yu Dagan; Zhu Minqiang; Zhou Wanpeng; Chen Anping

2003-01-01

Applying the theory of depositional system, the depositional facies and depositional systems of the Zhiluo Formation in Dongsheng area are systematically analysed, and the authors proposed that sediments of the Zhiluo Formation are of fluvial facies, and streams of the Zhiluo time experienced three evolution stages, namely: the early braided stream, the middle low sinuosity meandering stream and the late high sinuosity meandering stream. Based on features of paleoclimatic evolution, the Zhiluo Formation is divided into two lithological members. The lower lithological member consists of sediments of braided and low sinuosity meandering streams under humid-ward paleoclimatic conditions forming grey sedimentary formation. The upper member is composed of sediments of meandering streams under arid-hot paleoclimatic conditions representing complex-colored (mainly red) sedimentary formation. It is suggested that uranium mineralization in the study area is of channel sandstone type and controlled by braided channel sediments. Besides, the ore-formation conditions for channel sandstone type uranium deposit are preliminarily discussed

Uranium mining and production of concentrates in India

International Nuclear Information System (INIS)

Bhasin, J.L.

1997-01-01

In order to meet the uranium requirements for the atomic power programme of the country, uranium deposits were explored, mined and concentrates were produced indigenously. The geology of the areas, mode of entries and the various extraction methods deployed in different mines with their constraints are described. The various equipments used in mining and processing activities are elaborated. The flow sheets for processing the uranium ore and that of the effluent treatment plant are given in detail. The future plans of the company for undertaking the new projects to meet the demand of uranium requirement for the increasing nuclear power programme are given. (author). 18 figs

Method of purifying uranium tetrafluoride hydrate and preparing uranium (VI) peroxide hydrate using a fluoride complexing agent

International Nuclear Information System (INIS)

Barreiro, A.J.; Lowe, C.M.T.; Lefever, J.A.; Pyman, R.L.

1983-01-01

The annual production of phosphate rock, on the order of about 30-40 million tons yearly, represents several million pounds of uranium. The present invention provides a process of purifying uranium tetrafluoride hydrate to produce a uranium (VI) peroxide product meeting 'yellow cake' standards using a double precipitation procedure. A fluoride complexing agent is used in the precipitation

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)

Meeting of the French geological society - Uranium: geology, geophysics, chemistry. Book of abstracts; Reunion de la Societe Geologique de France - Uranium: geologie, geophysique, chimie. Recueil des resumes

Energy Technology Data Exchange (ETDEWEB)

Zakari, A.A.; Mima, S.; Bidaud, A.; Criqui, P.; Menanteau, P.; David, S.; Pagel, M.; Chagnes, A.; Cote, G.; Courtaud, B.; Thiry, J.; Miehe, J.M.; Gilbert, F.; Cuney, M.; Bruneton, P.; Ewington, D.; Vautrin-Ul, C.; Cannizzo, C.; Betelu, S.; Chausse, A.; Ly, J.; Bourgeois, D.; Maynadie, J.; Meyer, D.; Clavier, N.; Costin, D.T.; Cretaz, F.; Szenknect, S.; Ravaux, J.; Poinssot, C.; Dacheux, N.; Durupt, N.; Blanvillain, J.J.; Geffroy, F.; Aparicio, B.; Dubessy, J.; Nguyen-Trung, C.; Robert, P.; Uri, F.; Beaufort, D.; Lescuyer, J.L.; Morichon, E.; Allard, T.; Milesi, J.P.; Richard, A.; Rozsypal, C.; Mercadier, J.; Banks, D.A.; Boiron, M.C.; Cathelineau, M.; Dardel, J.; Billon, S.; Patrier, P.; Wattinne, A.; Vanderhaeghe, O.; Fabre, C.; Castillo, M.; Salvi, S.; Beziat, D.; Williams-Jones, A.E.; Trap, P.; Durand, C.; Goncalves, P.; Marquer, D.; Feybesse, J.L.; Richard, Y.; Orberger, B.; Hofmann, A.; Megneng, M.; Orberger, B.; Bouttemy, M.; Vigneron, J.; Etcheberry, A.; Perdicakis, M.; Prignon, N.; Toe, W.; Andre-Mayer, A.S.; Eglinger, A.; Jordaan, T.; Hocquet, S.; Ledru, P.; Selezneva, V.; Vendryes, G.; Lach, P.; Cuney, M.; Mercadier, J.; Brouand, M.; Duran, C.; Seydoux-Guillaume, A.M.; Bingen, B.; Parseval, P. de; Guillaume, D.; Bosse, V.; Paquette, J.L.; Ingrin, J.; Montel, J.M.; Giot, R.; Maucotel, F.; Hubert, S.; Gautheron, C.; Tassan-Got, L.; Pagel, M.; Barbarand, J.; Cuney, M.; Lach, P.; Bonhoure, J.; Leisen, M.; Kister, P.; Salaun, A.; Villemant, B.; Gerard, M.; Komorowski, J.C.; Michel, A.; Riegler, T.; Tartese, R.; Boulvais, P.; Poujols, M.; Gloaguen, E.; Mazzanti, M.; Mougel, V.; Nocton, G.; Biswas, B.; Pecaut, J.; Othmane, G.; Menguy, N.; Vercouter, T.; Morin, G.; Galoisy, L.; Calas, G.; Fayek, M.

2010-11-15

This document brings together the abstracts of the 39 presentations given at this meeting days on uranium, organized by the French geological society, and dealing with: 1 - Prospective study of the electronuclear technological transition; 2 - The front-end of the nuclear cycle: from the molecule to the process; 3 - Geophysics: recent changes; 4 - Use of well logging in uranium exploration; 5 - Genetical classification of thorium deposits; 6 - Genetical nomenclature of uranium sources; 7 - Uranium deposits linked to a Proterozoic discordance - retrospective; 8 - The use of spectral analysis techniques in uranium exploration: real-time mapping of clay alteration features; 9 - Development of functionalized silk-screened carbon electrodes for the analysis of uranium trace amounts; 10 - Study of the actinides solvation sphere in organic environment; 11 - Thermodynamic of uraniferous phases of interest for the nuclear cycle; 12 - Heap leaching of marginal minerals at Somair: from lab studies to the production of 700 t of uranium/year; 13 - Agglomeration phenomenology and role of iron in uranium heap leaching; 14 - Chloride uranyl complexes up to 300 deg. C along the saturation vapour curve: Raman spectroscopy analysis and metallogenic consequences; 15 - Weathering systems in the Shea Creek deposit (Athabasca, Canada): vertical variability of argillaceous weathering; 16 - Weathering systems in the Shea Creek deposit (Athabasca, Canada): contribution of irradiation defects in clays to the tracing of past uranium migrations; 17 - Uranium concentrations in mineralizing fluids of the Athabasca basin: analytical and experimental approach; 18 - Paleo-surfaces and metallic rooting: the autochthonous uranium of pre-Athabasca paleo-alterites, Canada; 19 - Distribution of argillaceous parageneses in the Imouraren deposit - Niger; 20 - Heat flux and radioelements concentration (U, Th, K) of precambrian basements: implications in terms of crust growth mechanisms, paleo

Determination of uranium in uranium metal, uranium oxides, and uranyl nitrate solutions by potentiometric titration

International Nuclear Information System (INIS)

Tucker, H.L.; McElhaney, R.J.

1983-01-01

A simple, fast method for the determination of uranium in uranium metal, uranium oxides, and uranyl nitrate solutions has been adapted from the Davies-Gray volumetric method to meet the needs of Y-12. One-gram duplicate aliquots of uranium metal or uranium oxide are dissolved in 1:1 HNO 3 and concentrated H 2 SO 4 to sulfur trioxide fumes, and then diluted to 100-mL volume. Duplicate aliquots are then weighed for analysis. For uranyl nitrate samples, duplicate aliquots containing between 50 and 150 mg of U are weighed and analyzed directly. The weighed aliquot is transferred to a Berzelius beaker; 1.5 M sulfamic acid is added, followed in order by concentrated phosphoric acid, 1 M ferrous sulfate, and (after a 30-second interval) the oxidizing reagent. After a timed 3-minute waiting period, 100 mL of the 0.1% vanadyl sulfate-sulfuric acid mixture is added. The sample is then titrated past its endpoint with standard potassium dichromate, and the endpoint is determined by second derivative techniques on a mV/weight basis

Prospects of uranium supply-demand situation in world nuclear power development

International Nuclear Information System (INIS)

Chen Zuyi; Wang Xingwu

2010-01-01

Based on the newest materials and data published by authoritative organizations, this paper introduces the near-term and medium to long-term development situation of world nuclear power, summarizes the main characteristics of recent world uranium production, preliminarily analyses the relationship between uranium supply and demand to 2030. It is suggested that from the view-point of whole world, uranium resources are fully sufficient for the near-term and medium to long-term world uranium production and uranium demand of nuclear power. World uranium production can meet the near-term uranium demand for nuclear power. However, a big supply-demand gap may exist after 2015 as world nuclear power will be developed with high speed. In case if all const ruction plans of new uranium mines and production- expansion plans of existing uranium mines will be completed on time, it is quite possible for the world uranium production to meet the long-term uranium demand of nuclear power development. (authors)

Transient Receptor Potential channels: What's happening? Reflections in the wake of the 2009 TRP Meeting, Karolinska Institutet, Stockholm.

Science.gov (United States)

Goswami, Chandan; Islam, Md Shahidul

2010-01-01

More than 150 participants from 25 countries gathered in Stockholm during 25(th) to 27(th) Sept 2009 to attend the meeting "TRP channels: from sensory signaling to human disease" and enjoyed an international, intensive and vibrant meeting. This meeting shed lights on the recent advances made in this field of research in different sectors of biology, and identified directions for future research and the areas where TRP channels could be used as potential targets for prevention and treatment of human diseases. The participants of this meeting shared their recent largely unpublished data, state-of-the-art techniques and their critical views which would push research in this field forward in the new decade. Another major outcome of this meeting was the realization that extensive work remains to be done to develop the necessary tools and enhance the quality of research in this area so that the prevailing controversies can be resolved. In this report we summarize the latest scientific excitements, some critical issues, as well as some future directions for research that were addressed and discussed in this meeting.

Impact of new environmental and safety regulations on uranium exploration, mining, milling and management of its waste. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

Concern for health, safety and the environment has grown rapidly during the last two decades. Exploitation of any mineral commodity, including uranium, involves the modification of the surrounding environment. Appropriate regulations governing such activities can assure good practices and minimize possible negative impacts on the environment and the health and safety of the workers and the general public. During the past few years, a number of countries have promulgated new regulations related to uranium exploitation, mining, milling and the related waste management. Recent regulations are stricter in terms of environmental assessment, mitigation, radiation protection and control of waste. The impact of those regulations in developed countries has resulted in better planning of operations, improvement in mine and mill designs and a more efficient approach to tailings management. The Meeting was attended by 25 participants from 17 countries representing government organizations and private industry. This document includes 21 papers presented at the Meeting on new experiences in major uranium producing countries on the subject, past producers, as well as on country where regulations and related regulatory structure are still at the early evolutionary stage. Each of the papers was indexed separately.

Impact of new environmental and safety regulations on uranium exploration, mining, milling and management of its waste. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2001-09-01

Concern for health, safety and the environment has grown rapidly during the last two decades. Exploitation of any mineral commodity, including uranium, involves the modification of the surrounding environment. Appropriate regulations governing such activities can assure good practices and minimize possible negative impacts on the environment and the health and safety of the workers and the general public. During the past few years, a number of countries have promulgated new regulations related to uranium exploitation, mining, milling and the related waste management. Recent regulations are stricter in terms of environmental assessment, mitigation, radiation protection and control of waste. The impact of those regulations in developed countries has resulted in better planning of operations, improvement in mine and mill designs and a more efficient approach to tailings management. The Meeting was attended by 25 participants from 17 countries representing government organizations and private industry. This document includes 21 papers presented at the Meeting on new experiences in major uranium producing countries on the subject, past producers, as well as on country where regulations and related regulatory structure are still at the early evolutionary stage. Each of the papers was indexed separately

The sedimentology and uranium mineralisation of the DR-3 deposit, Laingsburg district

International Nuclear Information System (INIS)

Le Roux, J.P.

1982-08-01

As part of its research program in the Karoo, NUCOR carried out a sedimentological investigation of the DR-3 deposit, discovered by JCI. It is located on the farm Drie Vaderlandsche Rietvalleyen, 40 km north of Laingsburg, in an unnamed sandstone package of the Abrahamskraal Formation. The orebody lies in an area affected by southward-dipping monoclines, which possibly originated because of basement faults during subsidence of the Karoo trough. These monoclines may be have locally altered the courses of rivers flowing from the source areas to the south-west. The S1-sandstone which hosts the uranium was probably deposited in a braided river environment of the Donjek type. The vector mean azimuth is towards 075 degrees for S1 and 062 degrees for the studied sequence as a whole, but towards the east there is a marked change in the palaeocurrent direction. On a more regional scale, preliminary investigations indicate the braided river system was at least 5 km wide. Uranium mineralisation on DR-3 is concentrated within a major east-west-trending channel, with the best-developed ore at the junctions of this channel with tributaries from the south. This is probably due to plant material settling out in the areas of reduced current velocities where opposing streams meet

Physico-chemical and radiological characterization of uranium tailings from Tummalapalle uranium mining site

International Nuclear Information System (INIS)

Patra, A.C.; Sahoo, S.K.; Lenka, P.; Gupta, Anil; Jha, S.K.; Tripathi, R.M.; Molla, S.; Rana, B.K.

2018-01-01

Mining of uranium bearing minerals is essential for the extraction of uranium to meet the power requirements of India. Mining and milling activities produce large quantities of low active tailings, as wastes, which are contained in Tailings Ponds. The nature of tailings depends on the mineralogy of ore and host rock and their quantity depends on the configuration of the ore body and mining methods. The mobility of an element from these tailings depends on elemental concentration, pH, particle size, cation exchange capacity, bulk density and porosity of the tailings etc. This necessitates complete characterisation of the tailings. In this paper we aim to characterize the uranium mill tailings generated from Tummalapalle uranium mining facility in Kadappa district, Andhra Pradesh, India

National Uranium Resource Evaluation: Manhattan Quadrangle, Kansas

International Nuclear Information System (INIS)

Fair, C.L.; Smit, D.E.

1982-08-01

Surface reconnaissance and detailed subsurface studies were conducted in the Manhattan Quadrangle, Kansas, to evaluate uranium favorability using National Uranium Resource Evaluation criteria. These studies were designed in part to follow up airborne radiometric and hydrogeochemical and stream-sediment surveys. More than 600 well records were examined in the subsurface phase of the study. Results of these investigations indicate environments favorable for channel-controlled peneconcordant sandstone uranium deposits in Cretaceous rocks and for Wyoming roll-type deposits in Pennsylvanian sandstones. The Cretaceous sandstone environments exhibit such favorable characteristics as a bottom unconformity, high bed load, braided fluvial channels, large-scale cross-bedding, and one anomalous outcrop. The Pennsylvanian sandstone environments exhibit such favorable characteristics as arkosic cross-bedded sandstones, included pyrite and organic debris, interbedded shales, and gamma-ray log anomalies. Environments considered unfavorable for uranium deposits are limestone and dolomite environments, marine black shale environments, evaporative precipitate environments, and some fluvial sandstone environments. Environments considered unevaluated because not enough data were available include Precambrian plutonic, metamorphic, and sedimentary rocks, even though a large number of thin sections were available for study

Progress report on nuclear science and technology in China (Vol.1). Proceedings of academic annual meeting of China Nuclear Society in 2009, No.2--uranium mining and metallurgy sub-volume

International Nuclear Information System (INIS)

2010-11-01

Progress report on nuclear science and technology in China (Vol. 1) includes 889 articles which are communicated on the first national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the second one, the content is about uranium mining, uranium metallurgy and nuclear power.

Removal of uranium from uranium-contaminated soils -- Phase 1: Bench-scale testing. Uranium in Soils Integrated Demonstration

Energy Technology Data Exchange (ETDEWEB)

Francis, C. W.

1993-09-01

To address the management of uranium-contaminated soils at Fernald and other DOE sites, the DOE Office of Technology Development formed the Uranium in Soils Integrated Demonstration (USID) program. The USID has five major tasks. These include the development and demonstration of technologies that are able to (1) characterize the uranium in soil, (2) decontaminate or remove uranium from the soil, (3) treat the soil and dispose of any waste, (4) establish performance assessments, and (5) meet necessary state and federal regulations. This report deals with soil decontamination or removal of uranium from contaminated soils. The report was compiled by the USID task group that addresses soil decontamination; includes data from projects under the management of four DOE facilities [Argonne National Laboratory (ANL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), and the Savannah River Plant (SRP)]; and consists of four separate reports written by staff at these facilities. The fundamental goal of the soil decontamination task group has been the selective extraction/leaching or removal of uranium from soil faster, cheaper, and safer than current conventional technologies. The objective is to selectively remove uranium from soil without seriously degrading the soil`s physicochemical characteristics or generating waste forms that are difficult to manage and/or dispose of. Emphasis in research was placed more strongly on chemical extraction techniques than physical extraction techniques.

Uranium favorability of tertiary rocks in the Badger Flats, Elkhorn Thrust Area, Park and Teller Counties, Colorado

International Nuclear Information System (INIS)

Young, P.; Mickle, D.G.

1976-10-01

Uranium potential of Tertiary rocks in the Badger Flats--Elkhorn Thrust area of central Colorado is closely related to a widespread late Eocene erosion surface. Most uranium deposits in the area are in the Eocene Echo Park Alluvium and Oligocene Tallahassee Creek Conglomerate, which were deposited in paleodrainage channels on or above this surface. Arkosic detritus within the channels and overlying tuffaceous sedimentary rocks of the Antero and Florissant Formations of Oligocene age and silicic tuffs within the volcanic units provide abundant sources of uranium that could be concentrated in the channels where carbonaceous debris facilitates a reducing environment. Anomalous soil, water, and stream-sediment samples near the Elkhorn Thrust and in Antero basin overlie buried channels or are offset from them along structural trends; therefore, uranium-bearing ground water may have moved upward from buried uranium deposits along faults. The area covered by rocks younger than the late Eocene erosion surface, specifically the trends of mapped or inferred paleochannels filled with Echo Park Alluvium and Tallahassee Creek Conglomerate, and the Antero Formation are favorable for the occurrence of uranium deposits

Uranium issues and policies: an overview

International Nuclear Information System (INIS)

Patterson, J.A.

1979-01-01

US policy is to reestablish the viability of nuclear energy and to expand the useful energy derived from uranium. A comprehensive assessment of US uranium resources is a key part of this effort. This assessment should lead to resolution of issues regarding adequacy of US uranium resources and production capability to meet long-term need in an economic manner. DOE programs on ore-reserve estimation, resource appraisal (particularly NURE), and production capability analysis are responsive to these information needs, as well as concerns regarding uranium demand, market growth, uranium prices, and foreign supply and demand. The cooperation of industry, particularly in providing basic information needed for DOE studies, is a vital element of this activity

Innovations in uranium exploration, mining and processing techniques, and new exploration target areas. Proceedings of a technical committee meeting held in Vienna, 5-8 December 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

In 1994 there were 432 nuclear power plants in operation with a combined electricity generating capacity of 340 347 MWe. To achieve this, 58,000 tonnes of uranium were required as nuclear fuel. In view of its economic importance, the International Atomic Energy Agency has had a long-standing interest in uranium exploration, resources, production and demand. This is reflected in numerous publications covering different aspects of this field. Particularly worth mentioning is the periodical ``Uranium Resources, Production and Demand``, published jointly with the Nuclear Energy Agency of the OECD. Its fourteenth edition was published in early 1994. It was the objective of this Technical Committee meeting, the proceedings of which are presented in this TECDOC, to bring together specialists in the field and to collect information on new developments in exploration, mining techniques and innovative methods of processing that are more environmentally friendly. The meeting was attended by a total of 22 participants from 14 countries. Eleven papers were presented describing new exploration areas, improvements in processing methods, new mining techniques for the extraction of high grade ore, and innovative approaches for site reclamation. Two working groups were organized and dealt with the analysis of world uranium resources and the new direction of research in mining and ore processing. Refs, figs, tabs.

To meet new tasks of scientific research on uranium geology in new century

International Nuclear Information System (INIS)

Chen Zuyi

2000-01-01

The author analyses the new situation that the scientific research on uranium geology is facing in the coming new century, and proposes that the guiding idea of the scientific research on uranium geology is to coordinate the general policy of Bureau of Geology--to give the first priority to in-situ leachable sandstone-type uranium deposits. The specific tasks for the scientific research on uranium geology are: to implement regional evaluation and target area selection of in-situ leachable sandstone-type uranium deposits; to develop new techniques and methods of detecting buried in-situ leachable sandstone-type uranium deposits; to turn the genetic model of uranium deposit and deposit model to prospecting model; to strengthen the research on economic geology and the dynamic assessment system of uranium resources and to build up and improve the data base of Meso-Cenozoic basins and sandstone-type uranium deposits. In order to guarantee the successful implementation of the above tasks it is necessary for the Beijing Research Institute of Uranium Geology--the leading unit in scientific research on uranium geology to accelerate bringing up large numbers of young outstanding researchers; to have clear consciousness of market economy and product quality; to given play to advantages of qualified personnel, advanced equipment and modern technology

Guide to the conduct of public meetings as part of the public information process for uranium and thorium mine-mill facilities

International Nuclear Information System (INIS)

1980-01-01

The Canadian Atomic Energy Control Board requires that an applicant for a site approval for a uranium or thorium mine-mill facility inform the public about the project and facilitate public response. For small undertakings, the information requirement may be met by a public meeting organized by the proponents of the project. This guide provides specific instructions on giving notice of the meeting, availability of documentation, choice of a chairperson, agenda, the roles of the proponents and the regulatory agencies, and means of obtaining feedback from the public. (L.L.)

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

Genesis of uranium deposits of the Tono Mine, Japan

International Nuclear Information System (INIS)

Katayama, N.; Kubo, K.; Hirono, S.

1974-01-01

The uranium deposits of the Tono mine, Gifu Prefecture, Japan, occur in the basal part of the Toki group of Miocene age, and are distributed in the tributaries or at the head of channels on the plane of unconformity under the formation. These features characterize the basal ground-water type of uranium deposit, and they are unique in that their typical ore mineral is a zeolite of the heulandite-clinoptilolite group, uranium being adsorbed in it. The paper presents the history of formation of the Tsukiyoshi deposits, the most intensely explored in the Tono mine. The matrices of conglomerates and sandstones of the Toki group usually contain tuffaceous material, which has been montmorillonitized or zeolitized diagenetically. The conduit of uranium-bearing ground waters that migrated from the basement granites into the Tertiary sediments was controlled by the impermeable barriers, which are rocks in which montmorillonite predominated, or by the Tsukiyoshi fault, as well as by channel structures. Where the waters became rather stagnant, uranium was adsorbed in zeolite from them. Enrichment of uranium further proceeded locally as follows. Pyrite was oxidized to produce sulphuric acid solution which leached the uranium that had been adsorbed in zeolite. The pH of the uranium-rich solution became higher and higher in the course of migration and, as soon as it reached about 4, the uranium in the solution was again adsorbed in zeolite, the uranium content of which may have been enriched up to 0.9%. Coffinites have been formed where uranium was accumulated over the adsorption capacity of zeolite or where strongly reducing conditions were maintained by carbonaceous matter. (author)

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

Geochemical dispersion of uranium near prospects in Pennsylvania

International Nuclear Information System (INIS)

Rose, A.W.; Schmiermund, R.L.; Mahar, D.L.

1977-06-01

The geochemical dispersion of U was investigated near sedimentary uranium prospects in eastern and north-central Pennsylvania. Near Jim Thorpe, known uranium occurrences in the Catskill Fm. are limited to the base of the Duncannon member. At Penn Haven Junction, roll-type U deposits with appreciable Pb and Se are localized adjacent to an oxidized tongue of channel-filling conglomeratic sandstone. The channel and encircling U occurrences furnish a large target for geochemical exploration. Selective extractions show that the organic, Fe-oxide, sand and silt fractions of stream sediments are the major hosts for U in stream sediments. Fe-oxides have a greater affinity for U than organic matter but are less abundant. The U content of organic matter is about 10 5 times the U content of stream water. Stream sediments furnish a representative sample of the average content of U, Zn, Cu, and major elements in soils of a drainage basin in north-central Pennsylvania, so a semiquantitative appraisal of weathering uranium occurrences can be made from stream sediments in climates and topography like Pennsylvania. The flux of uranium leaving the basin in solution is about equal to that leaving as sediment. Uranium is considerably less mobile than Ca and Na. A new method of extracting uranium from water samples, using a liquid ion exchanger (Amberlite LA-1), shows promise for simple field application

In situ leaching of uranium: Technical, environmental and economic aspects

International Nuclear Information System (INIS)

1989-01-01

Within the framework of its activities in nuclear raw materials the International Atomic Energy Agency has convened a series of meetings to discuss various aspects of uranium ore processing technology, recovery of uranium from non-conventional resources and development of projects for the production of uranium concentrates including economic aspects. As part of this continuing effort to discuss and document important aspects of uranium production the IAEA convened a Technical Committee Meeting on Technical, Economic and Environmental Aspects of In-Situ Leaching. Although the use of this technique is limited by geological and economic constraints, it has a significant potential to produce uranium at competitive prices. This is especially important in the current uranium market which is mainly characterised by large inventories, excess production capability and low prices. This situation is not expected to last indefinitely but it is unlikely to change drastically in the next ten years or so. This Technical Committee Meeting was held in Vienna from 3 to 6 November 1987 with the attendance of 24 participants from 12 countries. Eight papers were presented. Technical sessions covered in-situ mining research, environmental and licensing aspects and restoration of leached orebodies; the technological status of in-situ leaching, the current status and future prospects of in-situ leaching of uranium in Member States, general aspects of planning and implementation of in-situ projects and the economics of in-situ leaching. Refs, figs and tabs

Environmental design of a uranium mill

International Nuclear Information System (INIS)

Quan, C.H.; Ring, R.J.; McNaughton, S.J.

2002-01-01

In the frame work of the Cleaner Technology Project for Uranium Mining and Milling, Australian Nuclear and Technology Organization (ANSTO), Environment Division of ANSTO has carried out a programme of research which seeks to identify, investigate and develop cleaner technologies that have the potential to minimize the environmental impact of uranium mining and milling. This paper describes three design options of a new uranium mill that can meet environmental, technical and economical objectives. The feasibility of such an approach was examined in the laboratory and in a pilot plant study. (author)

Uranium supply/demand projections to 2030 in the OECD/NEA-IAEA ''Red Book''. Nuclear growth projections, global uranium exploration, uranium resources, uranium production and production capacity

International Nuclear Information System (INIS)

Vance, Robert

2009-01-01

World demand for electricity is expected to continue to grow rapidly over the next several decades to meet the needs of an increasing population and economic growth. The recognition by many governments that nuclear power can produce competitively priced, base load electricity that is essentially free of greenhouse gas emissions, combined with the role that nuclear can play in enhancing security of energy supplies, has increased the prospects for growth in nuclear generating capacity. Since the mid-1960s, 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 2 years) on world uranium resources, production and demand. These updates have been published by the OECD/NEA in what is commonly known as the ''Red Book''. The 2007 edition replaces the 2005 edition and reflects information current as of 1 st January 2007. Uranium 2007: Resources, Production and Demand presents, in addition to updated resource figures, the results of a recent review of world uranium market fundamentals and provides a statistical profile of the world uranium industry. It contains official data provided by 40 countries (and one Country Report prepared by the IAEA Secretariat) on uranium exploration, resources, production and reactor-related requirements. Projections of nuclear generating capacity and reactor-related uranium requirements to 2030 as well as a discussion of long-term uranium supply and demand issues are also presented. (orig.)

Program plan for the National Uranium Mine Tailings Office

International Nuclear Information System (INIS)

1983-03-01

The National Uranium Mine Tailings Program was formed to conduct research into the long-term environmental behaviour of uranium mine tailings. This research is necessary to provide a data base upon which close-cut criteria for uranium mines can be based. The research program to be carried out under the auspices of the National Tailings Program Office has, as its goal, the development of this data base, and the formulation of a series of reports based on that data base. These documents are to be designed to allow the uranium mining industry to produce site-specific close-out plans which will be acceptable to the regulatory authorities. This report addresses the program to be undertaken to meet the above broad objective. It focusses on defining in more specific and explicit terms what the program objectives need to be to meet the close-out requirements currently perceived by the regulatory agencies involved. These program objectives have been refined and summarized as follows: On close-out, the tailings site shall: 1. Meet currently accepted individual exposure criteria, and meet air and water quality regulations. 2. Ensure a predictable decline in release rates of contaminants to the environment. Ideally, this decline would be monotonic in nature. 3. Meet the ALARA principle both at present and into the long-term future. 4. Ensure that the management strategy or technologies employed in close-out shall be of a passive nature and not require ongoing institutional intervention. On the basis of these program objectives, this report identifies specific program product in terms of manuals of practice, guidelines, etc. that are to be produced as a result of program activity. These documents will effectively provide guidance on acceptable close-out technology to the uranium industry and regulatory agencies

Removal of uranium from uranium-contaminated soils -- Phase 1: Bench-scale testing

International Nuclear Information System (INIS)

Francis, C.W.

1993-09-01

To address the management of uranium-contaminated soils at Fernald and other DOE sites, the DOE Office of Technology Development formed the Uranium in Soils Integrated Demonstration (USID) program. The USID has five major tasks. These include the development and demonstration of technologies that are able to (1) characterize the uranium in soil, (2) decontaminate or remove uranium from the soil, (3) treat the soil and dispose of any waste, (4) establish performance assessments, and (5) meet necessary state and federal regulations. This report deals with soil decontamination or removal of uranium from contaminated soils. The report was compiled by the USID task group that addresses soil decontamination; includes data from projects under the management of four DOE facilities [Argonne National Laboratory (ANL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), and the Savannah River Plant (SRP)]; and consists of four separate reports written by staff at these facilities. The fundamental goal of the soil decontamination task group has been the selective extraction/leaching or removal of uranium from soil faster, cheaper, and safer than current conventional technologies. The objective is to selectively remove uranium from soil without seriously degrading the soil's physicochemical characteristics or generating waste forms that are difficult to manage and/or dispose of. Emphasis in research was placed more strongly on chemical extraction techniques than physical extraction techniques

Probabilistic estimates of US uranium supply

International Nuclear Information System (INIS)

Piepel, G.F.; Long, L.W.; McLaren, R.A.; Ford, C.E.

1981-02-01

This report develops and presents probabilistic estimates of total US uranium supply. The word supply is used in the broad sense that both uranium quantity and cost are of interest. Cost implies minimum acceptable selling price rather than market price. Specifically, four types of probability distributions are developed: (1) quantity of US uranium; (2) cost of US uranium; (3) quantity of US uranium available at or below a certain cost; and (4) cost of US uranium given a certain consumption. In this report, uranium refers to recoverable U 3 O 8 (endowment adjusted for mining recovery and milling losses) occurring in both reserve and potential deposits meeting minimum size requirements with minimum grade above 0.01%. Cost includes operating and capital costs, taxes, profit, and cost capital. This definition of cost is often used to better denote this meaning. This definition of cost is contrasted with forward costs, that exclude sunk costs, taxes, and return on investment. Consumption refers to uranium that has been used from the current time to any point in the future. Uranium quantity and consumption are expressed in short tons, while full recovery costs are stated in constant 1980 dollars per pound

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)

Nuclear instrumentation for uranium exploration

International Nuclear Information System (INIS)

Sarma, Ch. V.N.; Sarma, C.V.R.; Sreehari, R.

1999-01-01

Instrumentation required for uranium exploration may be broadly classified based on surface and sub-surface measurement of gamma-ray intensity. Surface measurement of gross and spectral gamma intensity are carried out by employing portable Geiger Mueller/scintillation counters and four-channel spectrometers. Measurement of thoron ( 220 Rn) and radon ( 222 Rn) in the soil gas is being carried out by closed circuit technique using radon measuring system. Radiometric mapping of trenches, pits and mine-faces are carried out using shielded probe with 2π source geometry, whereas logging sonde with instruments through the steel armoured cable are employed for point to 4π geometry. Spectral borehole logging system with built-in multi-channel analyser (MCA) has been developed for the uranium exploration programme for AMD. Note-book PC based high sensitivity air-borne gamma-ray spectrometric survey system has been designed, developed and test flown. (author)

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

78 FR 8203 - Sunshine Act Meetings

Science.gov (United States)

2013-02-05

...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... Meeting) (Contact: Ken Karwoski, 301-415-2752) This meeting will be webcast live at the web address--www... Uranium Recovery (Public Meeting) (Contact: Bill von Till, 301-415-0598) This meeting will be webcast live...

75 FR 9451 - Sunshine Act Meetings

Science.gov (United States)

2010-03-02

... Tuesday, March 2, 2010 9:30 a.m. Briefing on Uranium Recovery (Public Meeting). (Contact: Dominick Orlando, 301-415-6749.) This meeting will be webcast live at the Web address-- http://www.nrc.gov , Week of... NUCLEAR REGULATORY COMMISSION [NRC-2010-0002] Sunshine Act Meetings Agency Holding the Meetings...

Treatment of effluents in uranium industry

International Nuclear Information System (INIS)

Ghosh, S.K.

2009-01-01

Uranium processing technology in India has matured in the last 50 years and is able to meet the country's requirement. Right from mining of the ore to milling and refining, effluents are generated and are being processed for their safe disposal. While the available technology is able to meet the regulatory limits of the effluents, the same may not be enough to meet the increased demand of uranium in the future. The increased population, urbanization and climate change are not only going to decrease the supply of process water but will also place increased restrictions on disposal to environment. This demands technologies that will generate less effluent for disposal and enable reuse and recycle concept to the extent possible. Presently used conventional physical-chemical methods, to contain the contaminants would, therefore, require further refinements. Contaminants like sulfates, chlorides etc in the effluent of uranium mill based on acid leach process are the concerns for the future plants. Hence, there is an urgent need for development of suitable methods for maximum recycle of the process effluents, which will also enable in minimizing the consumption of process water. A suitable membrane based process can be an option leaving a concentrated brine for reuse or for further treatment and disposal

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

Uranium ore deposits: geology and processing implications

International Nuclear Information System (INIS)

Belyk, C.L.

2010-01-01

There are fifteen accepted types of uranium ore deposits and at least forty subtypes readily identified around the world. Each deposit type has a unique set of geological characteristics which may also result in unique processing implications. Primary uranium production in the past decade has predominantly come from only a few of these deposit types including: unconformity, sandstone, calcrete, intrusive, breccia complex and volcanic ones. Processing implications can vary widely between and within the different geological models. Some key characteristics of uranium deposits that may have processing implications include: ore grade, uranium and gangue mineralogy, ore hardness, porosity, uranium mineral morphology and carbon content. Processing difficulties may occur as a result of one or more of these characteristics. In order to meet future uranium demand, it is imperative that innovative processing approaches and new technological advances be developed in order that many of the marginally economic traditional and uneconomic non-traditional uranium ore deposits can be exploited. (author)

Forty years of uranium resources, production and demand in perspective

International Nuclear Information System (INIS)

Price, R.; Barthel, F.; Blaise, J.R.; McMurray, J.

2006-01-01

The NEA has been collecting and analysing data on uranium for forty years. The data and experience provide a number of answers to the questions being asked today, as many countries begin to look at nuclear energy with renewed interest. In terms of uranium resources, the lessons of the past give confidence that uranium supply will remain adequate to meet demand. (authors)

Uranium: the market and adequacy of supply

International Nuclear Information System (INIS)

Cherry, B.H.

1976-01-01

The expansion of the nuclear industry to meet anticipated electrical growth requirements is in part dependent on the ability of the domestic uranium industry to expand anticipated uranium demand. This expansion is potentially constrained by many factors, including resource availability, the mounting of an adequate drilling program, availability of competent people, industry financing capability, and the dynamics of expanding an industry from a relatively small base. In the absence of industry success in mounting adequate expansion efforts, customer involvement in risk taking will be required to develop uranium supplies in a timely manner

Drilling and logging in uranium exploration

International Nuclear Information System (INIS)

Anon.

1976-01-01

The report reviews drilling and logging practices in exploration of uranium ores and summarizes the papers presented in the panel meeting. Recommendations for further research and development are given

Minutes of the WG.2 meeting, 18 October 1978

International Nuclear Information System (INIS)

1978-10-01

The meeting of WG.2B on 18 October 1978 and the meeting of WG.2 on 18-19 October 1978 are summarized. Both meetings gave attention to the projection of enrichment capacities through the year 2000 and to the content of the final report. An appendix presents French views on the proliferation risks of uranium enrichment. Obtaining highly enriched uranium involves the availability of natural uranium and the mastership of an appropriate enrichment technique. Natural uranium is relatively easily available, so proliferation resistance must be found in the enrichment technique. Some difficulties noted are: Bringing the technique to the level of possible utilization, manufacturing enrichment plant components, starting up, operating, concealing a clandestine plant, and converting an existing LEU plant into a HEU plant by re-arrangement or by batch recycling. A qualitative assessment of the major technologies in terms of these criteria is given

75 FR 4428 - Sunshine Act Meeting Notice

Science.gov (United States)

2010-01-27

....m. Briefing on Uranium Recovery (Public Meeting). (Contact: Dominick Orlando, 301-415-6749.) This... NUCLEAR REGULATORY COMMISSION [NRC-2010-0002] Sunshine Act Meeting Notice DATES: Weeks of January... Plans (Public Meeting). (Contact: Quynh Nguyen, 301-415-5844.) This meeting will be webcast live at the...

Documentation of the Uranium Market Model (UMM)

International Nuclear Information System (INIS)

1989-01-01

The Uranium Market Model is used to make projections of activity in the US uranium mining and milling industry. The primary data sources were EIA, the Nuclear Assurance Corporation, and, to a lesser extent, Nuexco and Nuclear Resources International. The Uranium Market Model is a microeconomic simulation model in which uranium supplied by the mining and milling industry is provided to meet the demand for uranium by electric utilities with nuclear power plants. Uranium is measured on a U 3 O 8 (uranium oxide) equivalent basis. The model considers every major production center and utility on a worldwide basis (with Centrally Planned Economies considered in a limited way), and makes annual projections for each major uranium production and consumption region in the world. Typically, nine regions are used: the United States, Canada, Australia, South Africa, Other Africa, Europe, Latin America, the Far East, and Other. Production centers and utilities are identified as being in one of these regions. In general, the model can accommodate any user-provided set of regional definitions and data

Some new tendencies in uranium exploration of Russia

International Nuclear Information System (INIS)

Chen Zuyi

2005-01-01

Russia is a country with abundant uranium resources. However, the uranium production in Russia can meet neither the recent nor the long term demands of nuclear power in the country. In addition, the market price of uranium product during the last two years has been going up continuously. The above facts force Russia to adjust its policy for the exploration and the development of uranium resources in the country, such as to strengthen the prospecting and exploration of the unconformity-related uranium deposit, to try to expand new target stratigraphic horizons of paleo-valley type sandstone-hosted uranium deposit and to discover new uranium-mineralized areas, to do economic-technical re-evaluation of previously explored uranium deposits, and to discover new ore-concentrated regions in known U-metallogenic belts. In order to guarantee the successful performance of the above policy, numerous scientific-technological measures have been taken including intensified research on regional metallogeny of uranium. Based on the above situation, the author proposes some corresponding suggestions for uranium prospecting and exploration in China in the future. (authors)

15. ESRF users meeting

Energy Technology Data Exchange (ETDEWEB)

Fotis C, Kafatos; Ulrich, K.U.; Weib, S.; Rossberg, A.; Scheinost, A.C.; Foerstendorf, H.; Zanker, H.; Meyerheim, H.L.; Sander, D.; Popescu, R.; Kirschner, J.; Robach, O.; Ferrer, S.; Lyman, P.F.; Shneerson, V.L.; Fung, R.; Harder, R.J.; Parihar, S.S.; Johnson-Steigelman, H.T.; Lu, E.D.; Saldin, D.K.; Eastwood, D.S.; Atkinson, D.; Tanner, B.K.; Hase, T.P.A.; Van Kampen, M.; Hjorvarsson, B.; Brown, S.; Thompson, P.; Konovalov, O.; Saint-Martin, E.; Daillant, J.; Luzet, D.; Szlachetko, J.; Barrett, R.; Berset, M.; Dousse, J.C.; Fennane, K.; Hoszowska, J.; Kubala-Kukus, A.; Pajek, M.; Szlachetko, M.; Monaco, A.; Chumakov, A.; Crichton, W.; Van Buerck, I.; Wortmann, G.; Meyer, A.; Ponkratz, U.; Ruffer, R.; Sakurai, Y.; Hiraoka, N.; Itou, M.; Buslaps, T.; Honkimki, V.; Maeno, Y.; Collart, E.; Shukla, A.; Rueff, J.P.; Leininger, Ph.; Ishii, H.; Cai, Y.; Cheong, S.W.; Martins, R.M.S.; Schell, N.; Beckers, M.; Silva, R.; Braz Fernandes, F.M.; Acapito, F.; Seta, M. de; Capelini, G.; Giorgi, M.; Schorr, G.; Geandier, G.; Alves Marques, M.; Barros Marquesa, M.I. de; Cabaco, M.I.; Gaspara, A.M.; Marques, M.P.M.; Amado, A.M.; Amorim da Costa, A.M.; Bruneseaux, F.; Weisbecker, P.; Brandao, M.J.; Aeby-Gautier, E.; Simmonds, H.; Lei, C.; Das, A.; Trolley, D.; Thomas, H.E.; Macdonald, J.E.; Wiegart, L.; Tolan, M.; Struth, B.; Petukhov, A.V.; Thijssen, J.H.J.; Hart, D.C.; Imhof, A.; Van Blaaderen, A.; Dolbnya, I.P.; Snigirev, A.; Mossaid, A.; Snigireva, I.; Reconditi, M.; Brunello, E

2005-07-01

This document gathers the posters presented on the one day and a half long plenary meeting workshop. This meeting workshop is a privileged forum where ESRF users can exchange their views on the latest scientific and technical development involving synchrotron radiation. One poster deals with the investigation of colloid composition and uranium bond structure to see whether the migration of contaminants from abandoned mines could be stimulated or attenuated by colloids. Another poster is dedicated to the investigation of the uranium speciation in covered mine tailings by a combination of micro-spectroscopic and wet chemical approaches. 2 posters deal with the contribution of synchrotron radiation to radiotherapy.

15. ESRF users meeting

International Nuclear Information System (INIS)

Fotis C, Kafatos; Ulrich, K.U.; Weib, S.; Rossberg, A.; Scheinost, A.C.; Foerstendorf, H.; Zanker, H.; Meyerheim, H.L.; Sander, D.; Popescu, R.; Kirschner, J.; Robach, O.; Ferrer, S.; Lyman, P.F.; Shneerson, V.L.; Fung, R.; Harder, R.J.; Parihar, S.S.; Johnson-Steigelman, H.T.; Lu, E.D.; Saldin, D.K.; Eastwood, D.S.; Atkinson, D.; Tanner, B.K.; Hase, T.P.A.; Van Kampen, M.; Hjorvarsson, B.; Brown, S.; Thompson, P.; Konovalov, O.; Saint-Martin, E.; Daillant, J.; Luzet, D.; Szlachetko, J.; Barrett, R.; Berset, M.; Dousse, J.C.; Fennane, K.; Hoszowska, J.; Kubala-Kukus, A.; Pajek, M.; Szlachetko, M.; Monaco, A.; Chumakov, A.; Crichton, W.; Van Buerck, I.; Wortmann, G.; Meyer, A.; Ponkratz, U.; Ruffer, R.; Sakurai, Y.; Hiraoka, N.; Itou, M.; Buslaps, T.; Honkimki, V.; Maeno, Y.; Collart, E.; Shukla, A.; Rueff, J.P.; Leininger, Ph.; Ishii, H.; Cai, Y.; Cheong, S.W.; Martins, R.M.S.; Schell, N.; Beckers, M.; Silva, R.; Braz Fernandes, F.M.; Acapito, F.; Seta, M. de; Capelini, G.; Giorgi, M.; Schorr, G.; Geandier, G.; Alves Marques, M.; Barros Marquesa, M.I. de; Cabaco, M.I.; Gaspara, A.M.; Marques, M.P.M.; Amado, A.M.; Amorim da Costa, A.M.; Bruneseaux, F.; Weisbecker, P.; Brandao, M.J.; Aeby-Gautier, E.; Simmonds, H.; Lei, C.; Das, A.; Trolley, D.; Thomas, H.E.; Macdonald, J.E.; Wiegart, L.; Tolan, M.; Struth, B.; Petukhov, A.V.; Thijssen, J.H.J.; Hart, D.C.; Imhof, A.; Van Blaaderen, A.; Dolbnya, I.P.; Snigirev, A.; Mossaid, A.; Snigireva, I.; Reconditi, M.; Brunello, E.

2005-01-01

This document gathers the posters presented on the one day and a half long plenary meeting workshop. This meeting workshop is a privileged forum where ESRF users can exchange their views on the latest scientific and technical development involving synchrotron radiation. One poster deals with the investigation of colloid composition and uranium bond structure to see whether the migration of contaminants from abandoned mines could be stimulated or attenuated by colloids. Another poster is dedicated to the investigation of the uranium speciation in covered mine tailings by a combination of micro-spectroscopic and wet chemical approaches. 2 posters deal with the contribution of synchrotron radiation to radiotherapy

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)

Uranium distribution and sandstone depositional environments: oligocene and upper Cretaceous sediments, Cheyenne basin, Colorado

International Nuclear Information System (INIS)

Nibbelink, K.A.; Ethridge, F.G.

1984-01-01

Wyoming-type roll-front uranium deposits occur in the Upper Cretaceous Laramie and Fox Hills sandstones in the Cheyenne basin of northeastern Colorado. The location, geometry, and trend of specific depositional environments of the Oligocene White River and the Upper Cretaceous Laramie and Fox Hills formations are important factors that control the distribution of uranium in these sandstones. The Fox Hills Sandstone consists of up to 450 ft (140 m) of nearshore marine wave-dominated delta and barrier island-tidal channel sandstones which overlie offshore deposits of the Pierre Shale and which are overlain by delta-plain and fluvial deposits of the Laramie Formation. Uranium, which probably originated from volcanic ash in the White River Formation, was transported by groundwater through the fluvial-channel deposits of the White River into the sandstones of the Laramie and Fox Hills formations where it was precipitated. Two favorable depositional settings for uranium mineralization in the Fox Hills Sandstone are: (1) the landward side of barrier-island deposits where barrier sandstones thin and interfinger with back-barrier organic mudstones, and (2) the intersection of barrier-island and tidal channel sandstones. In both settings, sandstones were probably reduced during early burial by diagenesis of contained and adjacent organic matter. The change in permeability trends between the depositional strike-oriented barrier sandstones and the dip-oriented tidal-channel sandstones provided sites for dispersed groundwater flow and, as demonstrated in similar settings in other depositional systems, sites for uranium mineralization

Uranium 2010: The Future is U. Proceedings Volume 1 and 2

International Nuclear Information System (INIS)

Lam, E.K.; Rowson, J.W.; Ozberk, E.

2010-01-01

Uranium 2010, 'The Future is U' is the Third International Conference on Uranium and is organized by the Hydrometallurgy Section of the Metallurgical Society of the Canadian Institute of Mining, Metallurgy and Petroleum (CIM) and constitutes its 40th Annual Hydrometallurgy Meeting. Uranium 2010 Conference is indeed an international conference with over 400 delegates from 26 countries. Over 170 papers and posters covering various topics in the uranium fuel cycle are presented in the plenary and 25 sessions over three days. The conference provided an excellent opportunity for industry executives, representatives of universities and research institutes, design engineers, plant operators, regulators, policy makers, as well as metallurgical, environmental and health experts from all over the world to meet their colleagues, to discuss common interests and concerns, to network, to renew friendship or form new lasting friendships. (author)

National Uranium Resource Evaluation: Lawton Quadrangle, Oklahoma and Texas

International Nuclear Information System (INIS)

Al-Shaieb, Z.; Thomas, R.G.; Stewart, G.F.

1982-04-01

Uranium resources of the Lawton Quadrangle, Oklahoma and Texas, were evaluated to a depth of 1500 m using National Uranium Resource Evaluation criteria. Five areas of uranium favorability were delineated. Diagenetically altered, quartzose and sublithic, eolian and marginal-marine sandstones of the Permian Rush Springs Formation overlying the Cement Anticline are favorable for joint-controlled deposits in sandstone, non-channel-controlled peneconcordant deposits, and Texas roll-front deposits. Three areas contain lithologies favorable for channel-controlled peneconcordant deposits: arkosic sandstones and granule conglomerates of the Permian Post Oak Conglomerate south of the Wichita Mountains; subarkosic and sublithic Lower Permian fluvio-deltaic and coastal-plain sandstones of the eastern Red River Valley; and subsurface arkosic, subarkosic, and sublithic alluvial-fan and fan-delta sandstones of the Upper Pennsylvanian-Lower Permian sequence in the eastern Hollis Basin. The coarse-grained facies of the Cambrian Quanah Granite and genetically related aplite and pegmatite dikes in the Wichita Mountains are favorable for orthomagmatic and autometasomatic deposits, respectively

Uranium in Canada

International Nuclear Information System (INIS)

1989-01-01

In 1988 Canada's five uranium producers reported output of concentrate containing a record 12,470 metric tons of uranium (tU), or about one third of total Western world production. Shipments exceeded 13,200 tU, valued at $Cdn 1.1 billion. Most of Canada's uranium output is available for export for peaceful purposes, as domestic requirements represent about 15 percent of production. The six uranium marketers signed new sales contracts for over 11,000 tU, mostly destined for the United States. Annual exports peaked in 1987 at 12,790 tU, falling back to 10,430 tU in 1988. Forward domestic and export contract commitments were more than 70,000 tU and 60,000 tU, respectively, as of early 1989. The uranium industry in Canada was restructured and consolidated by merger and acquisition, including the formation of Cameco. Three uranium projects were also advanced. The Athabasca Basin is the primary target for the discovery of high-grade low-cost uranium deposits. Discovery of new reserves in 1987 and 1988 did not fully replace the record output over the two-year period. The estimate of overall resources as of January 1989 was down by 4 percent from January 1987 to a total (measured, indicated and inferred) of 544,000 tU. Exploration expenditures reached $Cdn 37 million in 1987 and $59 million in 1988, due largely to the test mining programs at the Cigar Lake and Midwest projects in Saskatchewan. Spot market prices fell to all-time lows from 1987 to mid-1989, and there is little sign of relief. Canadian uranium production capability could fall below 12,000 tU before the late 1990s; however, should market conditions warrant output could be increased beyond 15,000 tU. Canada's known uranium resources are more than sufficient to meet the 30-year fuel requirements of those reactors in Canada that are now or are expected to be in service by the late 1990s. There is significant potential for discovering additional uranium resources. Canada's uranium production is equivalent, in

75 FR 6413 - Sunshine Act Meeting Notice

Science.gov (United States)

2010-02-09

... a.m. Briefing on Uranium Recovery (Public Meeting). (Contact: Dominick Orlando, 301-415-6749.) This... NUCLEAR REGULATORY COMMISSION [NRC-2010-0002] Sunshine Act Meeting Notice DATES: Weeks of February.... Briefing on Regional Programs--Programs, Performance, and Future Plans (Public Meeting). (Contact: Richard...

Uranium-contaminated soil pilot treatment study

International Nuclear Information System (INIS)

Turney, W.R.J.R.; Mason, C.F.V.; Michelotti, R.A.

1996-01-01

A pilot treatment study is proving to be effective for the remediation of uranium-contaminated soil from a site at the Los Alamos National Laboratory by use of a two-step, zero-discharge, 100% recycle system. Candidate uranium-contaminated soils were characterized for uranium content, uranium speciation, organic content, size fractionization, and pH. Geochemical computer codes were used to forecast possible uranium leach scenarios. Uranium contamination was not homogenous throughout the soil. In the first step, following excavation, the soil was sorted by use of the ThemoNuclean Services segmented gate system. Following the sorting, uranium-contaminated soil was remediated in a containerized vat leach process by use of sodium-bicarbonate leach solution. Leach solution containing uranium-carbonate complexes is to be treated by use of ion-exchange media and then recycled. Following the treatment process the ion exchange media will be disposed of in an approved low-level radioactive landfill. It is anticipated that treated soils will meet Department of Energy site closure guidelines, and will be given open-quotes no further actionclose quotes status. Treated soils are to be returned to the excavation site. A volume reduction of contaminated soils will successfully be achieved by the treatment process. Cost of the treatment (per cubic meter) is comparable or less than other current popular methods of uranium-contamination remediation

World nuclear fuel market. Eighteenth annual meeting

International Nuclear Information System (INIS)

Anon.

1991-01-01

The papers presented at the eighteenth World Nuclear Fuels Market meeting are cataloged separately. This volume includes information on the following areas of interest: world uranium enrichment capacity and enriched uranium inventories; the impact of new enrichment technologies; predictions of future market trends; non-proliferation aspects of nuclear trade; and a debate as to whether uranium can be successfully traded on a commodities exchange

Successive composition of two laser channels upon excitation of He-Ar-Xe (2.03 μm) and Ar-Xe (1.73 μm) mixtures by uranium fission fragments

International Nuclear Information System (INIS)

Pikulev, A A; Tsvetkov, V M; Sosnin, P V; Sinyanskii, A A

2009-01-01

The operation efficiency of the scheme with successive composition of two laser channels upon excitation of the active medium by uranium-235 fission fragments is studied experimentally and numerically. For the He:Ar:Xe = 380:380:1 mixture (at a pressure of 1 atm and the lasing wavelength λ = 2.03 μm) the maximum lasing power of a double channel (1 kW) is almost twice that of a single channel (540 W). Calculations show that in the case of ideal composition (without losses on mirrors) the lasing power of the double channel can be increased to 1.2 kW. For the Ar:Xe = 380:1 mixture (the pressure is 0.5 atm, λ = 1.73 μm) the maximum lasing power of the double channel (620 W) is slightly above that of the single channel (520 W), which is caused by the losses on aluminum mirrors employed for channel doubling and by a negative effect of optical inhomogeneities. In the case of ideal composition, the lasing power can be increased to 830 W. (lasers)

Uranium mineralization in the Molteno and Elliot Formations

International Nuclear Information System (INIS)

Le Roux, J.P.

1990-01-01

To date very little has been published on the uranium deposits of the Molteno and Elliot Formations. Two selected deposits from these formations are described and compared to the uranium occurrences of the Beaufort Group. Whereas the latter are generally confined to channel zones due to the fine grain size and impermeable nature of the host sandstones, uranium in the Molteno and Elliot Formations seems to be concentrated in the less permeable 'island' areas. An apparent association with dolerite sills and dykes also suggests that the host sandstones were still sufficiently permeable after intrusion of the dolorite so that ground waters could remobilize the uranium. This agrees with recently published isotopic ages for the mineralization. There is a distinct possibility that roll-type uranium deposits may be present in the Molteno and Elliot Formations, and any future exploration should bear this in mind. 9 figs., 1 tab., 16 refs

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

National Uranium Resource Evaluation: Hutchinson Quadrangle, Kansas

International Nuclear Information System (INIS)

Fair, C.L.; Smit, D.E.; Gundersen, J.N.

1982-08-01

Surface reconnaissance and detailed subsurface studies were done within the Hutchinson Quadrangle, Kansas, to evaluate uranium favorability in accordance with National Uranium Resource Evaluation criteria. These studies were designed in part to follow up prior airborne radiometric, hydrogeochemical, and stream-sediment surveys. Over 4305 well records were examined in the subsurface phase of this study. The results of these investigations indicate environments favorable for channel-controlled peneconcordant sandstone deposits in rocks of Cretaceous age and for Wyoming and Texas roll-type deposits in sandstones of Pennsylvanian age. The Cretaceous sandstone environments exhibit favorable characteristics such as a bottom unconformity; high bedload; braided, fluvial channels; large-scale cross-bedding; and an anomalous outcrop. The Pennsylvanian sandstone environments exhibit favorable characteristics such as arkosic cross-bedded sandstones, included pyrite and organic debris, interbedded shales, and gamma-ray log anomalies. Environments considered unfavorable for uranium deposits are limestone and dolomite environments, marine black shale environments, evaporative precipitate environments, and some fluvial sandstone environments. Environments considered unevaluated due to insufficient data include Precambrian plutonic, metamorphic, and sedimentary rocks, even though a large number of thin sections were available for study

The development condition of longitudinal channels of a Lower Cretaceous formation and its perspective for sandstone type uranium deposits in the Erlian basin, northern China

International Nuclear Information System (INIS)

Qin, M.; Xu, Q.; Liu, W.; Song, J.; Chen, D.; Wei, S.

2014-01-01

The palaeochannel, which is classified as basal and interformational types on the basis of geological setting, is an important host for the sandstone type uranium deposit. Diversities exist in development conditions and uranium minerogenetic potential of the two types of palaeochanneles. The Erlian basin, about 105 km"2 and adjacent to channel-type uranium deposit provinces in Russia and Mongolia, is one of main uraniferous basins in the north of China. It is significant to research into development conditions of palaeochannels for uranium mineral exploration in the Erlian basin. 1. Geological background: The Erlian basin consists of five depressions which divide the basin and form alternations with uplifts and depressions. Sedimentary capping strata of the basin mainly is the Lower Cretaceous Bayanhua group (K1b) which consists of the Aershan group (K1ba), Tenger group (K1bt) and Saihan group (K1bs) from bottom to top. The Saihan group, which is the product in the phase of depression, is the most important uranous strata in the Erlian basin. 2. Development characteristic and condition of the longitudinal palaeochannel of the Saihan formation: Large-scale longitudinal multi-palaeochannels are identified in the center and northeast of the basin, such as the QiHaRiGeTu-SaiHanGaoBi palaeochannel (CH01), BaYanWuLa palaeochannel (CH02) and GaoLiHan palaeochanne l(CH03), et al., which character the length from several 10s of km to 100 km, width of several 10s of km and thickness of sand bodies from 20 m to 130 m, more or less. Palaeochannels of the Saihan formation are interformational type because the underlay is argillite at the top of the Tenggeer formation. Restrictive geological environments and conditions are necessary to form longitudinal channels and mainly are as follows: (1) the basin in the sustained step of depression; (2) sharp gradient (>5°?) in parts of sub-depressions and sufficient sedimentary supply from the upstream; (3) elongate erosional lowlands or

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

The sedimentology and uranium mineralisation of the Banksgaten deposit, Sutherland district

International Nuclear Information System (INIS)

Le Roux, J.P.

1982-08-01

As part of its research program, NUCOR carried out a sedimentological investigation of the Banksgaten uranium deposit discovered by Esso Minerals. The Banksgaten prospect is situated on a promontory of the Nuweveld Escarpment, 35 km south-east of Sutherland. The six prominent sandstone units exposed in the study area form part of the arenaceous Oukloof Member of the Teekloof Formation. Palaeocurrent studies show a wide variation in transport direction. However, the vector mean palaeocurrent trend is towards the north-north-east. The sedimentological environment is a distal braided river forming part of a deltaic plain. The uranium mineralisation occurs on three stratigraphic levels and is concentrated almost exclusively in the channels of the different sandstones. These channels are vertically superimposed and probably inherited the drainage pattern of pre-existing channels

Uranium Enrichment, an overview

International Nuclear Information System (INIS)

Coates, J.H.

1994-01-01

This general presentation on uranium enrichment will be followed by lectures on more specific topics including descriptions of enrichment processes and assessments of the prevailing commercial and industrial situations. I shall therefore avoid as much as possible duplications with these other lectures, and rather dwell on: some theoretical aspects of enrichment in general, underlying the differences between statistical and selective processes, a review and comparison between enrichment processes, remarks of general order regarding applications, the proliferation potential of enrichment. It is noteworthy that enrichment: may occur twice in the LWR fuel cycle: first by enriching natural uranium, second by reenriching uranium recovered from reprocessing, must meet LWR requirements, and in particular higher assays required by high burn up fuel elements, bears on the structure of the entire front part of the fuel cycle, namely in the conversion/reconversion steps only involving UF 6 for the moment. (author). tabs., figs., 4 refs

Trends in uranium and their significance for investors in mining shares

International Nuclear Information System (INIS)

Fishlock, D.

1975-01-01

After a general introduction on the nuclear industry and uranium the following points are discussed: uranium supply and demand; the financing of exploration and exploitation in order to meet an expected demand of seven or ten times the present world output of uranium within 25 years; the idiosyncrasies of government policies among the uranium-rich nations, and whether and how they can be reconciled with supply and demand; environmental problems, including the activities of nuclear energy's opponents, which in turn could greatly influence supply and demand

75 FR 8155 - Sunshine Act; Notice of Meeting

Science.gov (United States)

2010-02-23

....m. Briefing on Uranium Recovery (Public Meeting) (Contact: Dominick Orlando, 301-415-6749). This... NUCLEAR REGULATORY COMMISSION [NRC-2010-0002] Sunshine Act; Notice of Meeting DATES: Weeks of....m. Affirmation Session (Public Meeting) (Tentative). Entergy Nuclear Operations, Inc. (Indian Point...

Effective utilization of geomorphology in uranium exploration: a success story from Meghalaya, northeast India

International Nuclear Information System (INIS)

Mamallan, R.; Awati, A.B.; Gupta, K.R.; Kak, S.N.

1995-01-01

The southern fringe of Meghalaya plateau displays a spectacular development of erosional landforms in the thick sedimentary cover of Cretaceous-Tertiary formations. Mahadek formation, the lower member of this sequence, comprises both continental and marginal marine sediments while all the overlying formations are mainly of marine origin. In the study area all the tertiary formations are eroded away, leaving exposed the continental part of the Mahadek formation, which comprises channel-filled and floodplain sediments. Geomorphologically, both these units express themselves as cuestas but significant textural differences were observed, enabling us to discriminate them in aerial photographs. It is known that the channel-filled sedimentary unit incorporates many favourable geological and geochemical characters to host uranium mineralization. The domiasiat uranium deposit occurs in this unit only. By virtue of its distinct geomorphology, three domains of channel-filled sediments were demarcated in aerial photographs. Follow-up radiometric field checks on one of these domains, near the confluence of Wah Blei and Kynshiang rivers, have led to the discovery of significant uranium occurrences, opening up promising new avenues for uranium exploration in Megahalya. (author). 4 refs., 2 figs

A data base for PHW reactor operating on a once-through, low enriched uranium-thorium cycle

International Nuclear Information System (INIS)

Lungu, S.

1984-04-01

The study of a detailed data base for a new once-through uranium-thorium cycle using low enriched uranium (4 and 5,5% wt. U-235) and distinct UO 2 and ThO 2 fuel channels has been performed. With reference to a standard 638 MWe CANDU-type PHWR with 380 channels, evaluation of economics, fuel behaviour and safety has been performed. The Feinberg-Galanin method (code FEINGAL) has been used for calculation of axial flux distribution. All parameters have been provided by LATREP code following up the irradiation history. Economical assessment has shown that this fuel cycle is competitive with the natural uranium fuel cycle for 1979-based values of the parameters. Fuel behaviour and safety features modelling has shown that core behaviour of the uranium-thorium reactor under abnormal and accident conditions would be at least as good as that of the standard natural uranium reactor

A coalescence model for uranium exploration

International Nuclear Information System (INIS)

Stuart-Williams, V.; Taylor, C.M.

1983-01-01

Uranium mineralization was found in the Pristerognathus-Diictodon Assemblage Zone of the Teekloof Formation, Beaufort Group, west of Beaufort West, Cape Province, South Africa. All the anomalies can be related to a single mineralization model. Mineralization is found at the termination of a silt parting between two coalescing sandstones and lies in the lower sandstone as an inclined zone dipping downflow from the termination of the silt parting. The existence of primary Eh-pH gradient is indicated by a uranium-molybdenum zonation, the molybdenum lying above the uranium mineralization. The upper sandstone was an oxidizing fluvial channel in an arid environment through which uranyl carbonate was being transported in solution. Carbonaceous material undergoing anaerobic bacterial breakdown generated a weakly reducing fluid in the lower sandstone. Carbonaceous material at the REDOX front developed between the two mixing fluids at the point of sandstone coalescence reduced uranyl carbonates in solution. Once reduced the uranium minerals remained stable because the conditions in the REDOX front were only very weakly oxidizing. As floodplain aggradation continued, the upper sandstone was buried and the entire sandstone couplet became reducing, permanently stabilizing the uranium mineralization

Recent activities and trends in the uranium market

International Nuclear Information System (INIS)

Kwasny, R.; Lohrey, K.; Max, A.

2006-01-01

Implementing the large number of nuclear power plant projects worldwide presupposes a considerable increase in the production of natural uranium. Preparations have been made: Higher uranium prices stimulate investments into future mines and into uranium exploration. In some countries, the uranium industry is undergoing structural changes so as to be able to meet future requirements. The terms and conditions laid down in long-term uranium supply contracts (prices and fixed delivery volumes) provide present and future producers with the necessary security in investing and planning. The electricity utilities have accepted the shift from a former 'buyer's market' to a 'seller's market' and adapted their uranium supply strategies accordingly. Numerous uranium mines, most of them small, with relatively low uranium ore concentrations, are under construction or in the commissioning phase. However, as secondary sources (fuels not made up of fresh uranium) are gradually coming to an end, many more uranium deposits need to be found and developed to commercial maturity in order to ensure uranium supply also on the long term. The steadily growing industries in the front end and the back end of the fuel cycle have intensified concerns about the non-proliferation of nuclear fuels. However, political considerations with respect to proliferation resistant uranium supply strategies have met with scepticism right from the outset. (orig.)

Environmental management of uranium mining projects in Australia - a national perspective

International Nuclear Information System (INIS)

Usback, R.

1987-01-01

The environmental management of uranium mining projects in Australia is described. The paper reveals that the environmental examination of uranium mining proposals, and the establishment of environmental protection measures for such proposals, have been integrated with other requirements to meet the needs of local communities. (U.K.)

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)

Scrap uranium recycling via electron beam melting

International Nuclear Information System (INIS)

McKoon, R.

1993-11-01

A program is underway at the Lawrence Livermore National Laboratory (LLNL) to recycle scrap uranium metal. Currently, much of the material from forging and machining processes is considered radioactive waste and is disposed of by oxidation and encapsulation at significant cost. In the recycling process, uranium and uranium alloys in various forms will be processed by electron beam melting and continuously cast into ingots meeting applicable specifications for virgin material. Existing vacuum processing facilities at LLNL are in compliance with all current federal and state environmental, safety and health regulations for the electron beam melting and vaporization of uranium metal. One of these facilities has been retrofitted with an auxiliary electron beam gun system, water-cooled hearth, crucible and ingot puller to create an electron beam melt furnace. In this furnace, basic process R ampersand D on uranium recycling will be performed with the goal of eventual transfer of this technology to a production facility

Uranium exploration in Australia

International Nuclear Information System (INIS)

Battey, G.C.; Hawkins, B.W.

1977-01-01

As a result of exploration which recommenced in 1966 Australia's uranium reserves increased from 6,200 tonnes in 1967 to 227,000 tonnes uranium by June 1976. Most discoveries in the early 1950's were made by prospectors. The increase in reserves during the past decade is the result of exploration by companies utilising improved technology in areas selected as geologically favourable. These reserves were established at relatively low cost. In the Alligator Rivers Uranium Province the ''vein'' type deposits at Jabiluka, Ranger, Koongarra and Nabarlek contain 17% of the world's reserves. Most of these discoveries resulted from the investigation of airborne radiometric anomalies but cover over the prospective host rocks will necessitate the future use of costlier and more indirect exploration techniques. There was exploration for sandstone type uranium deposits in most of Australia's sedimentary basins. The greatest success was achieved in the Lake Frome Basin in South Australia. Other deposits were found in the Ngalia and Amadeus Basins in Central Australia and in the Westmoreland area, N.W. Queensland. A major uranium deposit was found in an unusual environment at Yeelirrie, Western Australia where carnotite occurs in a caliche and clay host which fills a shallow, ancient drainage channel. Although caliche occurrences are relatively widespread on the Precambrian shield no other economic deposit has been found. Recent discoveries in the Georgetown area of Queensland indicate the presence of another uranium province but it is too early to assess its potential. The ore occurs in clastic sediments at the base of a volcanic sequence overlying a Precambrian basement. Several companies which have established large uranium reserves have a number of additional attractive prospects. Exploration activity in Australia in 1975 was at a lower level than in previous years, but the potential for discovering further deposits is considered to be high

Stripping of Uranium (IV) from D2EHPA + TBP system with ammonium oxalate and its recovery as uranium peroxide

International Nuclear Information System (INIS)

Singh, D.K.; Singh, H.

2014-01-01

Uranium is an important fissile material for the generation of electricity by nuclear reactors. To obtain uranium as a final product meeting the stringent nuclear specifications, many process steps are involved starting from ore processing to the precipitation of yellow cake. Solvent extraction is one of the process industrially adopted worldwide to achieve such purity of uranium from leach liquor and usually uses amine or organophosphorus types of extractant depending upon the composition of feed material. In solvent extraction technique, stripping is a prominent hydrometallurgical operation which brings the metal values of interest in aqueous solution for further treatment. In the case of uranium, stripping is dependent on its oxidation state. For hexavalent state generally carbonate solutions are used, where as in the case of tetravalent form salt solution such as ammonium oxalate is effective. Use of ammonium oxalate as stripping agent for tetravalent uranium from pyrophosphoric acid has been reported in patent however the details are not disclosed. In the present investigation an effort has been made to investigate the stripping behaviour of uranium from a synthetically loaded synergistic solvent mixture of uranium in tetravalent state

A new uranium automatic analyzer

International Nuclear Information System (INIS)

Xia Buyun; Zhu Yaokun; Wang Bin; Cong Peiyuan; Zhang Lan

1993-01-01

A new uranium automatic analyzer based on the flow injection analysis (FIA) principle has been developed. It consists of a multichannel peristaltic pump, an injection valve, a photometric detector, a single-chip microprocessor system and electronic circuit. The new designed multifunctional auto-injection valve can automatically change the injection volume of the sample and the channels so that the determination ranges and items can easily be changed. It also can make the instrument vary the FIA operation modes that it has functions of a universal instrument. A chromatographic column with extractant-containing resin was installed in the manifold of the analyzer for the concentration and separation of trace uranium. The 2-(5-bromo-2-pyridylazo)-5-diethyl-aminophenol (Br-PADAP) was used as colour reagent. Uranium was determined in the aqueous solution by adding cetyl-pyridium bromide (CPB). The uranium in the solution in the range 0.02-500 mg · L -1 can be directly determined without any pretreatment. A sample throughput rate of 30-90 h -1 and reproducibility of 1-2% were obtained. The analyzer has been satisfactorily applied to the laboratory and the plant

Extracting Uranium from Seawater: Benefits, Risks and Policy Implication

Energy Technology Data Exchange (ETDEWEB)

Ismail, Aznan Fazli; Yim, Man-Sung; Marsh, Matthew [KAIST, Daejon (Korea, Republic of)

2015-05-15

One of the key issues that need to be addressed regarding the future of nuclear power is the availability of uranium. The most economical way to this day of providing uranium for nuclear energy has been through conventional mining. However, the current projection of the well-known, easily obtainable sources of uranium indicates that global nuclear industry can be supported through the end of the century under the once-through cycle. It, however, could be extended up to 250 years if the speculative uranium sources are taken into account. Uranium is also available in seawater. Extracting uranium from seawater has both pros and cons. The only main obstacles at this point is it not economically competitive compared to the conventional mining. Solving this issue will open up a new era of the way of extracting uranium to meet the future requirement of nuclear energy. As the uranium seawater extraction technology is rapidly being developed and might become feasible in the near future, an appropriate mechanism are required to safeguard the extraction technology.

Application of the small trackless equipments in Benxi uranium mine

International Nuclear Information System (INIS)

Lei Zeyong; Liu Shengzheng

2004-01-01

The application of the small trackless equipments in Benxi uranium mine is introduced in this paper. The running data of these equipments are tested and discussed. It is proved that these equipments can run normally and meet the needs of uranium mining. Some experimental data will be very useful for building small mines and rebuilding small mines in China

A view from the uranium industry

International Nuclear Information System (INIS)

Michel, B.M.

2000-01-01

We should all be encouraged by what is emerging in terms of deregulation, consolidation, and privatization of the nuclear industry and in terms of an increasing public realization that nuclear technology is safe and environmentally clean. The greater transparency which flows out of the restructuring of our industry encourages accountability and promotes excellence in every way. There are early signs of a changing public attitude toward nuclear technology. Opponents find it more difficult to refute facts and for some, impossible to come up with credible alternatives. The uranium industry has undergone much of the restructuring which the electricity business faces today. Consolidation as a result of market forces and privatization, has been with the uranium industry for quite a while. Today the industry is dominated by only a few players. It is in this highly competitive arena of the uranium market place that the nuclear electricity producers meet the uranium suppliers. That interaction is played out in the familiar supply and demand scenario

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

Uranium exploration of Samar Island

International Nuclear Information System (INIS)

Santos, G. Jr.

1979-02-01

Uranium exploration is being undertaken to meet the requirements of the Philippine Nuclear Power Plant-1 (PNPP-1) programmed to operate in 1982, for about 140 metric tons annually or 2664 MT of U 3 O 8 up to the year 2000. Samar was chosen as the survey pilot project and the method used was a geochemical reconnaissance or low density observation survey to delineate broad areas where follow-up uranium surveys may be undertaken. Stream sediments or surface waters were collected at each sampling point at a density of one sample per 20-25 sq. km. The conductance and pH of the water were measured with a conductivity meter and pH respectively. Radioactivity was determined using a portable scintillometer. The stream sediment and heavy mineral samples were analyzed for uranium (U), copper (CCu), lead (Pb), zinc (Zn), manganese (Mn), silver (Ag), cobalt (Co), nickel (Ni). Water samples were analyzed for uranium only. The solid samples were digested in an acid mixture of 85% concentrated nitric acid and 15% concentrated hydrochloric acid, and the leachable uranium was determined using a fluorimeter. The detection limits for uranium were 0.3 ppb and 0.3 ppm for water and solid samples, respectively. Analysis for Cu, Pb, Zn, Mn, Ag, Co, and Ni were done by Atomic Absorption Spectrophotometry using the same leaching solution prepared for uranium analysis. Over 9000 determinations were done on nearly 1600 samples. The survey delineated at least two areas where follow-up surveys for uranium are warranted. These areas are the San Isidro - Catarman in Northwestern Samar, and the vicinity of Bagacay mines in Central Samar

The view of Japanese utilities on uranium procurement

International Nuclear Information System (INIS)

Kishida, Tetsuji

1991-01-01

Since Japan is entirely dependent on imports to meet its demand for uranium, its foremost consideration is security of supply. From this point of view, the long-term strategy for uranium procurement followed by the Japanese Government and utilities can be summarized in four points; diversification of supply sources, long term contracts, holding of sufficient inventory and self-supply (ie. involvement in exploration activity and mine development). Under this basic strategy, Japanese utilities have made decisions on which suppliers they buy uranium from, and which purchasing method to adopt, based on the principles of securing stable sources of supply and stable prices. This position is reviewed and discussed. (author)

Assessment of uranium resources and supply

International Nuclear Information System (INIS)

1991-04-01

Uranium as nuclear fuel is an important energy resource, which generates about one-sixth of the world's total electricity generated in 1989. The current nuclear electricity generating capacity of 318 GW(e) is expected to grow by over 38% to 440 GW(e) in the year 2005. The world's uranium requirements are expected to increase similarly from about 52,000 t U in 1989 to over 70,000 t U in 2005. Beyond this time the uranium requirements are projected to reach over 80,000 t U in 2030. It was the objective of the Technical Committee Meeting on Assessment of Uranium Resources and Supply, organized by the IAEA and held in Vienna, between 29 August - 1 September 1989, to attract specialists in this field and to provide a forum for the presentation of reports on the methodologies and actual projects carried out in the different countries. Of special interest was the participation of specialists from some countries which did not or only occasionally co-operate with the IAEA in the projects related to the assessment of uranium resources and supply. A separate abstract was prepared for each of the 19 papers. Refs, figs and tabs

Experiment on bio-leaching of associated molybdenum and uranium ore

International Nuclear Information System (INIS)

Zheng Ying; Fan Baotuan; Liu Jian; Meng Yunsheng; Liu Chao

2007-01-01

Column leaching experiment results on associated molybdenum uranium ore by bacteria (T. f) are introduced. The ore are leached for 210 days using bacteria domesticated to tolerate molybdenum, the leaching of uranium is of 98% and leaching of molybdenum is of 41%. Sulphuric acid produced by bio-oxidation of sulfides in ore can meet the demand of ore leaching. (authors)

Uranium supply to 2000, Canada and the world

International Nuclear Information System (INIS)

Williams, R.M.

1976-01-01

Annual world uranium demand is expected to increase 12-to 15-fold by the year 2000. In response to this demand, annual world production capacity will grow by 35 per cent to 44 000 tonnes of uranium by 1978. Further expansion is possible, contingent on early production decisions, sufficient to meet annual world requirements approaching 90 000 tonnes of uranium in 1985. Known low-cost uranium reserves do not provide sufficient forward reserves for production levels forecast beyond 1979, and known higher-cost reserves extend the satisfactory forward reserve position by only five years. Since 1965, Canada has dropped from first to fourth place, after Australia, South Africa, and the United States, in terms of low-cost, reasonably assured resources. Canada continues to rank second, after the United States, in terms of production. Canadian nuclear fuel requirements are expected to grow by 14 per cent a year, approaching 12,600 tonnes of uranium in 2000. (author)

Fluorimetric routine determination of uranium in urine samples

International Nuclear Information System (INIS)

Widua, L.; Schieferdecker, H.; Hezel, U.

With a modified RA 2 reflectance accessory for the Zeiss PMQII/PMQ3 spectrophotometer, uranium in urine was detected with higher sensitivity. A quick method is now available with a detection limit of <2 μg U/1 urine for the determination of possible uranium incorporations, whose sensitivity meets the requirements of radiation protection. Compared with other extraction methods, the instrument outlay and the required working time are small. The total error of the method is below 5 percent

Eocene fluvial drainage patterns and their implications for uranium and hydrocarbon exploration in the Wind River Basin, Wyoming

International Nuclear Information System (INIS)

Seeland, D.A.

1978-01-01

Paleocurrent maps of the fluvial lower Eocene Wind River Formation in the Wind River Basin of central Wyoming define promising uranium- and hydrocarbon-exploration target areas. The Wind River Formation is thought to have the greatest potential for uranium mineralization in areas where it includes arkosic channel sandstones derived from the granitic core of the Granite Mountains, as in the channel-sandstone bodies deposited in Eocene time by a 40-kilometer segment of the eastward-flowing paleo-Wind River that exended westward from near the town of Powder River on the east edge of the basin. Channel-sandstone bodies with a Granite Mountains source occur south of this segment of the paleo-Wind River and north of the Granite Mountains. The southwestern part of this area includes the Gas Hills uranium district, but the channel-sandstone bodies between the Gas Hills district and the 40-kilometer segment of the paleo-Wind River may also be mineralized. This area includes the southeasternmost part of the Wind River Basin southeast of Powder River and contains northeasterly trending channel-sandstone bodies derived from the Granite Mountains. Limited paleocurrent information from the margins of the Wind River Basin suggests that the paleo-Wind River in Paleocene time flowed eastward and had approximately the same location as the eastward-flowing paleo-Wind River of Eocene time. The channel-sandstone bodies of the paleo-Wind Rivers are potential hydrocarbon reservoirs, particularly where they are underlain or overlain by the organic-rich shale and siltstone of the Waltman Shale Member of the Fort Union Formation. If leaks of sulfur-containing gas have created a reducing environment in the Eocene paleo-Wind River channel-sandstone bodies, then I speculate that the areas of overlap of the channel-sandstone bodies and natural-gas fields in the underlying rocks may be particularly favorable areas in which to search for uranium deposits

Eocene fluvial drainage patterns and their implications for uranium and hydrocarbon exploration in the Wind River Basin, Wyoming

International Nuclear Information System (INIS)

Seeland, D.A.

1975-01-01

Paleocurrent maps of the fluvial early Eocene Wind River Formation in the Wind River Basin of central Wyoming define promising uranium and hydrocarbon exploration target areas. The Wind River Formation is thought to have the greatest potential for uranium mineralization in areas where it includes arkosic channel sandstones derived from the granitic core of the Granite Mountains as in the channel sandstones deposited by the 25-mile segment of the Eocene Wind River extending westward from near the town of Powder River on the east edge of the basin. Channel sandstones with a Granite Mountain source occur south of this segment of the Eocene Wind River and north of the Granite Mountains. The southwestern part of this area includes the Gas Hills uranium district but channel sandstones between the Gas Hills district and the 25-mile segment of the Eocene Wind River are potentially mineralized. This area includes the entire southeasternmost part of the Wind River Basin southeast of Powder River and contains northeasterly trending channel sandstones derived from the Granite Mountains. Limited paleocurrent information from the margins of the Wind River Basin suggests that the Paleocene Wind River flowed eastward and had approximately the same location as the eastward-flowing Eocene Wind River. If leaks of sulfur-containing gas have created a reducing environment in the Eocene Wind River channel sandstones, then I speculate that the areas of overlap of the channel sandstones and natural gas fields in the underlying rocks may be particularly favorable areas in which to search for uranium deposits. The channel sandstones of the Paleocene and Eocene Wind Rivers are potential hydrocarbon reservoirs, particularly where underlain or overlain by the organic-rich shale and siltstone of the Waltman Shale Member of the Fort Union Formation

Interim guidance for the safe transport of reprocessed uranium

International Nuclear Information System (INIS)

1994-06-01

Increasingly reprocessed uranium is being used for the fabrication of nuclear fuel elements. Different intermediate reprocessing steps are carried out at different locations. Therefore, transportation of uranium material is necessary. Due to the difference in isotope composition of reprocessed uranium then unirradiated uranium a doubt is casted on the presumption that packages used for the transport of unirradiated uranium are automatically suitable for reprocessed uranium compounds. The Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) recommended that the issue be reviewed by consultants and that a document be developed that would give guidance to users of the Regulations. This TECDOC is the result of the endeavors of the experts convened at two Consultants Services meetings. It contains guidance on the provisions in the current Regulations as well as proposals for changes to the new Revised Edition whose publication is planned for 1996. This document demonstrates that under the present Transport Regulations it is possible in most cases to ship reprocessed uranium compounds in the same packages as unirradiated uranium compounds. In few cases a more stringent package type is required. 8 refs, 22 figs, 19 tabs

Australia's master plan for uranium: questions still cloud the future

International Nuclear Information System (INIS)

Anon.

1977-01-01

Although the Australian Government has given the long-awaited green light for mining and export of uranium, potential uranium producers will have to battle a welter of red tape before the production outlook from the 1980s on becomes clear. An extensive number of bureaucratic agencies must be established before site work can begin. However, it now seems reasonably certain that by the mid-1980s Australian uranium mines will be producing 10,000 to 15,000 mtpy of uranium oxide. After that, production should grow rapidly, given the government's optimism about longer term market prospects. In the months ahead the government will assess the levels of international demand to be expected in coming years and will plan production and sales to meet those needs. Uranium deposits developed so far are described briefly

Geology and uranium mineralization in the eastern part of the Kani Basin, Gifu, Central Japan

International Nuclear Information System (INIS)

Kobayashi, Takao

1989-01-01

The Misano and Utozaka uranium deposits in the eastern part of the Kani Basin are within Miocene nonmarine sediments which unconformably overlie Paleozoic-Mesozoic sediments and Cretaceous-Paleogene granites. These deposits are classified as sandstone type deposits structurally controlled by palaeo-channel structures formed on the pre-Miocene basement rocks. The host rock is the Kani lignite-bearing formation which is the lowermost sequence of the Kani Group. The age of the formation was estimated to be 20-19 Ma by fission track dating. The mineralized host sediments consist of conglomerates, arkosic, tuffaceous and carbonaceous sandstones. Although no primary uranium mineral was identified to date, it is considered that uranium is present in uranous form. The mineralization was strongly controlled by a fault structure within the basement granites as well as the channel structure formed on the basement rocks, especially on the granites. The enriched ore zone of the Misano deposit distributes within the basal part of the Kani lignite-bearing formation above the basement fault structure and in the palaeo-channel downward from the fault structure. The basement granites were also mineralized along the fault structure. Groundwater leached uranium form the basement granites, and migrated along the fault structure to the host sediments to form the deposite. (Kako, I.)

Uranium - a challenging mining business

International Nuclear Information System (INIS)

Stadelhofer, J.W.; Wedig, M.J.

2007-01-01

The main application of uranium is its use as a fuel for the nuclear electricity generation. Presently about 68,000 t (177 mill. lbs) of uranium are annually required, of which 41,500 (108 mill. lbs) are provided from fresh mine production whereas 26,500 t (69 mill. lbs) are stock drawdown supplies from civil or military sources. Two-thirds of production are recovered by underground mining and about 75% (30,350 t) of the world's uranium mine production are extracted from top ten mines. All major uranium mining companies are making efforts to enlarge their production capacities: The paramount Cameco's Cigar Lake project has been delayed due to mine water inflow. Production is expected to commence by latest in 2010; the nameplate capacity of 6000 t/a should be reached in 2011. AREVA reported plans to invest about Euro 500 to 600 mill. to double its uranium production by 2010. In 2006 Denison Mines and International Uranium Corporation announced that they have entered into an agreement to merge the two companies in order to create a mid-tier, North American-focused uranium producer with the potential annual production of more than 5.5 mill. lbs of U 3 O 8 by 2010. The skyrocketing global electricity demand, growing public acceptance and more favourable policies have initiated a new round of global development of the nuclear industry. Against this backdrop, about 30,000 t/a to 40,000 t/a of additional mine production will be required within the upcoming 20 years to substitute secondary uranium supplies and to meet the expected increased demand; new start-up junior mining companies (e.g. Paladin) will contribute to this increased production. (orig.)

Fixed capital investments for the uranium soils integrated demonstration soil treatment technologies

Energy Technology Data Exchange (ETDEWEB)

Douthat, D.M.; Armstrong, A.Q. [Oak Ridge National Lab., TN (United States); Stewart, R.N. [Univ. of Tennessee, Knoxville, TN (United States)

1995-05-01

The development of a nuclear industry in the United States 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 United States 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 address remediation and management of uranium-contaminated soils at sites owned by DOE, the Uranium Soils Integrated Demonstration (USID) Program was formed to evaluate and compare the versatility, efficiency, and economics of various technologies that may be combined into systems designed to characterize and remediate uranium contaminated soils. The USID Program has five major tasks in developing and demonstrating these technologies. Each 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 developed by the USID Program. The cost of treating contaminated soil is one of the criteria used in the decision-making process for selecting remedial alternatives.

Fixed capital investments for the uranium soils integrated demonstration soil treatment technologies

International Nuclear Information System (INIS)

Douthat, D.M.; Armstrong, A.Q.; Stewart, R.N.

1995-05-01

The development of a nuclear industry in the United States 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 United States 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 address remediation and management of uranium-contaminated soils at sites owned by DOE, the Uranium Soils Integrated Demonstration (USID) Program was formed to evaluate and compare the versatility, efficiency, and economics of various technologies that may be combined into systems designed to characterize and remediate uranium contaminated soils. The USID Program has five major tasks in developing and demonstrating these technologies. Each 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 developed by the USID Program. The cost of treating contaminated soil is one of the criteria used in the decision-making process for selecting remedial alternatives

National uranium resource evaluation: Williams quadrangle, Arizona

International Nuclear Information System (INIS)

O'Neill, A.J.; Nystrom, R.J.; Thiede, D.S.

1981-03-01

Geologic environments of the Williams Quadrangle, Arizona, were evaluated for uranium favorability by means of literature research, uranium-occurrence investigation and other surface studies, subsurface studies, aerial radiometric data, hydrogeochemical data, and rock-sample analytic data. Favorability criteria are those of the National Uranium Resource Evaluation program. Three geologic environments are favorable for uranium: the Tertiary fluvial rocks of the Colorado Plateau where they unconformably overlie impermeable bed rock (for channel-controlled peneconcordant deposits); collapse breccia pipes in Paleozoic strata of the Colorado Plateau (for vein-type deposits in sedimentary rocks); and Precambrian crystalline rocks of the Hualapai, Peacock, and Aquarius Mountains, and Cottonwood and Grand Wash Cliffs (for magmatic-hydrothermal deposits). Unfavorable geologic environments are: Tertiary and Quaternary volcanic rocks, Tertiary and Quaternary sedimentary rocks of the Colorado Plateau, nearly all Paleozoic and Mesozoic sedimentary rocks, and the Precambrian-Cambrian unconformity of the Grand Wash Cliffs area. Tertiary rocks in Cenozoic basins and Precambrian crystalline rocks in the Grand Canyon region and in parts of the Aquarius Mountains and Cottonwood and Grand Wash Cliffs are unevaluated

Uncertainty hovers over the uranium market

International Nuclear Information System (INIS)

Holtorp, J.

1981-01-01

The results of evaluation of capitalist countries requirements for uranium for nuclear power engineering in 1985-1995 are presented. The data of maximum and minimum forecasting of NPP construction have been taken into account. It is assumed that the NPP total power in capitalist countries is to attain by 1990 335-350 million kW and by 1995 356-549 million kW. It is pointed out that by 1990 uranium production will constitute 82 thousand a year: 45% of this amount will be produced at existing mines, 17% at mines under construction and 38% at the designed mines. Use of only operating mines will enable in 1985 to have reserves of produced uranium sufficient for meeting the requirements of nuclear power engineering during 2.2 years and in 1990 - 0.7 year. On the basis of analysis of the given data the conclusion is drawn that uranium requirements in the nearest future will not be great, particularly if the observed decrease in the NPPs construction scale growth rate is preserved [ru

Treatability Test Plan for 300 Area Uranium Stabilization through Polyphosphate Injection

International Nuclear Information System (INIS)

Vermeul, Vince R.; Williams, M. D.; Fritz, Brad G.; Mackley, Rob D.; Mendoza, Donaldo P.; Newcomer, Darrell R.; Rockhold, Mark L.; Williams, Bruce A.; Wellman, Dawn M.

2007-01-01

The U.S. Department of Energy has initiated a study into possible options for stabilizing uranium at the 300 Area using polyphosphate injection. As part of this effort, PNNL will perform bench- and field-scale treatability testing designed to evaluate the efficacy of using polyphosphate injections to reduced uranium concentrations in the groundwater to meet drinking water standards (30 (micro)g/L) in situ. This technology works by forming phosphate minerals (autunite and apatite) in the aquifer that directly sequester the existing aqueous uranium in autunite minerals and precipitates apatite minerals for sorption and long term treatment of uranium migrating into the treatment zone, thus reducing current and future aqueous uranium concentrations. Polyphosphate injection was selected for testing based on technology screening as part of the 300-FF-5 Phase III Feasibility Study for treatment of uranium in the 300-Area

Treatability Test Plan for 300 Area Uranium Stabilization through Polyphosphate Injection

Energy Technology Data Exchange (ETDEWEB)

Vermeul, Vincent R.; Williams, Mark D.; Fritz, Brad G.; Mackley, Rob D.; Mendoza, Donaldo P.; Newcomer, Darrell R.; Rockhold, Mark L.; Williams, Bruce A.; Wellman, Dawn M.

2007-06-01

The U.S. Department of Energy has initiated a study into possible options for stabilizing uranium at the 300 Area using polyphosphate injection. As part of this effort, PNNL will perform bench- and field-scale treatability testing designed to evaluate the efficacy of using polyphosphate injections to reduced uranium concentrations in the groundwater to meet drinking water standards (30 ug/L) in situ. This technology works by forming phosphate minerals (autunite and apatite) in the aquifer that directly sequester the existing aqueous uranium in autunite minerals and precipitates apatite minerals for sorption and long term treatment of uranium migrating into the treatment zone, thus reducing current and future aqueous uranium concentrations. Polyphosphate injection was selected for testing based on technology screening as part of the 300-FF-5 Phase III Feasibility Study for treatment of uranium in the 300-Area.

Uranium silicide activities at Babcock and Wilcox

International Nuclear Information System (INIS)

Noel, W.W.; Freim, J.B.

1983-01-01

Babcock and Wilcox, Naval Nuclear Fuel Division (NNFD) in conjunction with Argonne National Laboratory (ANL) is actively involved in the Reduced Enrichment Research Test Reactor (RERTR) Program to produce low enriched fuel elements for research reactors. B and W and ANL have undertaken a joint effort in which NNFD will fabricate two low enriched uranium (LEU), Oak Ridge Reactor (ORR) elements with uranium silicide fuel furnished by ANL. These elements are being fabricated for irradiation testing at Oak Ridge National Laboratory (ORNL). Concurrently with this program, NNFD is developing and implementing the uranium silicide and uranium aluminide fuel fabrication technology. NNFD is fabricating the uranium silicide ORR elements in a two-phase program, Development and Production. To summarize: 1. Full size fuel plates can be made with U 3 SiAl but the fabricator must prevent oxidation of the compact prior to hot roll bonding; 2. Providing the ANL U 3 Si x irradiation results are successful, NNFD plans to provide two ORR elements during February 1983; 3. NNFD is developing and implementing U 3 Si x and UAI x fuel fabrication technology to be operational in 1983; 4. NNFD can supply U 3 O 8 high enriched uranium (HEU) or low enriched uranium (LEU) research reactor elements; 5. NNFD is capable of providing high quality, cost competitive LEU or HEU research reactor elements to meet the needs of the customer

Depending on scientific and technological progress to prospect for superlarge uranium deposits. Across-century target for uranium resources exploration work in China

International Nuclear Information System (INIS)

Shen Feng

1995-01-01

After over 30 years' development, uranium resources exploration work in China has resulted in the discovery of more than 10 economic types of uranium deposits in 23 provinces (regions) of the whole country and large quantities of uranium reserves have been submitted which guarantee the development of nuclear industry in China. However, characteristics such as smaller size of deposits and ore bodies, and lower ore grade of discovered China's uranium deposits have brought about a series of problems on how to economically exploit and utilize these uranium resources. To prospect for superlarge uranium deposits is a guarantee of making uranium resources essentially meet the demand for the long-term development of nuclear industry in China, and is an important way of improving economic benefits in mining China's uranium resources. It is an important mark for uranium geological exploration work to go up a new step as well. China exhibits the geological environment in which various types of superlarge uranium deposits can be formed. Having the financial support from the state to uranium resources exploration work, having professional uranium exploration teams well-experienced in ore prospecting, having modernized uranium exploration techniques and equipment and also having foreign experience in prospecting for superlarge uranium deposits as reference, it is entirely possible to find out superlarge uranium deposits in China at the end of this century and at the beginning of next century. In order to realize the objective, the most important prerequisite is that research work on metallogenetic geological theory and exploration techniques and prospecting methodology for superlarge uranium deposits must be strengthened, and technical quality of the geological teams must be improved. Within this century, prospect targets should be selected and located accurately to carry out the emphatic breakthrough in exploration strategy

Abstracts and papers of the 1999 International RERTR Meeting

International Nuclear Information System (INIS)

1999-10-01

The papers presented at the 22nd International RERTR Meeting dealt with the following topics: development and testing of new fuel elements (uranium-molybdenum alloys); research reactors core conversion studies (change from highly to moderately or slightly enriched uranium), including both measurements and calculations: spent fuel storage and transportation; production of 99 Mo from low enriched uranium. A number of papers were devoted to the status and future of national RERTR programs

Supply of enriched uranium for research reactors

International Nuclear Information System (INIS)

Mueller, Hans; Laucht, Juergen

1996-01-01

Since the RERTR meeting in 1990 at Newport/USA, NUKEM recommended that the research reactor community agree upon a worldwide unified technical specification for low enriched uranium (LEU) and high enriched uranium (HEU) since there existed numerous specifications both from suppliers/fabricators and research reactors. The target recommended by NUKEM is to arrive at a worldwide unified standard specification in order to facilitate supplies of LEU and HEU to fabricators for fabrication of research reactor fuel elements. In our paper presented at the RERTR meeting at Paris in September 1995, we pointed out that LEU and HEU supplied by the U.S. Department of Energy (DOE) in the past was never 'virgin' material, i.e., it was mixed with reprocessed uranium. Our recommendation was to include this fact in the proposed unified specification. Since the RERTR meeting in 1995 progress on a unified standard specification has been made and we would like to provide more specific information about that in this paper. Furthermore, we will deal with the question whether there is a secure supply of LEU for converted research reactors. We list current and potential suppliers of LEU, noting however, that the DOE has for a number of years been unable to supply any LEU due to production problems. The future availability of LEU of U.S. origin is, of course, essential for those research reactor operators which have converted their reactors from HEU to LEU and which are intending to return spent fuel of U.S. origin to the U.S.A. (author)

Measurement of uranium in soil environment optimization of liquid fluorescent method improvement

International Nuclear Information System (INIS)

Qin Guangcheng; Li Yan

2013-01-01

Measurement of uranium in soil environment were introduced in this paper optimization improvement fluid fluorescence analysis method. Use 'on the determination of uranium in soil, rocks, etc. Samples of liquid fluorescent method' when measuring low environment soil samples can not meet the required precision of 8% or less in gansu province and method detection limit of 0.3 mg/kg or less. In affecting the method detection limit, recovery rate and precision of the soil sample decomposition temperature, measuring the temperature of the sample, sample pH value measurement, the background fluorescence measurement condition optimization of analysis is determined, the method detection limit of 0.133 mg/kg, the average recovery rate was 96.6%, the precision is 3.80%. The experimental results show that the method can meet the requirements for determination of trace uranium m environment soil samples. (authors)

Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.2--uranium mining and metallurgy sub-volume

International Nuclear Information System (INIS)

2014-05-01

Progress report on nuclear science and technology in China (Vol. 3) includes 48 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the second one, the content is about uranium mining and metallurgy sub-volume

Geomembrane selection criteria for uranium tailings ponds

International Nuclear Information System (INIS)

Mitchell, D.H.; Cuello, R.

1986-09-01

The selection criteria, particularly those involving chemical compatibility, of geomembranes to be used in ponds at uranium mill operations are discussed. The principal functional criteria which a geomembrane must meet for this application are: (1) a specified service life and (2) low permeability. Chemical compatibility with the waste is essential in meeting these functional criteria. In two different types of aging tests using simulated acidic uranium mill waste, degradation of chemical and physical properties were examined in geomembranes of high-density polyethylene, polyvinyl chloride, and chlorosulfonated polyethylene. Compatibility tests according to the National Sanitation Foundation procedures are recommended to ascertain the stability of certain physical properties of the proposed geomembrane. Actual experience with a specific geomembrane in an identical application is probably the best method to assure compatibility; however, this experience is frequently not available. Experience with a geomembrane in similar applications is valuable in the selection process, however, small differences in either the geomembrane formulation or the waste composition may result in large differences in performance of the geomembrane. It is likely that many geomembranes have acceptable chemical stability for typical uranium mill applications, therefore, additional factors in the selection processes will include seaming characteristics, mechanical properties, site characteristics, and costs

International symposium concluded that uranium supply for nuclear power is secure

International Nuclear Information System (INIS)

2000-01-01

The document informs that stable uranium supply to fuel nuclear power plants will continue to be available according to the conclusion reached at the International Symposium on the Uranium Production Cycle and the Environment held from 2 to 6 October 2000 at the IAEA in Vienna. The meeting included specialists from about 40 countries, in addition to the Arab Atomic Energy Agency, European Commission, OECD/Nuclear Energy Agency (NEA), Office of Supervising Scientist (OSS)/Environment Australia, United Nations, Uranium Institute, World Bank, the World Energy Council and the Nuclear Energy Institute (NEI)

South African uranium resources - 1997 assessment methodology and results

International Nuclear Information System (INIS)

Ainslie, L.C.

2001-01-01

The first commercial uranium production in South Africa started in 1953 to meet the demand for British/US nuclear weapons. This early production reached its peak in 1959 and began to decline with the reduced demand. The world oil crisis in the 1970s sparked a second resurgence of increased uranium production that peaked in 1980 to over 6,000 tonnes. Poor market condition allied with increasing political isolation resulted in uranium production declining to less than a third of the levels achieved in the early 1980s. South Africa is well endowed with uranium resource. Its uranium resources in the RAR and EAR-I categories, extractable at costs of less than $80/kg U, as of 1 January 1997, are estimated to 284 400 tonnes U. Nearly two thirds of these resources are associated with the gold deposits in the Witwatersrand conglomerates. Most of the remaining resources occur in the Karoo sandstone and coal deposits. (author)

New development stage of China's uranium industry

International Nuclear Information System (INIS)

Zhang Rong

2001-01-01

From the early 1980s China adjusted its uranium industry to better meet the market economy requirements. Until 1997, the adjustment has been completed. The technical and managerial improvements result in a more efficient uranium production. In 1996 a series of events related to the nuclear power development of China manifests very favorable situation for the uranium industry. The first two nuclear power plants with a total installed capacity of 2100 MW in the mainland of China have been operating safely and steadily for several years. The additional nuclear power projects to be constructed for the rest of this century are implemented in an all-round way. Four plants with eight reactors of a total of 6900 MW have entered their construction period in succession. In 1996 a commercial ISL mine in Xinjiang with annual capacity 100 tU was completed, and the larger scale of ISL mine is expected to be constructed by 2000. The Benxi uranium mine in northeast China was put into production. It applies some new mining and processing technologies and improved management, which might serve as a new model of uranium mines in China. (author)

Evaluation of uranium anomalies in the Goodman-Dunbar area, northeastern Wisconsin

International Nuclear Information System (INIS)

Mathews, G.W.; Blackburn, W.H.

1982-01-01

Based on this investigation, the Goodman-Dunbar area is considered not to be favorable for the occurrence of uranium deposits of economic potential. Whether one adopts an anatectic or igneous intrusive model for the pegmatites, the area does not meet NURE favorability criteria guidelines because: (1) The apparent average grade of the alaskites will not meet or exceed the 100-ppM minimum cutoff grade; (2) Even if the grade requirements were met, the alaskite is not extensive enough to provide a sufficient volume of endowed rock. It is reasonable to assume that similar alaskites may exist west of this study area, beneath the glacial drift. If the uranium is located in interstitial sites and (or) along fractures, as postulated in this investigation, then it would be readily available for leaching into local surface- and ground-water regimes. This alaskite and other possible alaskites are probably the cause of local stream-water anomalies. The contrasting uranium contents of the alaskites and Dunbar Gneiss also are probable causes for anomalous airborne measurements. The area near Dunbar, Wisconsin, warrents no further study in terms of uranium potential. 4 figures, 2 tables

Indian uranium scenario and a new process technology for alkaline leaching

International Nuclear Information System (INIS)

Suri, A.K.; Ghosh, S.K.; Padmanabhan, N.P.H.

2008-01-01

The growing demand of uranium for the nuclear power reactors in the country necessitates maximal utilization of the indigenously available uranium resources. In addition to the single operating uranium mine and the mill at Jaduguda, new mines need to be opened to meet the requirements. However, for the exploitation of the various uranium deposits no single elixir process technology is available and needs to necessarily be developed based on the uranium and gangue mineralogy. One such challenge was development of techno-economic process for exploitation of a reasonably vast deposit at Tummalapalle, Andhra Pradesh. The ore characteristics are much different from that of Jaduguda ore and required alkaline pressure leaching technique to bring the uranium values from the ore into solution. Based on the laboratory and pilot plant studies a working flow sheet has been developed and this paper describes the challenges and how they were tackled. (author)

Present state and problems of uranium fuel fabrication businesses

International Nuclear Information System (INIS)

Yuki, Akio

1981-01-01

The businesses of uranium fuel fabrication converting uranium hexafluoride to uranium dioxide powder and forming fuel assemblies are the field of most advanced industrialization among nuclear fuel cycle industries in Japan. At present, five plants of four companies engage in this business, and their yearly sales exceeded 20 billion yen. All companies are planning the augmentation of installation capacity to meet the growth of nuclear power generation. The companies of uranium fuel fabrication make the nuclear fuel of the specifications specified by reactor manufacturers as the subcontractors. In addition to initially loaded fuel, the fuel for replacement is required, therefore the demand of uranium fuel is relatively stable. As for the safety of enriched uranium flowing through the farbicating processes, the prevention of inhaling uranium powder by workers and the precaution against criticality are necessary. Also the safeguard measures are imposed so as not to convert enriched uranium to other purposes than peacefull ones. The strict quality control and many times of inspections are carried out to insure the soundness of nuclear fuel. The growth of the business of uranium fuel fabrication and the regulation of the businesses by laws are described. As the problems for the future, the reduction of fabrication cost, the promotion of research and development and others are pointed out. (Kako, I.)

Relationship between characteristics of fan-delta sandstone bodies and in-situ leachable sandstone-type uranium mineralization

International Nuclear Information System (INIS)

Nie Fengjun; Zhou Weixun; Guan Taiyang; Li Sitian

2000-01-01

Like normal deltas, fan-deltas are composed of three parts, i.e., fan-delta plain, fan-delta front and pre-fin-delta, In-situ leachable uranium deposits are commonly distributed along the margins of in-land basins. The author analyzes the possible relationship between the basic characteristics of fan-delta sandstone bodies and uranium mineralization. Two examples, e.g., the fan delta depositional systems in the eastern part of Jungger basin and the southern part of Yili basin, are given to illustrate the fan-delta vertical sequence and planar distribution of sedimentary facies. It has been pointed out that the braided channel sandstone bodies on delta plain, sub-aqueous distributional channel sandstone bodies and delta front sandstone bodies may be the favourable host rocks for in-situ leachable sandstone uranium deposits

Study of the interactions between uranium and organic compounds in the hydrothermal systems

International Nuclear Information System (INIS)

Salze, David

2008-01-01

Formers studies on the relations between organic matter and uranium have shown that these interactions go since the complexation and the transport of uranium in organics fluids until its reduction by the organic matter leading to the uranium-bearing mineral precipitation. An experimental study of these reactions to 200 deg. C and 500 bars between experimental compounds (pure organic compounds) such as the n-alkanes (n-pentane, n-hexane, n-heptane, n-octane, n-nonane, n-decane, n-dodecane, n-tetradecane and n-hexadecane), an n-alkene hydrocarbon (n-dec-1-ene), cycles (butyl-cyclohexane and cyclo-hexane) and the aromatic ones (butyl-benzene and naphthalene), and hexavalent uranium oxides was undertaken. These experiments allowed to show a progressive oxidation of n-alkanes starting from made up C6. The increasing size of the aliphatic chains and the increase in the time of setting in interaction are major factors of the increase in the environment oxidizing capacity in interaction with uranium on the organic compound. The determination of the oxidation step of uranium oxides after experiment made it possible to determine that in aqueous environment the aliphatic model compounds are reducers more powerful than the aromatic compounds. An organic matter from lake or marine origin generally has an aliphatic fraction larger than the organic matter of continental origin and thus will be more likely to reduce uranium. A natural example, the uranium deposits in the sandstones from Arlit, the tectono-lithologic type, was selected in order to apply the results obtained in the experimental part. They are located in fluviatile sandstones rich in organic matter of continental origin (type III) deposited in the paleo-channels. Former authors considered that only this organic matter of type III was responsible for the reduction of U (VI) in U (IV). Work which was undertaken in the present study shows that migrated oils of probable marine origin strongly contributed to the genesis

Options for disposal and reapplication of depleted uranium hexafluoride

International Nuclear Information System (INIS)

Fitch, St.H.

2009-01-01

The nuclear renaissance has spurred the need to enrich uranium to fuel power reactors to meet the nation's energy requirements. However, enriching uranium produces the volatile byproduct of DUF 6 tails. In an ambient environment, DUF 6 decomposes into uranium oxides and hydrogen fluoride (HF). This HF component makes DUF 6 unsuitable for disposal as low-level waste. To make DUF 6 suitable for disposal, it must be stabilized in a controlled process by converting it into uranium oxides and fluorine compounds by the processes of de-conversion and fluorine extraction. Once stabilized, the DU and fluorine have reapplication potential that would delay or divert the need for disposal. Certain challenges confound this process, notably the chemical toxicity from elemental fluorine and DU, radiation hazards, limited low-level waste disposal capacity, and potential political and public opposition. (authors)

Lawrence Livermore Laboratory concept for uranium recovery from seawater

International Nuclear Information System (INIS)

Gregg, D.; Wang, F.

1980-01-01

The Lawrence Livermore Laboratory concept for uranium recovery from seawater involves the following process steps: (1) produce activated carbon via a coal gasification plant; (2) contact activated carbon sorbent with seawater using a settling process (no pumping of seawater); (3) vacuum activated carbon from sea floor; (4) gasify or burn activated carbon (further concentrating the uranium in the ash); (5) extract the uranium from the rich ash ore by conventional techniques. The process advantages are: (1) eliminates seawater pumping, the need for an illuent, and the need for a fresh water wash; (2) should result in much lower capital investment and regional process energy. Major process issues are: (1) uranium loading on activated carbon; (2) activated carbon modifications required to improve the sorbtion performance; (3) activated carbon particle size needed to meet system requirements; (4) minimization of sorbent losses when contacted with seawater

Metallogenic geologic prerequisites of sandstone-type uranium deposits and target area selection. Taking Erlian and Ordos basins as examples

International Nuclear Information System (INIS)

Chen Fazheng

2002-01-01

Sandstone-type uranium deposit is the main target of recent uranium prospecting and exploration. According to the metallogenic characteristics, sandstone-type uranium deposits are divided into three groups: paleo-channel type, interlayer oxidation zone type and phreatic interlayer oxidation type. The author makes an analysis on the geologic prerequisites of the three types of uranium deposits, the similarities and difference, and preliminarily summarizes genetic models of different types of uranium deposits. Finally, taking Erlian and Ordos basins as examples, the author makes an evaluation and a strategic analysis on the uranium metallogenic prospect of the above two basins

Proceedings of the international meeting on reduced enrichment for research and test reactors

Energy Technology Data Exchange (ETDEWEB)

Tsuchihashi, Keichiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1984-05-01

The purpose of the Meeting was to exchange and discuss the most up-to-date information on the progress of various programs related to research and test reactor core conversion from high enriched uranium to lower enriched uranium. The papers presented during the Meeting were divided into 9 sessions and one round able discussion which concluded the Meeting. The Sessions were: Program, Fuel Development, Fuel Fabrication, Irradiation testing, Safety Analysis, Special Reactor Conversion, Reactor Design, Critical Experiments, and Reprocessing and Spent Fuel Storage. Thus, topics of this Meeting were of a very wide range that was expected to result in information exchange valuable for all the participants in the RERTR program.

Proceedings of the international meeting on reduced enrichment for research and test reactors

International Nuclear Information System (INIS)

Tsuchihashi, Keichiro

1984-05-01

The purpose of the Meeting was to exchange and discuss the most up-to-date information on the progress of various programs related to research and test reactor core conversion from high enriched uranium to lower enriched uranium. The papers presented during the Meeting were divided into 9 sessions and one round able discussion which concluded the Meeting. The Sessions were: Program, Fuel Development, Fuel Fabrication, Irradiation testing, Safety Analysis, Special Reactor Conversion, Reactor Design, Critical Experiments, and Reprocessing and Spent Fuel Storage. Thus, topics of this Meeting were of a very wide range that was expected to result in information exchange valuable for all the participants in the RERTR program

Enriched uranium recovery flowsheet improvements

International Nuclear Information System (INIS)

Holt, D.L.

1986-01-01

Savannah River uses 7.5% TBP to recover and purify enriched uranium. Adequate decontamination from fission products is necessary to reduce personnel exposure and to ensure that the enriched uranium product meets specifications. Initial decontamination of the enriched uranium from the fission products is carried out in the 1A bank, 16 stages of mixer-settlers. Separation of the enriched uranium from the fission product, 95 Zr, has been adequate, but excessive solvent degradation caused by the long phase contact times in the mixer-settlers has limited the 95 Zr decontamination factor (DF). An experimental program is investigating the replacement of the current 1A bank with either centrifugal contactors or a combination of centrifugal contactors and mixer-settlers. Experimental work completed has compared laboratory-scale centrifugal contactors and mixer-settlers for 95 Zr removal efficiencies. Feed solutions spiked with actual plant solutions were used. The 95 Zr DF was significantly better in the mixer-settlers than in the centrifugal contactors. As a result of this experimental study, a hybrid equipment flowsheet has been proposed for plant use. The hybrid equipment flowsheet combines the advantages of both types of solvent extraction equipment. Centrifugal contactors would be utilized in the extraction and initial scrub sections, followed by additional scrub stages of mixer-settlers

Reviews on the metallogenic and geological features of sandstone-type uranium deposits in Japan

International Nuclear Information System (INIS)

Pei Chengkai; Huang Xianfang; Zhang Baoju

2006-01-01

Regional geologic settings of sandstone-type uranium deposits in Japan are firstly analyzed. The regional tectonic evolution characteristics of 'Green tuff region' and 'Non green tuff region' and their relationship with uranium mineralization are elaborated in depth. Based on those mentioned above, the uranium sources of sandstone-type uranium deposits in Japan are discussed deeply and the most favorable uranium sources are considered to come from the basement and the surrounding granites. Their intrusive epochs range from Later Cretaceous to Palaeogene (about 60 to 70 Ma ago). The characteristics of ore-bearing host rocks, matter compositions of the deposits, ore formation enrichment factors, the hydrogeologic conditions and so on are described by taking Ningyo-Toge and Tono deposits as examples. Finally, the prospecting measures for the palaeo-channel sandstone-type uranium deposits (basal type) are reviewed. (authors)

Impact of pulling down regulatory state barriers on uranium in Australia: Is there a need in order to maintain and increase Australia’s global market share of uranium?

Directory of Open Access Journals (Sweden)

Ikhlaas Gurrib

2013-10-01

Full Text Available This paper sets a prospective framework to study the impact of opening more mines to meet future growing demand on Australia’s economy. The structure is aimed at decomposing investments and exports variables into Uranium exports and Uranium Exploration expenditure and analyse their impacts on each State GSP (Goods State Product and for Australia as a nation. The demand and supply factors affecting the uranium market are defragmented before providing the research methodology and data specifics. Later analysis is expected to have policy implications by serving as a guide to pull down State Regulatory barriers like those imposed currently in Queensland, which is rich with uranium deposits and allow only uranium exploration but no uranium mining. Empirical findings would suggest whether exporting the carbon free energy would add value to Australia’s different competing states and as a whole globalized economy.

Characterization and anion exchange removal of uranium from Hanford ground water

International Nuclear Information System (INIS)

Delegard, C.H.; Weiss, R.L.; Kimura, R.T.; Law, A.G.; Routson, R.C.

1986-01-01

In February 1985, uranium concentrations increased abruptly to 0.1 kgU/m/sup 3/ in ground waters underlying a retired liquid waste disposal facility in the United States Department of Energy-Richland Operations Hanford Site. Characterization tests showed the uranium was present as an anionic carbonate complex not sorbable by Hanford sediments. The uranium was mobilized by flow from a perched zone of water caused by recent nearby cooling water disposal above an impermeable sediment layer. In a unique demonstration of the concept of ''as low as reasonably achievable,'' efforts were immediately undertaken to minimize the spread of the plume and to reduce the amount of uranium in the ground water. An anion exchange-based uranium removal process flowsheet was rapidly developed and implemented. Operational for six months, the process has treated over 30,000 m/sup 3/ of ground water and collected 94% of the uranium while producing a treated effluent that meets criteria for discharge to the soil column

A study on direct determination of uranium in ore by analyzing γ-ray spectrum with dual linear regression

International Nuclear Information System (INIS)

Liu Chunkui

1996-01-01

The method introduced is based on different energy of γ-ray emitted from radionuclide in the uranium-radium decay series in ore. The pulse counting rates of two spectra bands, i.e. N 1 (55∼193 keV) and N 2 (260∼1500 keV), are measured by portable type HYX-3 400-channel γ-ray spectrometer. On the other side, the uranium content (Q U ) is obtained by chemical analysis of channel sampling. Then the regression coefficients (b 0 , b 1 ,b 2 ) can be determined through dual linear regression by using Q U and N 1 , N 2 . The direct determination of uranium can be made with the regression equation Q U = b 0 + b 1 N 1 + b 2 N 2

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.

Prospects brighten for world uranium producers

International Nuclear Information System (INIS)

Steyn, J.

1996-01-01

Since the beginning of 1995, uranium spot market prices have risen by more than 67%. This has been due to supply related factors and might have been greater if world nuclear power projections had not shown virtually zero growth over the next few decades except in the Far East. Perceptions of a looming supply shortfall have been created by rapidly declining inventories, western mine production being able to meet only half of plant requirements, constraints on access to CIS supplies in the future and considerably less than anticipated uranium-equivalent supply from nuclear weapons material. Data on projected world supply and demand balances are presented. On the supply side this includes all primary production and inventories of all forms. A supply deficit of 5 million 1b, U 3 O 8 by 2010 is shown. Trade constraints, weapons stockpiles and laser enrichment, which are the most important factors affecting both the near- and longer-term uranium markets, are discussed. (UK)

Uranium extraction from gold-uranium ores

Energy Technology Data Exchange (ETDEWEB)

Laskorin, B.N.; Golynko, Z.Sh.

1981-01-01

The process of uranium extraction from gold-uranium ores in the South Africa is considered. Flowsheets of reprocessing gold-uranium conglomerates, pile processing and uranium extraction from the ores are presented. Continuous counter flow ion-exchange process of uranium extraction using strong-active or weak-active resins is noted to be the most perspective and economical one. The ion-exchange uranium separation with the succeeding extraction is also the perspective one.

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

Radium and uranium in phosphate fertilizers and their impact on the radioactivity of waters

International Nuclear Information System (INIS)

Barisic, D.; Lulic, S.; Miletic, P.

1992-01-01

The study of radioactivity in the phosphate fertilizers and water ways of the Kanovci area was performed in order to determine the influence of the application of phosphate fertilizers on the radioactive pollution of these waters. The activity of 226 Ra, 228 Ra, 235 U and 238 U was measured in different types of phosphate fertilizers and waters by means of γ-ray spectrometry. Surface water, water from drainage channels, shallow groundwater and deep groundwater samples were collected from the Kanovci agricultural and well field area in Eastern Slavonia, where phosphate fertilizers have been used for the past 15 years. 137 Cs was also measured in water samples. The typical phosphate fertilizer used in the Kanovci area contains 75 Bq kg -1 of 226 Ra, 9 Bq kg -1 of 228 Ra, 52 Bq kg -1 of 235 U and 1120 Bq kg -1 of 238 U. The estimated annual deposition of uranium and radium in soils of the agricultural and well field area in Kanovci is: 4.5 Bq m -2 for 226 Ra, 0.5 Bq m -2 for 228 Ra, 3.1 Bq m -2 for 235 U and 67 Bq m -2 for 238 U. The greatest concentrations of both uranium isotopes are measured in water from drainage channels with a mean value of 120 Bq m -3 for 238 U and 5.5 Bq m -3 for 235 U. The concentrations of both radium isotopes generally increase with depth of water as distinct from uranium, whose concentrations in deep groundwater are much lower. The highest concentrations of 137 Cs were measured in water from drainage channels; it was not detected in deep groundwater. The 238 U/ 226 Ra activity ratio (AR) is the highest in water from drainage channels and the Bosut River, while in deep groundwater the ratio is only 1.6. Results indicate that high uranium concentrations in surface water, shallow groundwater and water from drainage channels are caused by phosphate fertilizer application in agriculture on the Kanovci area. (author)

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

DOE's Stewardship of Government-Owned Uranium Materials

International Nuclear Information System (INIS)

Jackson, J. Dale; Donaldson, Dale E.

2002-01-01

Beginning in the 1980's, a significant number of Department of Energy facilities have been shut down and are in the decommissioning process. The shutdown of additional facilities is planned. In addition, during the past several decades, the Department of Energy has loaned nuclear material to a wide variety of private and governmental institutions for research and educational purposes. Subsequent changes in the Department's priorities have reduced the need for nuclear materials to support the Department's programs. Similarly, there has been a reduction in the need for borrowed nuclear materials by organizations and institutions using nuclear materials 'on loan' from the Department. As a result, inventories of uranium material from the Department's facilities and 'on loan' must be removed and returned to the Department. This material is in the form of low enriched uranium (LEU), normal uranium (NU), and depleted uranium (DU) in various forms. This uranium material is located at over one hundred sites within the United States and overseas, including universities and laboratories. Much of this uranium is not needed to support national priorities and programs. The Department of Energy has assumed a stewardship role in managing nuclear materials throughout their life cycle, from acquisition to storage. Surplus uranium has created challenges for DOE in managing and storing the material as well as identifying opportunities for its further use. On behalf of the Department, the Oak Ridge Operations Office has been given the responsibility to implement the Department responsibilities in meeting these challenges and managing the Department's uranium materials. To support this effort, the Office of Nuclear Fuel Security and Uranium Technology within the ORO complex coordinates uranium management functions across the Department of Energy. This coordination provides DOE with a number of important benefits, among which are: consolidated management and storage of uranium; improved

The sedimentary environment of the Beaufort Group Uranium Province in the vicinity of Beaufort West, South Africa

International Nuclear Information System (INIS)

Stear, W.M.

1980-12-01

Most of the Beaufort Group uranium deposits in the southwestern Karoo are located near the contact of the Abrahamskraal Formation and the Teekloof Formation within a stratigraphic interval of about 500 meters. Rocks of the Lower Beaufort uranium province in the Beaufort West study area occur in thick, fining upwards megacyclic sequences, each of which consists of an arenaceous zone overlain by an argillaceous zone. The morphology and internal geometry of selected channel sandstone bodies are described in plan and cross-section. Lateral and vertical profile diagrams are used to illustrate the salient features of fluvial style in the Abrahamskraal Formation and to compare these characteristics with recognised fluvial facies models. The Abrahamskraal Formation provides a local facies model of an ancient, interior drainage system characterised by a continuously shifting, ephemeral fluvio-lacustrine complex. Semi-arid climatic conditions in the depositional environment promoted the formation of uranium mineralization. The geologic structure and stratigraphy of the area, the facies and their distribution, the channel facies association as well as the geometry of the channel sandstone bodies and the interchannel facies association are discussed

Analysis of geological condition and prospecting potential of uranium metallogenesis in Maling granite mass

International Nuclear Information System (INIS)

Shao Fei; Zou Maoqing; Wu Yong; Xu Jinshan; Xu Wang; Chen Chang

2011-01-01

Based on the study of regional geological evolution of Maling granite mass, uranium content of granite mass and its peripheric strata, petrogeochemistry and the known spatial distribution pattern of uranium mineralization and ore-controlling structures, new recognition is 1) Maling composite mass is the 'S' type re-melted granite, 2) the accumulative area of regional uranium metallogenic substances forms uranium-rich re-melted strata, 3) magma evolution is the matter base for the uranium-rich hydrotherm, 4) NE-trending main faults are channels for metallogenesis and the lateral high-angle dipping faults, fractures and interlayer fractures in the peripheric strata are the spaces of mineralization. The ore intersected by drilling in Maling granite is acidic type. Prospecting potential of Maling granite mass is analyzed, and preferable prospecting space is delineated for further exploration. (authors)

The sedimentology of uranium-bearing sandstones on the farm Kaffersfontein 328, Beaufort West area

International Nuclear Information System (INIS)

Cole, D.I.

1979-10-01

The sedimentology of uranium-bearing sandstones on the farm Kaffersfontein 328 was studied by use of 23 vertical profiles measured across and adjacent to 3 mineralised deposits. The profiles consist of 18 field sections and 5 borehole logs. The vertical profiles basically consist of a succession of sedimentary facies. A total of 18 facies were recognised within the fluvial sandstone sequence according to the criteria of grain-size and sedimentary structures. Transitions between the facies were subjected to a Markov chain analysis in order to delineate Markov-dependent transitions. Uranium mineralisation coincides with areas of thicker sandstone, usually where channel over-deepening has taken place. It always occurs above the base of a channel, which often marks the base of the fluvial sandstone sequence. Irregularities in the base of the channel probably caused interruptions to the flow of uraniferous solutions and allowed sufficient time for the precipitation of the uranium. Carbonaceous debris is always associated with the mineralisation and most likely acted as an indirect reductant for the precipitation of uranium from solution. The direct reductant was most probably H 2 S produced by anaerobic bacteria acting on the carbonaceous debris. The mineralisation is confined to the coarser-grained sedimentary facies, which suggests that permeability was an important control on the mineralisation. These facies probably acted as suitable aquifers for the transport of uraniferous solutions. Horizontally bedded sandstone facies comprises 41 per cent of the total cumulative thickness of mineralisation. This facies represents a higher stream power and may consequently contain more carbonaceous material derived from plants, which were eroded from upstream areas. The nature of the bedding may also have provided a more effective permeability zone for the transport of uraniferous solutions prior to precipitation of the uranium

U.S. forms uranium enrichment corporation

International Nuclear Information System (INIS)

Seltzer, R.

1993-01-01

After almost 40 years of operation, the federal government is withdrawing from the uranium enrichment business. On July 1, the Department of Energy turned over to a new government-owned entity--the US Enrichment Corp. (USEC)--both the DOE enrichment plants at Paducah, Ky., and Portsmouth, Ohio, and domestic and international marketing of enriched uranium from them. Pushed by the inability of DOE's enrichment operations to meet foreign competition, Congress established USEC under the National Energy Policy Act of 1992, envisioning the new corporation as the first step to full privatization. With gross revenues of $1.5 billion in fiscal 1992, USEC would rank 275th on the Fortune 500 list of top US companies. USEC will lease from DOE the Paducah and Portsmouth facilities, built in the early 1950s, which use the gaseous diffusion process for uranium enrichment. USEC's stock is held by the US Treasury, to which it will pay annual dividends. Martin Marietta Energy Systems, which has operated Paducah since 1984 and Portsmouth since 1986 for DOE, will continue to operate both plants for USEC. Closing one of the two facilities will be studied, especially in light of a 40% world surplus of capacity over demand. USEC also will consider other nuclear-fuel-related ventures. USEC will produce only low-enriched uranium, not weapons-grade material. Indeed, USEC will implement a contract now being completed under which the US will purchase weapons-grade uranium from dismantled Russian nuclear weapons and convert it into low-enriched uranium for power reactor fuel

Energy crisis and uranium energy resources

International Nuclear Information System (INIS)

Koryakin, Yu.I.

1975-01-01

Problems of ensuring a supply of nuclear power with fuel are reviewed. It is probable that by the year 2000 fuel requirements for nuclear power will be determined by the heat variant of its development since the fraction of fast breeders will then be very insignificant. In connection with the energy process, in western countries there has arisen the economic possibility of using more expensive uranium (more than $22 per kg U 3 O 8 ). Now there is the point of view that, in the new post-crisis conditions, nuclear power plants with light-water reactors will be competitive. It is expected that the energy crisis will give additional impetus to development of nuclear power. In some countries work is being done on extraction of uranium from sea water. In this case, in order for uranium supplies to meet nuclear energy needs for 8, 10, or 12 years, new supplies of uranium must be sought every year. For each kilogram of U 3 O 8 , supplies of uranium will cost $11-17.6 more. Annual inflation will move the recovery costs into the higher cost category. There is good reason to consider that a significant increase in the cost of nuclear power plants and a sharp rise in credit will lead to a more concrete prediction of the total nuclear power in 2000 A.D. of 2700-3200 million kW. With exhaustion of cheap supplies, uranium will be classified by politico-economic considerations. In this case the presentation concerning the competitiveness of nuclear power and conventional energy sources may change

Standard specification for blended uranium oxides with 235U content of less than 5 % for direct hydrogen reduction to nuclear grade uranium dioxide

CERN Document Server

American Society for Testing and Materials. Philadelphia

2001-01-01

1.1 This specification covers blended uranium trioxide (UO3), U3O8, or mixtures of the two, powders that are intended for conversion into a sinterable uranium dioxide (UO2) powder by means of a direct reduction process. The UO2 powder product of the reduction process must meet the requirements of Specification C 753 and be suitable for subsequent UO2 pellet fabrication by pressing and sintering methods. This specification applies to uranium oxides with a 235U enrichment less than 5 %. 1.2 This specification includes chemical, physical, and test method requirements for uranium oxide powders as they relate to the suitability of the powder for storage, transportation, and direct reduction to UO2 powder. This specification is applicable to uranium oxide powders for such use from any source. 1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this specification does not relieve the user of th...

Erosion protection of uranium tailings impoundments

International Nuclear Information System (INIS)

Walters, W.H.; Skaggs, R.L.; Foley, M.G.; Beedlow, P.A.

1986-09-01

Pacific Northwest Laboratory (PNL) prepared this report to assist in the design and review of erosion protection works for decommissioned uranium tailings impoundments. The major causes of erosion over the long-term decommissioning period are from rainfall-runoff (overland flow) and stream channel flooding. The method of protection recommended for the impoundment side slopes and site drainage channels is rock riprap. Combinations of vegetation and rock mulch are recommended for the top surface. The design methods were developed from currently available procedures supplemented by field, laboratory, and mathematical model studies performed by PNL. Guidelines for the placement of riprap, inspection, and maintenance are presented. Other subjects discussed are rock selection and testing, slope stability, and overland erosion modeling

Data base for a CANDU-PHW operating on a once-through, slightly enriched uranium cycle (AECL-6594)

International Nuclear Information System (INIS)

1979-07-01

This report, prepared for INFCE, gives data for an extrapolated 1000 MW(e) CANDU-PHW design operating on a once-through fuel cycle with a feed fuel of slightly enriched uranium - 1.2 weight % U-235 in uranium. The effects of varying fuel enrichment, maximum channel power, and economic parameters are also discussed

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.

World nuclear fuel market. Seventeenth annual meeting

International Nuclear Information System (INIS)

Anon.

1990-01-01

The papers presented at the seventeenth World Nuclear Fuels Market meeting are cataloged individually. This volume includes information on the following areas of interest: historical and current aspects of the uranium and plutonium market with respect to supply and demand, pricing, spot market purchasing, and other market phenomena; impact of reprocessing and recycling uranium, plutonium, and mixed oxide fuels; role of individual countries in the market: Hungary, Germany, the Soviet Union, Czechoslovakia, France, and the US; the impact of public opinion and radioactive waste management on the nuclear industry, and a debate regarding long term versus short term contracting by electric utilities for uranium and enrichment services

Estimating long-term uranium resource availability and discovery requirements. A Canadian case study

International Nuclear Information System (INIS)

Martin, H.L.; Azis, A.; Williams, R.M.

1979-01-01

Well-founded estimates of the rate at which a country's resources might be made available are a prime requisite for energy planners and policy makers at the national level. To meet this need, a method is discussed that can aid in the analysis of future supply patterns of uranium and other metals. Known sources are first appraised, on a mine-by-mine basis, in relation to projected domestic needs and expectable export levels. The gap between (a) production from current and anticipated mines, and (b) production levels needed to meet both domestic needs and export opportunities, would have to be met by new sources. Using as measuring sticks the resources and production capabilities of typical uranium deposits, a measure can be obtained of the required timing and magnitude of discovery needs. The new discoveries, when developed into mines, would need to be sufficient to meet not only any shortfalls in production capability, but also any special reserve requirements as stipulated, for example, under Canada's uranium export guidelines. Since the method can be followed simply and quickly, it can serve as a valuable tool for long-term supply assessments of any mineral commodity from a nation's mines. (author)

Recent activities and trend in the uranium market

International Nuclear Information System (INIS)

Kwasny, R.; Aul, F.; Lohrey, K.

2007-01-01

Concerns about the impact of hydrocarbon use on climate and global warming are significantly growing. Furthermore, we are all well aware that security of supply is increasingly an issue. In this context, it is now principally recognised that nuclear energy has to be back on the agenda. All in all, the prospects for the nuclear power industry and thus for the uranium activities is very positive for the coming years. The changes that have taken place in the international uranium market during the past several years are remarkable. Since 2002, the uranium prices have increased more than tenfold. The spot market price of uranium began an increase from about USD 9/lb U 3 O 8 in mid 2001 following a fire at the Olympic Dam mill (Australia) in October 2001 and was propelled in subsequent years by a series of interrupting events, such as the mine shaft flooding at the McArthur River mine (Canada) in April 2003, the threat of the early shutdown of the Roessing mine (Namibia) and the Ranger mine (Australia) in 2003, the decision of Techsnabexport (Tenex, Russia) in October 2003 to terminate sales of UF6 to the US trading company Globe Nuclear Services and Supply GNSS Ltd. (GNSS), and finally the complete flooding at the developing Cigar Lake mine (Canada) in October 2006. With the emergence of hedge funds and investors, that began in late 2004, increased uranium demand and upward pressure on market prices were further stimulated. What about the recent events and trends in the uranium industry? Are the uranium producers and the utilities well prepared to meet all the challenges associated with developments in the uranium business? And what about the risks, uncertainties and other factors that could affect the developments in the uranium industry and uranium markets? (orig.)

Uranium exploration planning and strategy

International Nuclear Information System (INIS)

Smith, A.Y.; Tauchid, M.

1991-01-01

A country may decide to begin uranium exploration for any of the following three reasons: 1. To meet the needs of a domestic nuclear power programme; 2. To supply uranium as a commodity to the world market in order to earn foreign exchange; 3. To acquire national information on the country's mineral resource planning. In any of these cases, a country must make some basic decisions regarding the means and modes whereby the uranium exploration will be carried out - by national organizations exclusively; by state organizations in joint venture with outside interests by foreign interests under the control of national regulations. Most uranium exploration is carried out following an exploration strategy in which the programme is divided into a series of steps or stages. Each of the phases is designed to eliminate areas of low potential to contain uranium deposits, while focusing attention on areas of higher potential that will be explored in greater detail at higher cost in the subsequent phase. The methods used in each phase are selected to provide the maximum information at the minimum cost so that at the end of each phase a decision can be made whether to continue to the next phase of stop. Because uranium exploration is a high cost high risk activity, governments must make decisions at the outset whether they wish to carry our the work alone and whether they can support the costs involved, or whether they wish to attract foreign investors to help absorb the costs and therefore the risks. In either case, major policy decisions are required to be made to establish the legal and fiscal environment in which the programm will be carried out. (author). 4 refs, 4 figs

Uranium enrichment plans and policies

International Nuclear Information System (INIS)

Schwennesen, J.L.

1981-01-01

Significant progress has been made in US efforts to expand its enrichment capacity. The Cascade Improvement Program (CIP) and Cascade Upgrading Program (CUP) are now complete at Oak Ridge and Paducah and almost complete at Portsmouth. Considerable progress has also been made in constructing the Gas Centrifuge Enrichment Plant (GCEP), and physical construction of the first process building is well under way. Current plans are to have two process buildings on-line by 1989 with the remaining six buildings to be added sequentially as needed to meet demand. The status of DOE enrichment services contracts is essentially unchanged from that reported at last year's seminar. The OUEA latest forecast of nuclear power growth, however, is considerably lower than reported last year, although a leveling trend is becoming apparent. The Variable Tails Assay Option (VTAO) of the AFC contract was made available for the third time for FY 1983. The DOE inventories of natural uranium still remain high. The Department of Energy will dispose of this material by using it for Government programs and for enrichment plant operations. It appears that Government inventories of uranium are adequate through at least the mid-1990s. It remains DOE policy not to dispose of its natural uranium stocks through direct sales in the marketplace, except for very small quantities or if an emergency situation would exist and all reasonable attempts had been made, without success, to obtain natural uranium from commercial sources. Finally, with regard to DOE plans on future transaction tails assays, it still appears likely that the current 0.20 percent uranium-235 reference tails assay will be maintained until well into the 1990s, at which time it might be increased up to 0.25 percent uranium-235

NEA Uranium Activities: Reliable supply - Safe and environmentally responsible production

International Nuclear Information System (INIS)

Vance, Robert

2014-01-01

Conclusions: • Shift in axis of nuclear power development (and uranium mining) away from OECD countries (83% of world nuclear generating capacity); • Nuclear capacity increase will create additional uranium demand, but countries with the largest and growing demand may meet all requirements using traditional market means; • Market reforms needed in liberalized markets to maintain or increase nuclear generation share; • Opportunities remain for producers, but may need to adjust expectations to these new circumstances; • Secondary supply not done yet

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

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

Best Practice in Environmental Management of Uranium Mining

International Nuclear Information System (INIS)

2010-01-01

generation as an integral part of the strategy of many countries to mitigate their impacts on climate change. The existing uranium mining industry has raised environmental standards through the introduction and development of best practices. One concern is that some of the newer, junior, mining companies and producer nations entering the market in the present expansion phase may not be aware of these best practices and current international standards. Failure to maintain the current high levels of environmental management may see the uranium mining industry's development hampered through the poor performance of a few new, but inexperienced companies, which would result in adverse reactions from the pubic and regulating authorities. This could be especially damaging to the straightforward development of the new resources demanded by the market. As part of a strategy to assist in the maintenance of standards in uranium mining and to assist in the dissemination of information on best practices, the IAEA assisted in the organization of a Technical Meeting on Best Practices in Environmental Management of Uranium Production Facilities, in Saskatoon, Canada, from 22 to 25 June 2004. This report contains the papers presented at that meeting, and the conclusions reached in discussions, together with an overall guide to what is best practice in modern uranium mining

Experimental Plan: Uranium Stabilization Through Polyphosphate Injection 300 Area Uranium Plume Treatability Demonstration Project

Energy Technology Data Exchange (ETDEWEB)

Wellman, Dawn M.; Fruchter, Jonathan S.; Vermeul, Vince R.

2006-09-20

This Test Plan describes a laboratory-testing program to be performed at Pacific Northwest National Laboratory (PNNL) in support of the 300-FF-5 Feasibility Study (FS). The objective of the proposed treatability test is to evaluate the efficacy of using polyphosphate injections to treat uranium contaminated groundwater in situ. This study will be used to: (1) Develop implementation cost estimates; (2) Identify implementation challenges; and (3) Investigate the technology's ability to meet remedial objectives These activities will be conducted in parallel with a limited field investigation, which is currently underway to more accurately define the vertical extent of uranium in the vadose zone, and in the capillary fringe zone laterally throughout the plume. The treatability test will establish the viability of the method and, along with characterization data from the limited field investigation, will provide the means for determining how best to implement the technology in the field. By conducting the treatability work in parallel with the ongoing Limited Field Investigation, the resulting Feasibility Study (FS) will provide proven, site-specific information for evaluating polyphosphate addition and selecting a suitable remediation strategy for the uranium plume within the FS time frame at an overall cost savings.

Summary records of meetings of INFCE/WG.1 - First to seventh meetings

International Nuclear Information System (INIS)

Seven meetings of INFCE/WG.1 were held in the period of 26 January 1978 to 14 September 1979. The activities of Working Group 1 during this period are presented in 7 Summary Records. The main activity areas are: revision of uranium, heavy water and thorium availability; consideration of special needs of developing countries

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

Proceedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors

Energy Technology Data Exchange (ETDEWEB)

1993-07-01

The international effort to develop and implement new research reactor fuels utilizing low-enriched uranium, instead of highly- enriched uranium, continues to make solid progress. This effort is the cornerstone of a widely shared policy aimed at reducing, and possibly eliminating, international traffic in highly-enriched uranium and the nuclear weapon proliferation concerns associated with this traffic. To foster direct communication and exchange of ideas among the specialists in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at Argonne National Laboratory, sponsored this meeting as the eleventh of a series which began 1978. Individual papers presented at the meeting have been cataloged separately.

Proceedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors

International Nuclear Information System (INIS)

1993-07-01

The international effort to develop and implement new research reactor fuels utilizing low-enriched uranium, instead of highly- enriched uranium, continues to make solid progress. This effort is the cornerstone of a widely shared policy aimed at reducing, and possibly eliminating, international traffic in highly-enriched uranium and the nuclear weapon proliferation concerns associated with this traffic. To foster direct communication and exchange of ideas among the specialists in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at Argonne National Laboratory, sponsored this meeting as the eleventh of a series which began 1978. Individual papers presented at the meeting have been cataloged separately

Research and application for wastewater treatment technology in a southern uranium mine

International Nuclear Information System (INIS)

Tan Jianhua; Zhao Jinfang; Huang Yunbai; Deng Jianguo

2014-01-01

This paper analyzes the source and property of a southern uranium mine's drainage and the treatment technology is tested, and proposed by employing the process of '408 (Ⅱ) resin adsorption-NaCl + NaHCO 3 elution '. The results show that the treated drainage can meet the emission requirement of Regulations for radiation and environment protection in uranium mining and milling (GB23727-2009), with the uranium content being less than 0.3 mg/L -l . The econo-technical norms such as material consumption are improved as the new technology has been applied in practical production. (authors)

Origin of sandstone-hosted uranium deposits, Frome Embayment, South Australia

International Nuclear Information System (INIS)

Sanford, R.F.

1985-01-01

The formation of sandstone-hosted uranium deposits in the Frome Embayment of South Australia is largely a result of tectonic events possibly as old as the Archean. Uranium deposits of several types and ages in the region demonstrate the importance of uranium enrichment in the source area. Mobile zones around the Archean terrane of the Gawler block have been the locus of intermittent tectonic activity from Early Proterozoic to recent time. Vein-type uranium deposits in basement source rocks are concentrated in these zones, because they favor deep crustal partial melting and ascent of Na-rich granitic magmas and hydrothermal solutions. Relatively stable areas bordered by mobile zones, are important for the formation of sandstone-hosted uranium deposits because they act as platforms for terrigenous sedimentation from the surrounding, uplifted, uranium-rich basement rocks. Wet, subtropical conditions prevailing at the time of uplift aided rapid erosion and subaerial deposition of channel sands with intermixed organic detritus. Later uplift accompanied by erosion of the recently deposited sands in the headwater area caused increased recharge of oxygenated uraniferous ground water, which led to the formation of geochemical-cell roll-front type deposits like those in the Wyoming basins. Subsequent arid conditions helped preserve the deposits. (author)

Human resource development for uranium production cycle

International Nuclear Information System (INIS)

Ganguly, C.

2014-01-01

Nuclear fission energy is a viable option for meeting the ever increasing demand for electricity and high quality process heat in a safe, secured and sustainable manner with minimum carbon foot print and degradation of the environment. The growth of nuclear power has shifted from North America and Europe to Asia, mostly in China and India. Bangladesh, Vietnam, Indonesia, Malaysia and the United Arab Emirates are also in the process of launching nuclear power program. Natural uranium is the basic raw material for U-235 and Pu-239, the fuels for all operating and upcoming nuclear power reactors. The present generation of nuclear power reactors are mostly light water cooled and moderated reactor (LWR) and to a limited extent pressurized heavy water reactor (PHWR). The LWRs and PHWRs use low enriched uranium (LEU with around 5% U-235) and natural uranium as fuel in the form of high density UO_2 pellets. The uranium production cycle starts with uranium exploration and is followed by mining and milling to produce uranium ore concentrate, commonly known as yellow cake, and ends with mine and mill reclamation and remediation. Natural uranium and its daughter products, radium and radon, are radioactive and health hazardous to varying degrees. Hence, radiological safety is of paramount importance to uranium production cycle and there is a need to review and share best practices in this area. Human Resource Development (HRD) is yet another challenge as most of the experts in this area have retired and have not been replaced by younger generation because of the continuing lull in the uranium market. Besides, uranium geology, exploration, mining and milling do not form a part of the undergraduate or post graduate curriculum in most countries. Hence, the Technical Co-operation activities of the IAEA are required to be augmented and more country specific and regional training and workshop should be conducted at different universities with the involvement of international experts

Extending the world's uranium resources through advanced CANDU fuel cycles

Energy Technology Data Exchange (ETDEWEB)

De Vuono, Tony; Yee, Frank; Aleyaseen, Val; Kuran, Sermet; Cottrell, Catherine

2010-09-15

The growing demand for nuclear power will encourage many countries to undertake initiatives to ensure a self-reliant fuel source supply. Uranium is currently the only fuel utilized in nuclear reactors. There are increasing concerns that primary uranium sources will not be enough to meet future needs. AECL has developed a fuel cycle vision that incorporates other sources of advanced fuels to be adaptable to its CANDU technology.

Remedial Action Programs annual meeting: Proceedings

International Nuclear Information System (INIS)

1988-01-01

Within the DOE's Office of Nuclear Energy, the Office of Remedial Action and Waste Technology manages a number of programs whose purposes are to complete remedial actions at DOE facilities and sites located throughout the United States. These programs include the Surplus Facilities Management Program, the Formerly Utilized Sites Remedial Action Program, the Uranium Mill Tailings remedial Action Program and the West Valley Demonstration Project. The programs involve the decontamination and decommissioning of radioactively-contaminated structures and equipment, the disposal of uranium mill tailings, and the cleanup or restoration of soils and ground water that have been contaminated with radioactive hazardous substances. Each year the DOE and DOE-contractor staff who conduct these programs meet to exchange information and experience in common technical areas. This year's meeting was hosted by the Surplus Facilities Management Program and was held near DOE Headquarters, in Gaithersburg, Maryland. This volume of proceedings provides the record for the meeting. The proceedings consist of abstracts for each presentation made at the meeting, and the visual aids (if any) used by the speakers. The material is organized in the following pages according to the five different sessions at the meeting: Session 1: Environmental Compliance--Policy; Session 2: Environmental Compliance--Practice; Session 3: Reports from working groups; Session 4: DandD Technology; and Session 5: Remedial Action Technology. The agenda for the meeting and the list of meeting registrants are provided in Appendix A and B, respectively. Individual papers are processed separately for the data base

Uranium dependence and the proliferation problem

International Nuclear Information System (INIS)

Jacoby, H.D.

1977-01-01

A 20-year ''breathing space'' of adequate uranium supplies is felt to warrant delaying breeder technology until the threat of proliferation can be met with adequate internationally controlled stockpiles and marketing. Although a shift to breeder reactors developed as concern grew over the possibility of depleted uranium reserves, U.S. policy has now reversed this trend in favor of nuclear systems with a lower risk of proliferation. A review of uranium dependence analyzes the fuel cycle, current and projected reserves, reliable enrichment services, and international effects of proliferation and market disruptions. Uranium supply forecasts are more positive now because overstated reactor buildup projections led utilities to order more fuel than they will need until the late 1980s. These surpluses of light-water reactor fuel could be stockpiled at a cost of $20 billion, felt to be a relatively modest figure in terms of the total cost of nuclear power. A stockpile able to meet demand levels could offer the security of domestic supplies with trade opportunities and would retain levels of exploration and extraction. Several strategies for managing stockpiles are possible, but international control is seen as the best way to maintain reliable prices and uniform supply policies for all nations

LASL approach to uranium geochemical reconnaissance

Energy Technology Data Exchange (ETDEWEB)

Sharp, R.R. Jr.

1977-01-01

The US ERDA, as part of the NURE program, has initiated a nationwide Hydrogeochemical and Stream Sediment Reconnaissance (HSSR). The aims of the NURE program are to provide data on which to base more accurate estimates of US uranium reserves for long-range planning and to aid in meeting the nation's projected uranium demands into the next century. The HSSR objective is to complete, by 1980, a reconnaissance of the nation's surface waters, ground waters, and stream and lake sediments, to aid in assessment of uranium reserves and identification of areas of interest for exploration. Patterned after extensive uranium reconnaissance done in many other countries, the LASL project is comprised of the following five components: (1) organization and planning, which includes management, design, and execution; (2) field sampling, which includes orientation studies, generation of specifications, and contracting and inspection of field work; (3) sample receiving and analysis, which includes development of methods and hardware, quality assurance, and archival storage; (4) data handling and presentation, including verification, storage, output, and plotting; and (5) data evaluation and publication, which incorporates geochemical, geological, statistical, and empirical evaluation and report writing. The LASL approach to each component and the current status in each state are described.

LASL approach to uranium geochemical reconnaissance

International Nuclear Information System (INIS)

Sharp, R.R. Jr.

1977-01-01

The US ERDA, as part of the NURE program, has initiated a nationwide Hydrogeochemical and Stream Sediment Reconnaissance (HSSR). The aims of the NURE program are to provide data on which to base more accurate estimates of US uranium reserves for long-range planning and to aid in meeting the nation's projected uranium demands into the next century. The HSSR objective is to complete, by 1980, a reconnaissance of the nation's surface waters, ground waters, and stream and lake sediments, to aid in assessment of uranium reserves and identification of areas of interest for exploration. Patterned after extensive uranium reconnaissance done in many other countries, the LASL project is comprised of the following five components: (1) organization and planning, which includes management, design, and execution; (2) field sampling, which includes orientation studies, generation of specifications, and contracting and inspection of field work; (3) sample receiving and analysis, which includes development of methods and hardware, quality assurance, and archival storage; (4) data handling and presentation, including verification, storage, output, and plotting; and (5) data evaluation and publication, which incorporates geochemical, geological, statistical, and empirical evaluation and report writing. The LASL approach to each component and the current status in each state are described

The changing picture of uranium exploration

International Nuclear Information System (INIS)

Duval, B.C.

1977-01-01

The purposes of this paper are: firstly, to analyse the factors determining exploration strategies, special emphasis being given to the task of defining exploration targets as dictated by projected demand, and to discussing the chances of making new discoveries necessary to meet this challenge; secondly, to delineate the main trends apparent in exploration activities across the free world and to interpret them in the light of this analysis; and, thirdly, to show how the exploration activities of an independent company like Minatome specifically illustrate these points. The various aspects covered include: natural uranium requirements for nuclear power reactors on line, 1970 to 2025; cumulative natural uranium requirements for the same period; availability of economic reserves; geological aspects; financial and political factors; exploration techniques. (U.K.)

Reuse of ammonium fluoride generated in the uranium hexafluoride conversion

International Nuclear Information System (INIS)

Silva Neto, J.B.; Carvalho, E.F. Urano de; Durazzo, M.; Riella, H.G

2010-01-01

The Nuclear Fuel Centre of IPEN / CNEN - SP develops and manufactures dispersion fuel with high uranium concentration to meet the demand of the IEA-R1 reactor and future research reactors planned to be constructed in Brazil. The fuel uses uranium silicide (U 3 Si 2 ) dispersed in aluminum. For producing the fuel, the processes for uranium hexafluoride (UF 6 ) conversion consist in obtaining U 3 Si 2 and / or U 3 O 8 through the preparation of intermediate compounds, among them ammonium uranyl carbonate - AUC, ammonium diuranate - DUA and uranium tetrafluoride - UF 4 . This work describes a procedure for preparing uranium tetrafluoride by a dry route using as raw material the filtrate generated when producing routinely ammonium uranyl carbonate. The filtrate consists primarily of a solution containing high concentrations of ammonium (NH 4 + ), fluoride (F - ), carbonate (CO 3 -- ) and low concentrations of uranium. The procedure is basically the recovery of NH 4 F and uranium, as UF 4 , through the crystallization of ammonium bifluoride (NH 4 HF 2 ) and, in a later step, the addition of UO 2 , occurring fluoridation and decomposition. The UF 4 obtained is further diluted in the UF 4 produced routinely at IPEN / CNEN-SP by a wet route process. (author)

Challenges in the front end of the uranium fuel cycle

International Nuclear Information System (INIS)

Seitz, Ken

2010-01-01

The long-term fundamentals for nuclear remain strong. Climate change and clean air concerns remain high on the agenda of national energy policies, as both developing and developed economies pursue a strategy of energy diversity and energy security. A global industry of 435 reactors is expected to grow to more than 639 reactors within the next 20 years with the potential for even more rapid expansion. This nuclear generating capacity relies on an international fuel cycle that can ensure stable and secure supply for decades to come. As the first step in the fuel cycle, the uranium industry has received various price signals over the past 5 decades, from the birth of an industry with strong demand and stock pile building and the associated robust pricing and new production stimulation, to an industry in decline and a period marked by liquidation of large inventories, to the recent resurgence of nuclear and the associated uranium price signals. In many ways, understanding the current uranium environment and the outlook for the industry requires some understanding of these phases of nuclear. The global nuclear fleet today needs about 65,000 tonnes of uranium per year to meet reactor feed requirements. Primary production meets about two thirds of this requirement while the remainder is drawn from secondary supply. Secondary supply can essentially be described as stockpiles of previously produced uranium. However, secondary supplies are finite and more primary production will be needed. From a long-term perspective, there is no question that there are sufficient uranium resources to support the nuclear industry for many years to come. The IAEA's 'Red Book' estimates that more than 5 million tonnes of known resources could potentially be developed at today's prices. This is enough to supply the global reactor fleet for almost 80 years at current usage rates. Recently higher uranium prices have resulted in some production increases although the rate of growth has been held

Accurate and precise determination of small quantity uranium by means of automatic potentiometric titration

International Nuclear Information System (INIS)

Liu Quanwei; Luo Zhongyan; Zhu Haiqiao; Wu Jizong

2007-01-01

For high radioactivity level of dissolved solution of spent fuel and the solution of uranium product, radioactive hazard must be considered and reduced as low as possible during accurate determination of uranium. In this work automatic potentiometric titration was applied and the sample only 10 mg of uranium contained was taken in order to reduce the harm of analyzer suffered from the radioactivity. RSD<0.06%, at the same time the result can be corrected for more reliable and accurate measurement. The determination method can effectively reduce the harm of analyzer suffered from the radioactivity, and meets the requirement of reliable accurate measurement of uranium. (authors)

Developments in natural uranium - graphite reactors

International Nuclear Information System (INIS)

Bourgeois, J.

1964-01-01

The French natural uranium-graphite power-reactor programme has been developing - from EDF 1 to EDF 4 - in the direction of an increase of the unit power of the installations, of the specific and volume powers, and of an improvement in the operational security conditions. The high power of EDF 4 (500 MWe) and the integration of the primary circuit into the reactor vessel, which is itself made of pre-stressed concrete, make it possible to make the most of the annular fuel elements already in use in EDF 1, and to arrive thus at a very satisfactory solution. The use of an internally cooled fuel element (an annular element) has led to a further step forward: it now becomes possible to increase the pressure of the cooling gas without danger of causing creep in the uranium tube. The use of a pre-stressed concrete vessel makes this pressure increase possible, and the integration of the primary circuit avoids the risk of a rapid depressurization which would be in this case a major danger. This report deals with the main problems presented by this new type of nuclear power station, and gives the main lines of research and studies now being carried out in France. - Neutronic and thermal research has made it possible to consider using large size fuel elements (internal diameter = 77 mm, external diameter 95 mm) while still using natural uranium. - The problems connected with the production of these elements and with their in pile behaviour are the subject of a large programme, both out of pile and in power reactors (EDF 2) and test reactors (Pegase). - The increase in the size of the element leads to a large lattice pitch (35 to 40 cm). This makes it possible to consider having one charging aperture per channel or for a small number of channels, whether the charge machine be inside or outside the pressure vessel. In conclusion are given the main characteristics of a project for a 500 MWe power station using such a fuel element. In particular this project is compared to EDF 4

Uranium mining and metallurgy library information service under the network environment

International Nuclear Information System (INIS)

Tang Lilei

2012-01-01

This paper analyzes the effect of the network environment on the uranium mining and metallurgy of the information service. Introduces some measures such as strengthening professional characteristic literature resources construction, changing the service mode, building up information navigation, deepening service, meet the individual needs of users, raising librarian's quality, promoting the co-construction and sharing of library information resources, and puts forward the development idea of uranium mining and metallurgy library information service under the network environment. (author)

Use of reprocessed uranium. Proceedings of a technical committee meeting held in Vienna, August 2007

International Nuclear Information System (INIS)

2009-11-01

Reprocessed uranium (RepU), the uranium recovered from nuclear processing, is produced by several Member States in their facilities or through commercial contracts. From a sustainable development perspective, recycling of this uranium has become an attractive option for improving the efficiency of natural resource management and reducing radioactive waste accumulation. This publication demonstrates that reprocessing of spent fuel could form a key part of advanced fuel methodologies and describes various reuse options of RepU. In particular, it includes detailed review papers on management, storage, packaging and transport of RepU, reprocessing, utility experience and potential use of RepU. The importance of market aspects, economics and long term perspectives is also addressed

Radiological considerations in the design of Reprocessing Uranium Plant (RUP) of Fast Reactor Fuel Cycle Facility (FRFCF), Kalpakkam

International Nuclear Information System (INIS)

Chandrasekaran, S.; Rajagopal, V.; Jose, M.T.; Venkatraman, B.

2012-01-01

A Fast Reactor Fuel Cycle Facility (FRFCF) being planned at Indira Gandhi Centre for Atomic Research, Kalpakkam is an integrated facility with head end and back end of fuel cycle plants co-located in a single place, to meet the refuelling needs of the prototype fast breeder reactor (PFBR). Reprocessed uranium oxide plant (RUP) is one such plant in FRFCF to built to meet annual requirements of UO 2 for fabrication of fuel sub-assemblies (FSAs) and radial blanket sub-assemblies (RSAs) for PFBR. RUP receives reprocessed uranium oxide powder (U 3 O 8 ) from fast reactor fuel reprocessing plant (FRP) of FRFCF. Unlike natural uranium oxide plant, RUP has to handle reprocessed uranium oxide which is likely to have residual fission products activity in addition to traces of plutonium. As the fuel used for PFBR is recycled within these plants, formation of higher actinides in the case of plutonium and formation of higher levels of 232 U in the uranium product would be a radiological problem to be reckoned with. The paper discussed the impact of handling of multi-recycled reprocessed uranium in RUP and the radiological considerations

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

Technology and the uranium industry

International Nuclear Information System (INIS)

Pool, T.C.

2000-01-01

Continuing economic and regulatory pressures on the uranium industry can be countered only through advances in technology. Low prices, the 'ALARA' principle, and concerns about 'sustainability' require the industry to continually improve upon its already impressive record of performance. Technological improvement in the uranium industry is necessary in order to: 1) Maintain our resource base through the discovery of ever deeper deposits; 2) Improve the efficiency with which we may exploit - a) very high-grade deposits by remote underground mining methods - b) very low-grade deposits with environmentally-benign, in situ, leaching methods - and c) moderate-grade, near-surface deposits by open-pit mining methods; 3) Meet increasingly stringent and, in many cases, arbitrary and unrealistic environmental and safety requirements; and 4) Cope with increasing competition from an expanding number of sources of secondary supply. Manifestations of the uranium industry's ability to improve its performance through technology can be seen in many ways including: a continuing reduction in production costs; large gains in productivity; and a truly superior record of employee safety. Maintenance of these trends requires both innovation and the open sharing of information. (author)

Technology and the uranium industry

International Nuclear Information System (INIS)

Pool, T.C.

2002-01-01

Continuing economic and regulatory pressures on the uranium industry can be countered only through advances in technology. Low prices, the 'ALARA' principle, and concerns about 'sustainability' require the industry to continually improve upon its already impressive record of performance. Technological improvement in the uranium industry is necessary in order to: (a) Maintain our resource base through the discovery of ever deeper deposits; (b) Improve the efficiency with which we may exploit (i) very high-grade deposits by remote underground mining methods (ii) very low-grade deposits with environmentally-benign, in situ leaching methods - and (iii) moderate-grade, near-surface deposits by open-pit mining methods (c) Meet increasingly stringent and, in many cases, arbitrary and unrealistic environmental and safety requirements; and (d) Cope with increasing competition from an expanding number of sources of secondary supply. Manifestations of the uranium industry's ability to improve its performance through technology can be seen in many ways including: a continuing reduction in production costs; large gains in productivity; and a truly superior record of employee safety. Maintenance of these trends requires both innovation and the open sharing of information. (author)

Uranium enrichment. Technology, economics, capacity

International Nuclear Information System (INIS)

Voigt, W.R. Jr.; Saire, D.E.; Gestson, D.K.; Peske, S.E.; Vanstrum, P.R.

1983-01-01

Large-scale enrichment of uranium has now been carried out for 40 years. While the gaseous diffusion process was the original choice of several countries and continues today to provide the major component of the world production of separative work, the last two decades have witnessed the development of a number of alternative processes for enrichment. These processes, which are being studied and deployed around the world, offer a wide range of technical and economic characteristics which will be useful in assuring adequate capacity to meet projected reactor fuel market needs through the rest of this century at competitive prices. With present uncertainties in future enriched uranium needs, it is apparent that flexibility in the deployment and operation of any enrichment process will be one of the prime considerations for the future. More economical production of separative work not only can have a beneficial impact on reactor fuel costs, but also tends to conserve natural uranium resources. This paper reviews the world scene in the enrichment component of the fuel cycle, including existing or planned commercial-scale facilities and announced R+D efforts on various processes. (author)

Uranium enrichment: technology, economics, capacity

Energy Technology Data Exchange (ETDEWEB)

Voigt, Jr., W. R.; Vanstrum, P. R.; Saire, D. E.; Gestson, D. K.; Peske, S. E.

1982-08-01

Large-scale enrichment of uranium has now been carried out for 40 years. While the gaseous diffusion process was the original choice of several countries and continues today to provide the major component of the world production of separative work, the last two decades have witnessed the development of a number of alternative processes for enrichment. These processes, which are being studied and deployed around the world, offer a wide range of technical and economic characteristics which will be useful in assuring adequate capacity to meet projected reactor fuel market needs through the rest of this century at competitive prices. With present uncertainties in future enriched uranium needs, it is apparent that flexibility in the deployment and operation of any enrichment process will be one of the prime considerations for the future. More economical production of separative work not only can have a beneficial impact on reactor fuel costs, but also tends to conserve natural uranium resources. This paper reviews the world scene in the enrichment component of the fuel cycle, including existing or planned commercial-scale facilities and announced R and D efforts on various processes.

Uranium enrichment: technology, economics, capacity

International Nuclear Information System (INIS)

Voigt, W.R. Jr.; Vanstrum, P.R.; Saire, D.E.; Gestson, D.K.; Peske, S.E.

1982-01-01

Large-scale enrichment of uranium has now been carried out for 40 years. While the gaseous diffusion process was the original choice of several countries and continues today to provide the major component of the world production of separative work, the last two decades have witnessed the development of a number of alternative processes for enrichment. These processes, which are being studied and deployed around the world, offer a wide range of technical and economic characteristics which will be useful in assuring adequate capacity to meet projected reactor fuel market needs through the rest of this century at competitive prices. With present uncertainties in future enriched uranium needs, it is apparent that flexibility in the deployment and operation of any enrichment process will be one of the prime considerations for the future. More economical production of separative work not only can have a beneficial impact on reactor fuel costs, but also tends to conserve natural uranium resources. This paper reviews the world scene in the enrichment component of the fuel cycle, including existing or planned commercial-scale facilities and announced R and D efforts on various processes

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.

Application of liquid-liquid extraction in uranium hydrometallurgy (Paper No. : V-1)

Energy Technology Data Exchange (ETDEWEB)

Murthy, T K.S.; Koppiker, K S

1979-01-01

Uranium recovery from the ores is carried out exclusively by hydrometallurgical techniques. The initial solubilisation of uranium is achieved by either sodium carbonate or sulphuric acid leaching, the latter being more common. Further purification and upgrading of uranium from the sulphate liquors is carried out by an ion-exchange process. Solid resin type anion exchangers or liquid ion-exchangers are employed. The processing of uranium liquors is, perhaps, the first major application of liquid-liquid extraction in metal recovery. Organophosphoric acids were initially used but later the long-chain aliphatic amines have superseded them. The amine extraction system has been widely studied and several variations are now known. Chloride, nitrate, carbonate or sulphate or acid stripping can be used for getting back the uranium into the aqueous phase. Combination of ion exchange (resin type) and solvent extraction processes called Eluex processes are developed for special applications. Studies have also been made of solvent extraction of uranium from leach pulps instead of clear liquors. Tributylphosphate has found wide application in the refining of uranium concentrates to meet the stringent needs of nuclear purity. liquid-liquid extraction is, perhaps, the only successful technique for the recovery of uranium, as by-product, from wet-process phosphoric acid. This has opened up a new source of uranium.

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)

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 recovery from slags of metallic uranium

International Nuclear Information System (INIS)

Fornarolo, F.; Frajndlich, E.U.C.; Durazzo, M.

2006-01-01

The Center of the Nuclear Fuel of the Institute of Nuclear Energy Research - IPEN finished the program of attainment of fuel development for research reactors the base of Uranium Scilicet (U 3 Si 2 ) from Hexafluoride of Uranium (UF 6 ) with enrichment 20% in weight of 235 U. In the process of attainment of the league of U 3 Si 2 we have as Uranium intermediate product the metallic one whose attainment generates a slag contend Uranium. The present work shows the results gotten in the process of recovery of Uranium in slags of calcined slags of Uranium metallic. Uranium the metallic one is unstable, pyrophoricity and extremely reactive, whereas the U 3 O 8 is a steady oxide of low chemical reactivity, what it justifies the process of calcination of slags of Uranium metallic. The calcination of the Uranium slag of the metallic one in oxygen presence reduces Uranium metallic the U 3 O 8 . Experiments had been developed varying it of acid for Uranium control and excess, nitric molar concentration gram with regard to the stoichiometric leaching reaction of temperature of the leaching process. The 96,0% income proves the viability of the recovery process of slags of Uranium metallic, adopting it previous calcination of these slags in nitric way with low acid concentration and low temperature of leaching. (author)

Uranium, depleted uranium, biological effects; Uranium, uranium appauvri, effets biologiques

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

Physicists, chemists and biologists at the CEA are developing scientific programs on the properties and uses of ionizing radiation. Since the CEA was created in 1945, a great deal of research has been carried out on the properties of natural, enriched and depleted uranium in cooperation with university laboratories and CNRS. There is a great deal of available data about uranium; thousands of analyses have been published in international reviews over more than 40 years. This presentation on uranium is a very brief summary of all these studies. (author)

Narrative depositional systems on the area with Nalinggou the relationship between uranium mineralization

International Nuclear Information System (INIS)

Meng Rui

2012-01-01

For sandstone-type uranium deposits in China began to research the late 1950s, 1990s in-situ leachable sand stone-type uranium deposits has become China's industrial significance of the important uranium deposits type. The sedimentary system analysis in in-situ leachable sandstone-type uranium deposit research plays a very important role. Based on the sedimentary system analysis and sequence stratigraphy as the basis, the area of Nalinggou on ridge middle Jurassic straight ROM group sedimentary system characteristics, middle Jurassic straight ROM group of sand body thickness, the area on ridge aspects of river channel exhibition cloth direction studied that: (1) river space distribution direction control the sand body cloth of the spatial distribution, then affects fu cloth of the spatial distribution of uranium sand body; (2) the evolution of the sedimentary environment created a good sand sequence distribution and enrichment conditions intercalation, be helpful for interlayer oxidation effect; (3) sequence of sedimentary control three layer structure lithology space combination. (authors)

A special kind of sandstone-type uranium deposit related to Jurassic palaeochannel systems in the northeastern Ordos Basin, China

International Nuclear Information System (INIS)

Li Ziying; Fang Xiheng; Xia Yuliang; Sun Ye; Jiao Yangquan; Chen Anping; Zhang Ke

2010-01-01

Dongsheng sandstone-type uranium deposit is a large one discovered in recent years in the northeastern Ordos Basin, China. It is a special kind of sandstone-type uranium deposit,different from other ordinary sandstone-type deposits because of its unique signatures. It is generally controlled by a transitional zone between greenish and grayish sandstones, both of those two kinds of sandstones now indicate reduced geochemical environments. The greenish color of the palaeo-oxidized sandstones mainly results from chloritization and epidotization related to oil and gas secondary reduction processes. The deposit genetically is different from ordinary sandstone uranium deposits,which is of more complex origin,undergoing not only palaeo-oxidization mineralization process, but also oil-gas fluid and hydrothermal reworking processes. It is spatially related to Jurassic Zhiluo Formation with braided palaeo channel systems. The uranium mineralization zone with higher grade usually exists in the branching area of the distributary channels of main braided streams, whose sandstone heterogeneity shows a transfer sedimentary facies from the braided stream sedimentary system to the braided delta sedimentary system. Statistical results show that medium and fine-grained sandstones are the most favorable rock types for uranium mineralization. (authors)

Orientation geochemical survey for uranium exploration using 230Th

International Nuclear Information System (INIS)

Xia Dingliang.

1985-01-01

The distribution of 230 Th in soils, rocks and ores and its relationship with respect to uranium ore formation are discussed for its possible use in geochemical exploration for U. 230 Th, U and Ra, being members of the same decay series, are different in their geochemical behavior upon which the study is orientated. Twenty uranium deposits and occurrences located in western and southern Hunan province are tested. Geochemical data obtained are comprehensively correlated. It is suggested that 230 Th is useful not only in U-Ra disequilibrium study but also in understanding the geochemical evolution of U ores. The data aid to interpret the genesis of uranium deposits and to assess the radioactive anomalies and uranium-bearing zones. Therefore, it can be adopted as a tool for searching in deep-buried uranium ores. The field procedure is rather simple and flexible to meet any geological environment. It is easy to read out and is less influnced by any kind of interference. In case of disequilibrium caused by oxidation and reduction during the period of ore formation it still gives good indication compared with that of radiometry, radonmetry and geochemical sampling for U

Device for safe disposal of non-utilizable cuttings from depleted uranium metal

International Nuclear Information System (INIS)

Fiala, B.

1991-01-01

A device was developed for the production of U 3 O 8 from cuttings of depleted uranium metal or of uranium metal waste whose surface area is sufficiently large for combustion. The waste may contain organic impurities or other metals. The purity of the U 3 O 8 thus obtained is about 98%. Tests gave evidence that the combustion facility meets all requirements set forth by hygienic and ecological regulations. (Z.M.). 1 fig

Are world uranium resources sufficient to fuel global growth in nuclear generating capacity?

International Nuclear Information System (INIS)

Cameron, R.; Vance, R.E.

2012-01-01

Increased uranium prices since 2003 have produced more activity in the sector than the previous 20 years. Nuclear reactor construction is proceeding in some countries, ambitious expansion plans have been announced in others and several, particularly in the developing world, are considering introducing nuclear power as a means of meeting rising electricity demand without increasing greenhouse gas emissions. Others have recently decided to either withdraw from the use of nuclear power or not proceed with development plans following the accident at the Fukushima Dai-ichi nuclear power plant in Japan in March 2011. Since the mid-1960, the OECD Nuclear Energy Agency and the International Atomic Energy Agency have jointly prepared a comprehensive update of global uranium resources, production and demand (commonly known as the 'Red Book'. The Red Book is based on government responses to a questionnaire that requests information on uranium exploration and mine development activity, resources and plans for nuclear development to 2035. This presentation provides an overview of the global situation based on the recently published 2011 edition. It features a compilation of global uranium resources, projected mine development and production capability in all the countries currently producing uranium or with plans to do so in the near future. This is compared to updated, post-Fukushima demand projections, reflecting nuclear phase-out plans announced in some countries and ambitious expansion plans of others. The 2011 Red Book shows that currently defined uranium resources are sufficient to meet high case projections of nuclear power development to 2035. (authors)

Powder Metallurgy of Uranium Alloy Fuels for TRU-Burning Reactors Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

McDeavitt, Sean M

2011-04-29

outlining the beginning of the materials processing setup. Also included within this section is a thesis proposal by Jeff Hausaman. Appendix C contains the public papers and presentations introduced at the 2010 American Nuclear Society Winter Meeting. Appendix A—MSNE theses of David Garnetti and Grant Helmreich and proposal by Jeff Hausaman A.1 December 2009 Thesis by David Garnetti entitled “Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications” A.2 September 2009 Presentation by David Garnetti (same title as document in Appendix B.1) A.3 December 2010 Thesis by Grant Helmreich entitled “Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications” A.4 October 2010 Presentation by Grant Helmreich (same title as document in Appendix B.3) A.5 Thesis Proposal by Jeffrey Hausaman entitled “Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors” Appendix B—External presentations introduced at the 2010 ANS Winter Meeting B.1 J.S. Hausaman, D.J. Garnetti, and S.M. McDeavitt, “Powder Metallurgy of Alpha Phase Uranium Alloys for TRU Burning Fast Reactors,” Proceedings of 2010 ANS Winter Meeting, Las Vegas, Nevada, USA, November 7-10, 2010 B.2 PowerPoint Presentation Slides from C.1 B.3 G.W. Helmreich, W.J. Sames, D.J. Garnetti, and S.M. McDeavitt, “Uranium Powder Production Using a Hydride-Dehydride Process,” Proceedings of 2010 ANS Winter Meeting, Las Vegas, Nevada, USA, November 7-10, 2010 B.4. PowerPoint Presentation Slides from C.3 B.5 Poster Presentation from C.3 Appendix C—Fuel cycle research and development undergraduate materials and poster presentation C.1 Poster entitled “Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys” presented at the Fuel Cycle Technologies Program Annual Meeting C.2 April 2011 Honors Undergraduate Thesis

Powder Metallurgy of Uranium Alloy Fuels for TRU-Burning Reactors Final Technical Report

International Nuclear Information System (INIS)

McDeavitt, Sean M.

2011-01-01

beginning of the materials processing setup. Also included within this section is a thesis proposal by Jeff Hausaman. Appendix C contains the public papers and presentations introduced at the 2010 American Nuclear Society Winter Meeting. Appendix A - MSNE theses of David Garnetti and Grant Helmreich and proposal by Jeff Hausaman A.1 December 2009 Thesis by David Garnetti entitled 'Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications' A.2 September 2009 Presentation by David Garnetti (same title as document in Appendix B.1) A.3 December 2010 Thesis by Grant Helmreich entitled 'Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications' A.4 October 2010 Presentation by Grant Helmreich (same title as document in Appendix B.3) A.5 Thesis Proposal by Jeffrey Hausaman entitled 'Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors' Appendix B - External presentations introduced at the 2010 ANS Winter Meeting B.1 J.S. Hausaman, D.J. Garnetti, and S.M. McDeavitt, 'Powder Metallurgy of Alpha Phase Uranium Alloys for TRU Burning Fast Reactors,' Proceedings of 2010 ANS Winter Meeting, Las Vegas, Nevada, USA, November 7-10, 2010 B.2 PowerPoint Presentation Slides from C.1 B.3 G.W. Helmreich, W.J. Sames, D.J. Garnetti, and S.M. McDeavitt, 'Uranium Powder Production Using a Hydride-Dehydride Process,' Proceedings of 2010 ANS Winter Meeting, Las Vegas, Nevada, USA, November 7-10, 2010 B.4. PowerPoint Presentation Slides from C.3 B.5 Poster Presentation from C.3 Appendix C - Fuel cycle research and development undergraduate materials and poster presentation C.1 Poster entitled 'Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys' presented at the Fuel Cycle Technologies Program Annual Meeting C.2 April 2011 Honors Undergraduate Thesis by William Sames, Research Fellow

Consideration of hot channel factors in design for providing operating margins on coolant channel outlet temperature

International Nuclear Information System (INIS)

Sharma, V.K.; Surendar, C.; Bapat, C.N.

1994-01-01

The Indian Pressurized Heavy Water Reactors (IPHWR) are horizontal pressure tube reactors using natural uranium oxide fuel in the form of short (495 mm) clusters. The fuel clusters in the Zr-Nb pressure tubes are cooled by high pressure, high temperature and subcooled circulating heavy water. Coolant flow distribution to individual channels is designed to match the power distribution so as to obtain uniform coolant outlet temperature. However, during operation, the coolant outlet temperature in individual channels deviate from their nominal value due to: tolerances in process design; effects of grid frequency on the pump speed; deviation in channel powers from the nominal values due to on-power fuelling and movement of reactivity devices, and so on. Thus an operating margin, between the highest permissible and nominal coolant outlet temperatures, is required taking into account various hot channel factors that contribute to higher coolant outlet temperatures. The paper discusses the methodology adopted to assess various hot channel factors which would provide optimum operating margins while ensuring sub-cooling. (author)

2. biophysical work meeting

International Nuclear Information System (INIS)

1992-11-01

The report comprises 18 papers held at the 2nd Biophysical Work Meeting, 11 - 13 September 1991 in Schlema, Germany. The history of biophysics in Germany particularly of radiation biophysics and radon research, measurements of the radiation effects of radon and the derivation of limits, radon balneotherapy and consequences of uranium ore mining are dealt with. (orig.) [de

Application of some advanced technologies in uranium industry

International Nuclear Information System (INIS)

Chen Zhenshi

2004-01-01

This presentation sets forth a brief survey of some current technologies (including exploration, mining, processing, tailings disposal, uranium mine reclamation, health and safety, etc.) in the uranium industry, relates that technology to economic, environmental and social concerns, and attempts to provide a projection of current trends into the future. Advances in technology are very important to the uranium industry because they provide various means to maintain future resource base through the discovery of new deposits; exploitation of lower-grade resources; and application of new technology to the known, but undeveloped resources. The application of advanced technology results in a continuing reduction in production costs; greatly increases in productivity; decreases or eliminates the adverse impacts on environment; as well as increases safety and well-being for employees. Thus, the sustainable development has been obtained in such aspects as resource base, economic exploitation, environmental protection and the ability to meet social obligations. (author)

Preliminary study of the uranium favorability of Malheur County, Oregon

International Nuclear Information System (INIS)

Erikson, E.H.

1977-11-01

A reconnaissance study of middle and upper Tertiary volcaniclastic sedimentary and silicic volcanic rocks in Malheur County, Oregon, indicates that, based upon the data available: (1) it is unlikely that sandstone-type uranium deposits exist in sedimentary rocks of north-central Malheur County; and (2) favorable uranium environments are more likely to exist in and adjacent to uraniferous silicic eruptive centers and plugs. Some rhyolites in the northern part of the county contain marginally anomalous uranium abundances (6 to 8 +- 2 ppM U 3 O 8 ), compared with similar rocks in southeastern Oregon. Available uranium from these rocks, as determined by nitric-acid leaching, approaches 50 to 75 percent of the total chemical U 3 O 8 present. One Pliocene rhyolite vitrophyre sample from Duck Butte in western Malheur County contains 9 +- 2 ppM U 3 O 8 . The uranium contents of these rhyolites approach those found in silicic plugs spatially related to uranium deposits in the Lakeview district, Oregon (Erikson and Curry, 1977). It is possible that undiscovered epithermal and (or) supergene uranium deposits may exist in favorable wall rocks subjacent to uraniferous silicic eruptive centers (Duck Butte), calderas (McDermitt caldera to the south and others identified in western Owyhee County, Idaho), and silicic plugs (as in the Lakeview district). With the exception of one small uranium anomaly found in unconsolidated sands in the Grassy Mountain Formation, the sedimentary rocks observed in the study area did not possess abnormal radioactivity or exhibit evidence of uranium mobility and enrichment. Carbonaceous trash is uncommon in these rocks. Gently dipping sandstone members of the Deer Butte Formation (upper Miocene) and local channel sands in the Grassy Mountain Formation (Pliocene) may have once been the most permeable rocks in the Tertiary section; but, there is no evidence to suggest that they were conduits for uranium-bearing solutions

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

A non-pedological hypothesis for the processes of uranium mineralization in calcrete

International Nuclear Information System (INIS)

Briot, P.; Fuchs, Y.

1984-01-01

The non-pedological hypothesis presented for the origin of the uraniferous calcrete deposits in Western Australia is based on the premise that alluvial and calcareous lacustrine sediments were initially formed during earlier wet periods, evidence for which has been found in the fossil records. These were followed by subsequent epigenetic alteration accompanied by the precipitation of uranium mineralization during drier semi-arid periods. Typical examples of the processes involved were found in the Yeelirrie uranium deposit. During the latter semi-arid period, the limited surface flow which consisted of periodic flash flood conditions probably contributed marginally to the recharge of the groundwater, and consequently, semi-stagnant groundwater conditions evolved, particularly where the hydraulic gradient was extremely small, for example, for the Yeelirrie channel it is approximately 0.001. In addition, ponding of water behind a natural barrier caused the groundwater to evolve along the following geochemical sequence: mild alkalinity, weak oxidizing conditions, and oversaturation in dissolved elements. These hydrological and hydrogeochemical conditions induced the epigenetic alteration of the palustral/lacustrine limestone, bringing about dolomite neogenesis and the precipitation of carnotite. The source of the uranium in the calcretes and the groundwater of the Yeelirrie channel is considered to be the weathered outcrops of the breakaways along its margins. The genetic hypothesis proposed in this paper, although somewhat different from those described previously and elsewhere in this volume, could be applied to the other uranium-bearing calcretes in Mauritania, Namibia, and Somalia

Present and future: heap leaching of uranium ore in China

International Nuclear Information System (INIS)

Li Jianhua

2010-01-01

Based on small and disperse uranium deposits, and low grade ores, heap leaching has been developed as the dominating technique in the uranium production of China. It is indicated that heap leaching technique has such advantages as less capital, low cost, low power consumption and water consumption. At the meanwhile, heap leaching technique presents shortcomings of poor adaptability and low recovery rate. In order to meet the oncoming enormous demand of nuclear power, great effort shall be put on research of new technology, new equipment, new material. (authors)

Unconventional uranium transactions

International Nuclear Information System (INIS)

Anderson, S.C.

1981-01-01

The purpose of this paper is to describe some representative unconventional transactions which have been observed in the uranium market; to explain the circumstances giving rise to these transactions; and to describe the benefits resulting from these transactions. Unconventional transactions are usually quite specialized, since they are tailored to meet the particular needs of specific market participants. Nevertheless, most of these transactions fall into the following basic categories: multi-party (back-to-back; bridge); swap (deconversion; nationality); barter; inventory financing (leasing with repurchase obligation; sale with repurchase option). These transactions are explained and discussed. (U.K.)

Standard test method for analysis of urine for uranium-235 and uranium-238 isotopes by inductively coupled plasma-mass spectrometry

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 This test method covers the determination of the concentration of uranium-235 and uranium-238 in urine using Inductively Coupled Plasma-Mass Spectrometry. This test method can be used to support uranium facility bioassay programs. 1.2 This method detection limits for 235U and 238U are 6 ng/L. To meet the requirements of ANSI N13.30, the minimum detectable activity (MDA) of each radionuclide measured must be at least 0.1 pCi/L (0.0037 Bq/L). The MDA translates to 47 ng/L for 235U and 300 ng/L for 238U. Uranium– 234 cannot be determined at the MDA with this test method because of its low mass concentration level equivalent to 0.1 pCi/L. 1.3 The digestion and anion separation of urine may not be necessary when uranium concentrations of more than 100 ng/L are present. 1.4 Units—The values stated in picoCurie per liter units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard. 1....

Innovations over old plant techniques in Jaduguda Uranium Mill expansion

Energy Technology Data Exchange (ETDEWEB)

Siddique, S; Verma, R P; Beri, K K [Uranium Corporation of India Limited, Jaduguda Mines, Singhbhum (India)

1994-06-01

India`s first Uranium Mines and Mills was commissioned at Jaduguda in 1968. The plant`s flowsheet was developed at BARC after extensive tests, for extraction of uranium as yellow cake from the ore. The designed capacity of the process plant was initially 1000 MT/day of ore treatment supplied from nearby mines. Subsequently, due to growing demand of uranium fuel, opening of Bhatin mines and setting up of three plants for recovery of uranium mineral from copper tailings of Hindustan Copper Ltd. was perceived. The capacity of the Jaduguda Plant was increased to 1400 MT/day in 1987 to meet this requirement. A new mine at Narwapahar is under development which will necessitate augmentation of the capacity of the Jaduguda plant by 700 MT/day. Major changes are contemplated in equipment selection for the expansion besides incorporation of a high degree of automation based on microprocessor technology which are discussed in this paper. (author). 4 refs., 5 figs.

Possible uranium sources of Streltsovsky uranium ore field

International Nuclear Information System (INIS)

Zhang Lisheng

2005-01-01

The uranium deposit of the Late Jurassic Streltsovaky caldera in Transbaikalia of Russia is the largest uranium field associated with volcanics in the world, its uranium reserves are 280 000 t U, and it is the largest uranium resources in Russia. About one third of the caldera stratigraphic pile consists of strongly-altered rhyolites. Uranium resources of the Streltsovsky caldera are much larger than any other volcanic-related uranium districts in the world. Besides, the efficiency of hydrothermal alteration, uranium resources appear to result from the juxtaposition of two major uranium sources; highly fractionated peralkaline rhyolites of Jurassic age in the caldera, and U-rich subalkaline granites of Variscan age in the basement in which the major uranium-bearing accessory minerals were metamict at the time of the hydrothermal ore formation. (authors)

Managing environmental and health impacts of uranium mining

Energy Technology Data Exchange (ETDEWEB)

Vance, R.E.; Cameron, R., E-mail: robert.vance@oecd.org, E-mail: ron.cameron@oecd.org [OECD Nuclear Energy Agency (France)

2014-07-01

As the raw material that fuels nuclear power plants that generate significant amounts of electricity with full life cycle carbon emissions as low as renewable energy sources, uranium is a valuable commodity. Yet uranium mining remains controversial, principally because of environmental and health impacts created when mining was undertaken by governments to meet Cold War strategic requirements. Uranium mining is conducted under significantly different circumstances today. Since the era of military production, societal expectations of environmental protection and the safety of workers and the public have evolved as the outcomes of the early era of mining became apparent, driving changes in regulatory oversight and mining practices. Key aspects of leading practice uranium mining are presented (conventional worker health and safety, worker radiation protection, public health and safety, water quality, tailings and waste rock management) and compared with historic practices to demonstrate the scale of differences. The application of additional aspects of uranium mine life cycle management (public consultation, environmental impact assessment, analysis of socio-economic impacts/benefits, environmental monitoring, financial assurance, product transport, security and safeguards, emergency planning and knowledge transfer), introduced as the industry matured, enhance overall management practices for the long term. Results from several case studies show that improved management of key aspects of uranium mining, combined with the incorporation of new life cycle parameters, have transformed the industry into the most regulated and arguably one of the safest and environmentally responsible types of mining in the world. (author)

Solvothermal synthesis of tetravalent uranium with isophthalate or pyromellitate ligands

Energy Technology Data Exchange (ETDEWEB)

Falaise, Clement; Delille, Jason; Volkringer, Christophe; Loiseau, Thierry [Contribution from Unite de Catalyse et Chimie du Solide (UCCS) - UMR CNRS 8181, Universite de Lille, USTL-ENSCL, Villeneuve d' Ascq (France)

2015-06-15

Three new coordination polymers bearing tetravalent uranium have been isolated with the O-donor ligands such as isophthalate (1,3-bdc) or pyromellitate (btec). The compounds 1 and 3 have been solvothermally synthesized in N,N-dimethylformamide (DMF). The crystal structure of U(1,3-bdc){sub 2}(DMF) (1) is built up from discrete tricapped trigonal-primastic UO{sub 9} units, for which one carbonyl oxygen atom from DMF is bound to uranium. The connection of the UO{sub 9} units with the isophthalate linkers occurs in a chelating and bidentate fashion and gives rise to the formation of a 3D framework, delimiting narrow channels running along the [101] direction. Upon heating, the DMF molecules are removed, generating the second phase U(1,3-bdc){sub 2} (2) compound, closely related to 1. Indeed, the coordination environment of uranium is reduced to eight with a distorted square-antiprismatic geometry. This transition induces the relative shrinkage of the network (ΔV = 23 %). The structure of the compound U(btec)(DMF){sub 2} (3) also exhibits a 3D framework composed of an isolated bicapped square-antiprismatic UO{sub 10} unit, for which two carbonyl oxygen atoms from DMF are bonded to uranium. Pyromellitate ensures the connection of the UO{sub 10} units through the carboxylate arms in a chelating mode. This results in the formation of a network with diamond-shaped channels, developed along the c axis and encapsulating the DMF molecules. In contrast to 1, no stable phase is observed upon removing the DMF species by heating. (Copyright copyright 2015 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Process for continuous production of metallic uranium and uranium alloys

Science.gov (United States)

Hayden, Jr., Howard W.; Horton, James A.; Elliott, Guy R. B.

1995-01-01

A method is described for forming metallic uranium, or a uranium alloy, from uranium oxide in a manner which substantially eliminates the formation of uranium-containing wastes. A source of uranium dioxide is first provided, for example, by reducing uranium trioxide (UO.sub.3), or any other substantially stable uranium oxide, to form the uranium dioxide (UO.sub.2). This uranium dioxide is then chlorinated to form uranium tetrachloride (UCl.sub.4), and the uranium tetrachloride is then reduced to metallic uranium by reacting the uranium chloride with a metal which will form the chloride of the metal. This last step may be carried out in the presence of another metal capable of forming one or more alloys with metallic uranium to thereby lower the melting point of the reduced uranium product. The metal chloride formed during the uranium tetrachloride reduction step may then be reduced in an electrolysis cell to recover and recycle the metal back to the uranium tetrachloride reduction operation and the chlorine gas back to the uranium dioxide chlorination operation.

Process for continuous production of metallic uranium and uranium alloys

Science.gov (United States)

Hayden, H.W. Jr.; Horton, J.A.; Elliott, G.R.B.

1995-06-06

A method is described for forming metallic uranium, or a uranium alloy, from uranium oxide in a manner which substantially eliminates the formation of uranium-containing wastes. A source of uranium dioxide is first provided, for example, by reducing uranium trioxide (UO{sub 3}), or any other substantially stable uranium oxide, to form the uranium dioxide (UO{sub 2}). This uranium dioxide is then chlorinated to form uranium tetrachloride (UCl{sub 4}), and the uranium tetrachloride is then reduced to metallic uranium by reacting the uranium chloride with a metal which will form the chloride of the metal. This last step may be carried out in the presence of another metal capable of forming one or more alloys with metallic uranium to thereby lower the melting point of the reduced uranium product. The metal chloride formed during the uranium tetrachloride reduction step may then be reduced in an electrolysis cell to recover and recycle the metal back to the uranium tetrachloride reduction operation and the chlorine gas back to the uranium dioxide chlorination operation. 4 figs.

Radiometric determination in situ of the face grades in Witwatersrand gold and uranium mines

International Nuclear Information System (INIS)

Smit, C.J.B.

1985-01-01

A prototype collimated radiometric face scanner was tested in the Harmony Gold Mine. The results obtained during the pilot study indicate that in situ radiometric uranium assays are statistically indistinguishable from those obtained conventionally from channel chip samples. In addition, the study demonstrated that reasonably reliable gold estimates can be deduced from the radiometric measurements, by use of the ratio of gold to uranium within a mine. The instrumentation, calibration procedures, and background determination are described briefly

International symposium on uranium production and raw materials for the nuclear fuel cycle - Supply and demand, economics, the environment and energy security. Extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The IAEA periodically organizes nical meetings and international symposia on all areas of the uranium production cycle. This publication contains 160 extended synopses related to the 2005 international symposium on 'Uranium Production and Raw Materials for the Nuclear Fuel Cycle - Supply and Demand, Economics, the Environment and Energy Security'. They cover all areas of natural uranium resources and production cycle including uranium supply and demand; uranium geology and deposit; uranium exploration; uranium mining and milling; waste management; and environment and regulation. Each synopsis was indexed individually.

Factors controlling localization of uranium deposits in the Dakota Sandstone, Gallup and Ambrosia Lake mining districts, McKinley County, New Mexico

Science.gov (United States)

Pierson, Charles Thomas; Green, Morris W.

1977-01-01

Geologic studies were made at all of the uranium mines and prospects in the Dakota Sandstone of Early(?) and Late Cretaceous age in the Gallup mining district, McKinley County, New Mexico. Dakota mines in the adjacent Ambrosia Lake mining district were visited briefly for comparative purposes. Mines in the eastern part of the Gallup district, and in the Ambrosia Lake district, are on the Chaco slope of the southern San Juan Basin in strata which dip gently northward toward the central part of the basin. Mines in the western part of the Gallup district are along the Gallup hogback (Nutria monocline) in strata which dip steeply westward into the Gallup sag. Geologic factors which controlled formation of the uranium deposits in the Dakota Sandstone are: (1) a source of uranium, believed to be uranium deposits of the underlying Morrison Formation of Late Jurassic age; (2) the accessibility to the Dakota of uranium-bearing solutions from the Morrison; (3) the presence in the Dakota of permeable sandstone beds overlain by impermeable carbonaceous shale beds; and (4) the occurrence within the permeable Dakota sandstone beds of carbonaceous reducing material as bedding-plane laminae, or as pockets of carbonaceous trash. Most of the Dakota uranium deposits are found in the lower part of the formation in marginal-marine distributary-channel sandstones which were deposited in the backshore environment. However, the Hogback no. 4 (Hyde) Mine (Gallup district) occurs in sandy paludal shale of the backshore environment, and another deposit, the Silver Spur (Ambrosia Lake district), is found in what is interpreted to be a massive beach or barrier-bar sandstone of the foreshore environment in the upper part of the Dakota. The sedimentary depositional environment most favorable for the accumulation of uranium is that of backshore areas lateral to main distributary channels, where levee, splay, and some distributary-channel sandstones intertongue with gray carbonaceous shales and

Challenges of ICRP 60 for uranium refining and conversion facilities

International Nuclear Information System (INIS)

Takala, J.M.

1998-01-01

Cameco Corporation operates high-grade uranium mines in northern Saskatchewan and uranium refining and conversion facilities in Ontario. The dose limits for these and all other nuclear facilities in Canada are 50 mSv per year and 4 WLM per year, which are applied separately. However, the upcoming incorporation of the recommendations in ICRP 60 into the Canadian regulations will result in several important changes. In addition to a more restrictive dose limit, the new regulations will require that all radiation exposures be combined into a single index of exposure. Meeting the new lower dose limits of 50 mSv per year and 100 mSv per 5 years will not be a major problem at Cameco facilities. However, the incorporation of long-lived radioactive dust exposures into the dose calculation will be a major challenge. This will cause the most difficulty at the uranium refining and conversion facilities where much of the process involves handling a variety of uranium compounds in the form of a dry powder. At the uranium conversion facilities the control of exposure to airborne uranium is achieved through a combination of lung counting, urinalysis, and fixed area monitors. To progress from a system of exposure control to dose estimation to individual workers will require some major changes. (author)

The development and application of quantitative methods for the determination of in-situ radiometric uranium grade on the Witwatersrand gold and uranium mines

International Nuclear Information System (INIS)

Symons, G.

1985-12-01

A detailed investigation of background radiation levels near the reef zone in the uranium section of the Western Areas Mine was conducted using a collimated radiometric face scanner. This study demonstrated that these radiation levels can be high; 25% or more of the counts measured when sampling a reef face may originate from a background source, especially from uranium ore rubble on the footwall close to the reef face. A method using a 20mm frontal shield was devised to obtain an accurate background correction. Three calibration schemes, the Area method, the Gamlog method, and the Deconvolution method were implemented for the production of accurate in-situ radiometric uranium grades. This involved the construction of a step-response calibration pad at Pelindaba together with the establisment of appropriate software and underground radiometric sampling procedures. Radiometric grades generated by these calibration procedures from 60 channel sections were on average 10% below those procured from conventional chip sampling. A correlation between gold and uranium grades was also evident. Crushed rock samples were collected to investigate the thorium problem and are still undergoing analysis at the time of writing. Refinements in the design of the collimated face scanner are also described

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)

The uranium production cycle and the environment. Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-04-01

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{sup 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

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

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.

Supply of enriched uranium for research reactors

International Nuclear Information System (INIS)

Mueller, H.

2004-01-01

Since the RERTR-Meeting in Newport/USA in 1990 recommended in several papers to the research reactor community to agree upon a worldwide unified technical specification for low enriched uranium (LEU) and high enriched uranium (HEU) in order to facilitate supplies of LEU and HEU to fabricators for acceptance and for fabrication of fresh fuel elements. This target for unified and simplified specification has only been partially reached due to different interests of the fabricators because they want to receive the uranium as pure as possible. As a result of various investigations, however, it became clear that both LEU and HEU received from the United States since the late fifties had different qualities which we have to deal with today due to the availability of stocks. We are now one step forward to know more precisely the properties of LEU and HEU we have received in the past. This uranium was never virgin and we have to cope with this situation. Therefore in my present paper I have concentrated on the documentation of analytical work performed on samples of LEU and HEU received in the past. I propose furthermore a frame of unified specifications for so-called virgin LEU and HEU including uranium from a Zero-experiment. In addition I am giving a recommendation for specifications of LEU obtained by blending of reprocessed HEU. Finally I am touching the question of secure supplies of fresh LEU. (author)

Utilization of a hydraulic barrier to control migration of a uranium plume

International Nuclear Information System (INIS)

Brettschneider, D.J.; Simmons, R.A. Jr.; Kappa, J.D.; Stover, J.A.

1995-01-01

A uranium plume emanating from the U.S. Department of Energy's Fernald Environmental Management Project (FEMP) in Fernald, Ohio had migrated off site and the leading edge of the plume had already mixed with an organic and inorganic plume emanating from two industries south of the FEMP. A method was needed to prevent the further southern migration of the plume, minimize any impacts to the geometry, concentrations, distribution or flow patterns of the organic and inorganic plumes emanating from the off-site industries, while meeting the ultimate cleanup goals for the FEMP. This paper discusses the use of a hydraulic barrier created to meet these goals by pumping a five well recovery system and the problems associated with the disposition of over 2 million gallons per day of water with low concentrations of uranium

The uranium geology and tectonic correlation between the African and Latin American continents

International Nuclear Information System (INIS)

Toens, P.D.; Le Roux, J.P.; Van Biljon, W.J.

1980-10-01

Subsequent to a meeting of the International Atomic Agency's Advisory Group on Uranium Geology in Latin America held in Lima, Peru in December 1978, it was decided that a project involving the correlation of uranium geology on either side of the Atlantic was called for. The representatives of the countries concerned were asked to meet in Vienna in July 1980 and present interim reports on progress made in their respective countries on this project. This paper represents an interim report by the South African Working Group. The aspects dealt with cover the matching of the two continents, the nature and distribution of the Gondwana and earlier sequences, as well as the nature and distribution of uraniferous alkaline complexes and granites [af

Laser fluorescence determination of radioactive waste cotton fabric in the exploration of uranium content

International Nuclear Information System (INIS)

Wang Jiangong

2010-01-01

In order to meet the dosage test the operational needs of the laser fluorescence determination of trace radioactive waste cotton fabric uranium research and exploration, to determine the sample ashing time, measured dosage of acidity and digestion and other technical parameters, gives the laser fluorescence determination of radioactive abandoned cotton fabric of trace uranium method. Method of high sensitivity, strong anti-interference, the detection limit of 0.025μg/g(Burning down dregs), relative standard deviation was 3.96%, the mean recovery 93.3%-103% for masks, gloves and other radioactive waste to the determination of trace uranium. (authors)

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)

Supply of enriched uranium for research reactors

Energy Technology Data Exchange (ETDEWEB)

Mueller, H. [NUKEM GmbH, Alzenau (Germany)

1997-08-01

Since the RERTR-meeting In Newport/USA in 1990 the author delivered a series of papers in connection with the fuel cycle for research reactors dealing with its front-end. In these papers the author underlined the need for unified specifications for enriched uranium metal suitable for the production of fuel elements and made proposals with regard to the re-use of in Europe reprocessed highly enriched uranium. With regard to the fuel cycle of research reactors the research reactor community was since 1989 more concentrating on the problems of its back-end since the USA stopped the acceptance of spent research reactor fuel on December 31, 1988. Now, since it is apparent that these back-end problem have been solved by AEA`s ability to reprocess and the preparedness of the USA to again accept physically spent research reactor fuel the author is focusing with this paper again on the front-end of the fuel cycle on the question whether there is at all a safe supply of low and high enriched uranium for research reactors in the future.

Supply of enriched uranium for research reactors

International Nuclear Information System (INIS)

Mueller, H.

1997-01-01

Since the RERTR-meeting In Newport/USA in 1990 the author delivered a series of papers in connection with the fuel cycle for research reactors dealing with its front-end. In these papers the author underlined the need for unified specifications for enriched uranium metal suitable for the production of fuel elements and made proposals with regard to the re-use of in Europe reprocessed highly enriched uranium. With regard to the fuel cycle of research reactors the research reactor community was since 1989 more concentrating on the problems of its back-end since the USA stopped the acceptance of spent research reactor fuel on December 31, 1988. Now, since it is apparent that these back-end problem have been solved by AEA's ability to reprocess and the preparedness of the USA to again accept physically spent research reactor fuel the author is focusing with this paper again on the front-end of the fuel cycle on the question whether there is at all a safe supply of low and high enriched uranium for research reactors in the future

Uranium favorability of late Eocene through Pliocene rocks of the South Texas Coastal Plain

Energy Technology Data Exchange (ETDEWEB)

Quick, J.V.; Thomas, N.G.; Brogdon, L.D.; Jones, C.A.; Martin, T.S.

1977-02-01

The results of a subsurface uranium favorability study of Tertiary rocks (late Eocene through Pliocene) in the Coastal Plain of South Texas are given. In ascending order, these rock units include the Yegua Formation, Jackson Group, Frio Clay, Catahoula Tuff, Oakville Sandstone, and Goliad Sand. The Vicksburg Group, Anahuac Formation, and Fleming Formation were not considered because they have unfavorable lithologies. The Yegua Formation, Jackson Group, Frio Clay, Catahoula Tuff, Oakville Sandstone, and Goliad Sand contain sandstones that may be favorable uranium hosts under certain environmental and structural conditions. All except the Yegua are known to contain ore-grade uranium deposits. Yegua and Jackson sandstones are found in strand plain-barrier bar systems that are aligned parallel to depositional and structural strike. These sands grade into shelf muds on the east, and lagoonal sediments updip toward the west. The lagoonal sediments in the Jackson are interrupted by dip-aligned fluvial systems. In both units, favorable areas are found in the lagoonal sands and in sands on the updip side of the strand-plain system. Favorable areas are also found along the margins of fluvial systems in the Jackson. The Frio and Catahoula consist of extensive alluvial-plain deposits. Favorable areas for uranium deposits are found along the margins of the paleo-channels where favorable structural features and numerous optimum sands are present. The Oakville and Goliad Formations consist of extensive continental deposits of fluvial sandstones. In large areas, these fluvial sandstones are multistoried channel sandstones that form very thick sandstone sequences. Favorable areas are found along the margins of the channel sequences. In the Goliad, favorable areas are also found on the updip margin of strand-plain sandstones where there are several sandstones of optimum thickness.

Uranium favorability of late Eocene through Pliocene rocks of the South Texas Coastal Plain

International Nuclear Information System (INIS)

Quick, J.V.; Thomas, N.G.; Brogdon, L.D.; Jones, C.A.; Martin, T.S.

1977-02-01

The results of a subsurface uranium favorability study of Tertiary rocks (late Eocene through Pliocene) in the Coastal Plain of South Texas are given. In ascending order, these rock units include the Yegua Formation, Jackson Group, Frio Clay, Catahoula Tuff, Oakville Sandstone, and Goliad Sand. The Vicksburg Group, Anahuac Formation, and Fleming Formation were not considered because they have unfavorable lithologies. The Yegua Formation, Jackson Group, Frio Clay, Catahoula Tuff, Oakville Sandstone, and Goliad Sand contain sandstones that may be favorable uranium hosts under certain environmental and structural conditions. All except the Yegua are known to contain ore-grade uranium deposits. Yegua and Jackson sandstones are found in strand plain-barrier bar systems that are aligned parallel to depositional and structural strike. These sands grade into shelf muds on the east, and lagoonal sediments updip toward the west. The lagoonal sediments in the Jackson are interrupted by dip-aligned fluvial systems. In both units, favorable areas are found in the lagoonal sands and in sands on the updip side of the strand-plain system. Favorable areas are also found along the margins of fluvial systems in the Jackson. The Frio and Catahoula consist of extensive alluvial-plain deposits. Favorable areas for uranium deposits are found along the margins of the paleo-channels where favorable structural features and numerous optimum sands are present. The Oakville and Goliad Formations consist of extensive continental deposits of fluvial sandstones. In large areas, these fluvial sandstones are multistoried channel sandstones that form very thick sandstone sequences. Favorable areas are found along the margins of the channel sequences. In the Goliad, favorable areas are also found on the updip margin of strand-plain sandstones where there are several sandstones of optimum thickness

Advances in uranium enrichment processes

International Nuclear Information System (INIS)

Rae, H.K.; Melvin, J.G.; Slater, J.B.

1986-05-01

Advances in gas centrifuges and development of the atomic vapour laser isotope separation process promise substantial reductions in the cost of enriched uranium. The resulting reduction in LWR fuel costs could seriously erode the economic advantage of CANDU, and in combination with LWR design improvements, shortened construction times and increased operational reliability could allow the LWR to overtake CANDU. CANDU's traditional advantages of neutron economy and high reliability may no longer be sufficient - this is the challenge. The responses include: combining neutron economy and dollar economy by optimizing CANDU for slightly enriched uranium fuel; developing cost-reducing improvements in design, manufacture and construction; and reducing the cost of heavy water. Technology is a renewable resource which must be continually applied to a product for it to remain competitive in the decades to come. Such innovation is a prerequisite to Canada increasing her share of the international market for nuclear power stations. The higher burn-up achievable with enriched fuel in CANDU can reduce the fuel cycle costs by 20 to 40 percent for a likely range of costs for yellowcake and separative work. Alternatively, some of the benefits of a higher fissile content can take the form of a cheaper reactor core containing fewer fuel channels and less heavy water, and needing only a single fuelling machine. An opportunity that is linked to this need to introduce an enriched uranium fuel cycle into CANDU is to build an enrichment business in Canada. This could offer greater value added to our uranium exports, security of supply for enriched CANDUs, technological growth in Canada and new employment opportunities. AECL has a study in progress to define this opportunity

Environmental impact of uranium mining and milling

International Nuclear Information System (INIS)

Dory, A.B.

1981-08-01

The Atomic Energy Control Board is now involved from the early planning stages in the development of uranium mine/mill facilities. As a result, new facilities (including tailings management areas) are designed and developed to meet a high standard. The impact of the mines and tailings areas in the Elliot Lake area on ground and surface waters and air quality is discussed in detail

Estimation of ultratrace level of uranium in sea water by laser fluorimeter

International Nuclear Information System (INIS)

Sahoo, S.K.; Tripathi, R.M.; Mohapatra, S.; Patra, A.C.; Lenka, P.; Puranik, V.D.

2010-01-01

Full text: Uranium, a naturally occurring primordial radionuclide, is imperative in the present Indian Nuclear Power Programme. Seawater may be an alternate source of uranium to meet the future demand. The total estimated quantity of uranium in seawater is around four and a half billion tonnes. Estimation of uranium in sea water is cumbersome and tedious because of ultra-trace concentration of uranium with high salt content and other interfering elements of sea water. Mainly chloride interferes in sea water analysis for estimation of nanogram level uranium because the ion at high concentration in sea water depresses uranyl complex fluorescence. At 500 ppm of chloride, the fluorescence response from a given uranium level is reduced by nearly 50%. Dilution method may be used in order to minimize the interference effect but it can't be implemented in this case as sea water contains 19000 ppm chloride but only 2-3 ppb of uranium. Thus, the separation of the interfering elements is necessary to analyze nanogram level of uranium in sea water. In the present study, an attempt has been made to analyze uranium in sea water by laser fluorimeter. Sample was treated with potassium persulphate to remove chloride ion and subsequent measurement was carried out after pH adjustment. The method was used for analysis of uranium content in 23 seawater samples ranged from 0.2 ± 0.1 μg/l to 2.2 ± 0.4 μg/l with a mean value of 1.01 ± 0.11 μg/l

Long term adequacy of uranium resources

International Nuclear Information System (INIS)

Steyn, J.

1990-01-01

This paper examines the adequacy of world economic uranium resources to meet requirements in the very long term, that is until at least 2025 and beyond. It does so by analysing current requirements forecasts, existing and potential production centre supply capability schedules and national resource estimates. It takes into account lead times from resource discovery to production and production rate limitations. The institutional and political issues surrounding the question of adequacy are reviewed. (author)

Treatment of uranium-bearing wastewater by vacuum membrane distillation

International Nuclear Information System (INIS)

Duan Xiaolin; Li Qicheng; Chen Bingbing

2006-01-01

The removal of uranium from wastewater was carried out by vacuum membrane distillation (VMD) using microporous polypropylene membrane. The effects of feed temperature, mass concentration of U, flow rate and vacuum-side pressure on permeation flux and rejection were studied. The optimum experimental conditions are as follows: feed flow rate is 0.5 m/s, feed temperature is 55 degree C, vacuum-side pressure is 2.66 kPa. When the mass concentrations of U in the feed solution range from 1 mg/L to 9 mg/L, the membrane flux is 3.5 kg/(m 2 ·h) and the rejection rate is 99.1% under the optimum conditions. The water separated from uranium solution by vacuum membrane distillation could meet the state-controlled discharge standard 0.05 mg/L. The VMD as a novel technology will play an important role in the treatment of uranium-bearing wastewater. (authors)

Analytical method of uranium (IV) and uranium (VI) in uranium ores and uranium-bearing rocks

International Nuclear Information System (INIS)

Shen Zhuqin; Zheng Yongfeng; Li Qingzhen; Zhong Miaolan; Gu Dingxiang

1995-11-01

The best conditions for keeping the original valences of uranium during the dissolution and separation procedure of geological samples (especially those micro uranium-bearing rock) were studied. With the exist of high concentration protectants, the sample was decomposed with concentration HF at 40 +- 5 degree C. The U(VI) was dissolved completely and formed stable complex UO 2 F 2 , the U(IV) was precipitated rapidly and carried by carrier. Quantitative separation was carried out immediately with suction. The decomposition of sample and separation of solid/liquid phases was completed within two minutes. After separation, the U(IV) and U(VI) were determined quantitatively with laser fluorescence or voltametry respectively according to the uranium content. The limit of detection for this method is 0.7 μg/g, RSD is 10.5%, the determinate range of uranium is 2 x 10 -6 ∼10 -1 g/g. The uranium contents and their valence state ratio were measured for more than one hundred samples of sand stone and granite, the accuracy and precision of these results are satisfactory for uranium geological research. (12 tabs.; 11 refs.)

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)

Precise coulometric titration of uranium in a high-purity uranium metal and in uranium compounds

International Nuclear Information System (INIS)

Tanaka, Tatsuhiko; Yoshimori, Takayoshi

1975-01-01

Uranium in uranyl nitrate, uranium trioxide and a high-purity uranium metal was assayed by the coulometric titration with biamperometric end-point detection. Uranium (VI) was reduced to uranium (IV) by solid bismuth amalgam in 5M sulfuric acid solution. The reduced uranium was reoxidized to uranium (VI) with a large excess of ferric ion at a room temperature, and the ferrous ion produced was titrated with the electrogenerated manganese(III) fluoride. In the analyses of uranium nitrate and uranium trioxide, the results were precise enough when the error from uncertainty in water content in the samples was considered. The standard sample of pure uranium metal (JAERI-U4) was assayed by the proposed method. The sample was cut into small chips of about 0.2g. Oxides on the metal surface were removed by the procedure shown by National Bureau of Standards just before weighing. The mean assay value of eleven determinations corrected for 3ppm of iron was (99.998+-0.012) % (the 95% confidence interval for the mean), with a standard deviation of 0.018%. The proposed coulometric method is simple and permits accurate and precise determination of uranium which is matrix constituent in a sample. (auth.)

31 CFR 540.317 - Uranium feed; natural uranium feed.

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Uranium feed; natural uranium feed... (Continued) OFFICE OF FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY HIGHLY ENRICHED URANIUM (HEU) AGREEMENT ASSETS CONTROL REGULATIONS General Definitions § 540.317 Uranium feed; natural uranium feed. The...

Uranium exploration

International Nuclear Information System (INIS)

De Voto, R.H.

1984-01-01

This paper is a review of the methodology and technology that are currently being used in varying degrees in uranium exploration activities worldwide. Since uranium is ubiquitous and occurs in trace amounts (0.2 to 5 ppm) in virtually all rocks of the crust of the earth, exploration for uranium is essentially the search of geologic environments in which geologic processes have produced unusual concentrations of uranium. Since the level of concentration of uranium of economic interest is dependent on the present and future price of uranium, it is appropriate here to review briefly the economic realities of uranium-fueled power generation. (author)

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

A study on the upgrading by physical means of low grade uranium ore from Phu Wiang District

International Nuclear Information System (INIS)

Wihokratna, W.

1980-01-01

The purpose of this thesis is to upgrade the uranium ore at Phu Wiang district. Because of the fine grains and high degree of dissemination of uranium in ores, resulting practically complete envelopment of the uranium minerals by the gangue minerals, the ore must first undergo digestion in order to reveal the uranium minerals. After digestion, sodium hydroxide of 0.05 normal was added to the ore and the mixture was fed into the agitator provided with baffles and two specially designed propellers. Due to the 'Push - Pull' motion of the propellers a zone of specially high turbulence was created between them. Also in this region higher concentration of uranium is revealed and the high concentrated uranium ore was regularly stripped off for further analysis. It was found that by using mineral of grain size of 100 mesh and 0.0187% of uranium content a concentration up to 0.063% uranium content (an upgrading better than by a factor of three times) was achieved with the above method. The uranium content was analyzed with 3'' x 3'' NaI (Tl) detector and 1024 channels MCA

Influence of uranium hydride oxidation on uranium metal behaviour

International Nuclear Information System (INIS)

Patel, N.; Hambley, D.; Clarke, S.A.; Simpson, K.

2013-01-01

This work addresses concerns that the rapid, exothermic oxidation of active uranium hydride in air could stimulate an exothermic reaction (burning) involving any adjacent uranium metal, so as to increase the potential hazard arising from a hydride reaction. The effect of the thermal reaction of active uranium hydride, especially in contact with uranium metal, does not increase in proportion with hydride mass, particularly when considering large quantities of hydride. Whether uranium metal continues to burn in the long term is a function of the uranium metal and its surroundings. The source of the initial heat input to the uranium, if sufficient to cause ignition, is not important. Sustained burning of uranium requires the rate of heat generation to be sufficient to offset the total rate of heat loss so as to maintain an elevated temperature. For dense uranium, this is very difficult to achieve in naturally occurring circumstances. Areas of the uranium surface can lose heat but not generate heat. Heat can be lost by conduction, through contact with other materials, and by convection and radiation, e.g. from areas where the uranium surface is covered with a layer of oxidised material, such as burned-out hydride or from fuel cladding. These rates of heat loss are highly significant in relation to the rate of heat generation by sustained oxidation of uranium in air. Finite volume modelling has been used to examine the behaviour of a magnesium-clad uranium metal fuel element within a bottle surrounded by other un-bottled fuel elements. In the event that the bottle is breached, suddenly, in air, it can be concluded that the bulk uranium metal oxidation reaction will not reach a self-sustaining level and the mass of uranium oxidised will likely to be small in relation to mass of uranium hydride oxidised. (authors)

Influence of uranium hydride oxidation on uranium metal behaviour

Energy Technology Data Exchange (ETDEWEB)

Patel, N.; Hambley, D. [National Nuclear Laboratory (United Kingdom); Clarke, S.A. [Sellafield Ltd (United Kingdom); Simpson, K.

2013-07-01

This work addresses concerns that the rapid, exothermic oxidation of active uranium hydride in air could stimulate an exothermic reaction (burning) involving any adjacent uranium metal, so as to increase the potential hazard arising from a hydride reaction. The effect of the thermal reaction of active uranium hydride, especially in contact with uranium metal, does not increase in proportion with hydride mass, particularly when considering large quantities of hydride. Whether uranium metal continues to burn in the long term is a function of the uranium metal and its surroundings. The source of the initial heat input to the uranium, if sufficient to cause ignition, is not important. Sustained burning of uranium requires the rate of heat generation to be sufficient to offset the total rate of heat loss so as to maintain an elevated temperature. For dense uranium, this is very difficult to achieve in naturally occurring circumstances. Areas of the uranium surface can lose heat but not generate heat. Heat can be lost by conduction, through contact with other materials, and by convection and radiation, e.g. from areas where the uranium surface is covered with a layer of oxidised material, such as burned-out hydride or from fuel cladding. These rates of heat loss are highly significant in relation to the rate of heat generation by sustained oxidation of uranium in air. Finite volume modelling has been used to examine the behaviour of a magnesium-clad uranium metal fuel element within a bottle surrounded by other un-bottled fuel elements. In the event that the bottle is breached, suddenly, in air, it can be concluded that the bulk uranium metal oxidation reaction will not reach a self-sustaining level and the mass of uranium oxidised will likely to be small in relation to mass of uranium hydride oxidised. (authors)

Global Uranium And Thorium Resources: Are They Adequate To Satisfy Demand Over The Next Half Century?

Science.gov (United States)

Lambert, I. B.

2012-04-01

This presentation will consider the adequacy of global uranium and thorium resources to meet realistic nuclear power demand scenarios over the next half century. It is presented on behalf of, and based on evaluations by, the Uranium Group - a joint initiative of the OECD Nuclear Energy Agency and the International Atomic Energy Agency, of which the author is a Vice Chair. The Uranium Group produces a biennial report on Uranium Resources, Production and Demand based on information from some 40 countries involved in the nuclear fuel cycle, which also briefly reviews thorium resources. Uranium: In 2008, world production of uranium amounted to almost 44,000 tonnes (tU). This supplied approximately three-quarters of world reactor requirements (approx. 59,000 tU), the remainder being met by previously mined uranium (so-called secondary sources). Information on availability of secondary sources - which include uranium from excess inventories, dismantling nuclear warheads, tails and spent fuel reprocessing - is incomplete, but such sources are expected to decrease in market importance after 2013. In 2008, the total world Reasonably Assured plus Inferred Resources of uranium (recoverable at less than 130/kgU) amounted to 5.4 million tonnes. In addition, it is clear that there are vast amounts of uranium recoverable at higher costs in known deposits, plus many as yet undiscovered deposits. The Uranium Group has concluded that the uranium resource base is more than adequate to meet projected high-case requirements for nuclear power for at least half a century. This conclusion does not assume increasing replacement of uranium by fuels from reprocessing current reactor wastes, or by thorium, nor greater reactor efficiencies, which are likely to ameliorate future uranium demand. However, progressively increasing quantities of uranium will need to be mined, against a backdrop of the relatively small number of producing facilities around the world, geopolitical uncertainties and

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.

Production of Fission Product 99Mo using High-Enriched Uranium Plates in Polish Nuclear Research Reactor MARIA: Technology and Neutronic Analysis

Directory of Open Access Journals (Sweden)

Jaroszewicz Janusz

2014-07-01

Full Text Available The main objective of 235U irradiation is to obtain the 99mTc isotope, which is widely used in the domain of medical diagnostics. The decisive factor determining its availability, despite its short lifetime, is a reaction of radioactive decay of 99Mo into 99mTc. One of the possible sources of molybdenum can be achieved in course of the 235U fission reaction. The paper presents activities and the calculation results obtained upon the feasibility study on irradiation of 235U targets for production of 99Mo in the MARIA research reactor. Neutronic calculations and analyses were performed to estimate the fission products activity for uranium plates irradiated in the reactor. Results of dummy targets irradiation as well as irradiation uranium plates have been presented. The new technology obtaining 99Mo is based on irradiation of high-enriched uranium plates in standard reactor fuel channel and calculation of the current fission power generation. Measurements of temperatures and the coolant flow in the molybdenum installation carried out in reactor SAREMA system give online information about the current fission power generated in uranium targets. The corrective factors were taken into account as the heat generation from gamma radiation from neighbouring fuel elements as well as heat exchange between channels and the reactor pool. The factors were determined by calibration measurements conducted with aluminium mock-up of uranium plates. Calculations of fuel channel by means of REBUS code with fine mesh structure and libraries calculated by means of WIMS-ANL code were performed.

Computational fluid mechanics in R and D on uranium enrichment

International Nuclear Information System (INIS)

Soubbaramayer, O.

1988-01-01

Uranium enrichment represents an essential link in the cycle of nuclear fuels for power production. There are many processes of uranium enrichment, but three of them dominate the nuclear history as well in the past (Gaseous diffusion and centrifugation) as in the present (Laser process). The important role played by the Numerical Fluid Mechanics in the three processes is pointed out. The type of problem raised by Gaseous Diffusion is Channel Flow with wall suction, by Centrifugation, flow of a Compressible gas in a strongly rotating cylinder (Stewartson and Ekman layers) and by Laser process, Thermocapillary-buoyancy flow of a molten metal in an evaporation crucible. The methods and results in these problems are reviewed. 18 refs, 11 figs

French uranium mining sites remediation

International Nuclear Information System (INIS)

Roche, M.

2002-01-01

Following a presentation of the COGEMA's general policy for the remediation of uranium mining sites and the regulatory requirements, the current phases of site remediation operations are described. Specific operations for underground mines, open pits, milling facilities and confining the milled residues to meet long term public health concerns are detailed and discussed in relation to the communication strategies to show and explain the actions of COGEMA. A brief review of the current remediation situation at the various French facilities is finally presented. (author)

Shape memory effects in a uranium + 14 at. % niobium alloy

International Nuclear Information System (INIS)

Vandermeer, R.A.; Ogle, J.C.; Snyder, W.B. Jr.

1978-01-01

There is a class of alloys that, on cooling from elevated temperatures, experience a martensitic phase change. Some of these, when stressed in the martensitic state to an apparently plastic strain, recover their predeformed shape simply by heating. This striking shape recovery is known as the ''shape memory effect'' (SME). Up to a certain limiting strain, epsilon/sub L/, 100% shape recovery may be accomplished. This memory phenomenon seems to be attributable to the thermoelastic nature of and deformational modes associated with the phase transformation in the alloy. Thus, shape recovery results when a stress-biased martensite undergoes a heat-activated reversion back to the parent phase from which it originated. There are uranium alloys that demonstrate SME-behavior. Uranium-rich, uranium--niobium alloys were the first to be documented; New experimental observations of SME in a polycrystalline uranium--niobium alloy are presented. This alloy can exhibit a two-way memory under cetain circumstances. Additional indirect evidence is presented suggesting that the characteristics of the accompanying phase transformation in this alloy meet the criteria or ''selection rules'' deemed essential for SME

Uranium exploration status in Bangladesh: Conceptual feasibility studies

International Nuclear Information System (INIS)

Majumder, R.; Khalil, M.; Rashid, M.

2014-01-01

. As Bangladesh is drained by the Padma-Meghna-Jamuna systems, there are numerous sand bars in those river channels. These sand bars are the prospective locations for uranium bearing minerals. In Bangladesh a regional reconnaissance survey was carried out in more than 2000 sq. km areas of greater Chittagong and Chittagong Hill Tracts and Sylhet districts that has resulted in the identification of more than 150 surface radiometric anomalies. Most of the samples collected from anomalous beds contain uranium ranging from 10 - 300 ppm. The highest radiometric counts occurred in Phooltala Reserve Forest within the Harargaj anticline of Moulavi bazar district, which was about 6000 cps (60 times the background counts). Chemical analysis of this sample has indicated the presence of 1020 ppm total uranium and two uranium bearing minerals namely uranothorite and thorianite have been discovered in the rock samples. Besides, anomalous reading of 25 times higher than the background was observed in the crystalline basement rocks at Mitapukur in Rangpur district. Moreover, in recent studies conducted by the Geological Survey of Bangladesh (GSB), higher radiometric counts have been observed in sand bar deposits of the Brahmaputra River. (author)

History of Uranium-233(233U)Processing at the Rocky Flats Plant. In support of the RFETS Acceptable Knowledge Program

International Nuclear Information System (INIS)

Moment, R.L.; Gibbs, F.E.; Freiboth, C.J.

1999-01-01

This report documents the processing of Uranium-233 at the Rocky Flats Plant (Rocky Flats Environmental Technology Site). The information may be used to meet Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC)and for determining potential Uranium-233 content in applicable residue waste streams

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

Czechoslovak uranium

International Nuclear Information System (INIS)

Pluskal, O.

1992-01-01

Data and knowledge related to the prospecting, mining, processing and export of uranium ores in Czechoslovakia are presented. In the years between 1945 and January 1, 1991, 98,461.1 t of uranium were extracted. In the period 1965-1990 the uranium industry was subsidized from the state budget to a total of 38.5 billion CSK. The subsidies were put into extraction, investments and geologic prospecting; the latter was at first, ie. till 1960 financed by the former USSR, later on the two parties shared costs on a 1:1 basis. Since 1981 the prospecting has been entirely financed from the Czechoslovak state budget. On Czechoslovak territory uranium has been extracted from deposits which may be classified as vein-type deposits, deposits in uranium-bearing sandstones and deposits connected with weathering processes. The future of mining, however, is almost exclusively being connected with deposits in uranium-bearing sandstones. A brief description and characteristic is given of all uranium deposits on Czechoslovak territory, and the organization of uranium mining in Czechoslovakia is described as is the approach used in the world to evaluate uranium deposits; uranium prices and actual resources are also given. (Z.S.) 3 figs

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.

Interim status of the Texas uranium survey experiment

International Nuclear Information System (INIS)

Jupiter, C.; Wollenberg, H.

1974-01-01

The objective of the Texas uranium survey experiment is to evaluate an improved method for prospecting for uranium by determining correlations among (a) geologic analysis, (b) soil sample radiochemical analysis, (c) aerial radiometric data, (d) aerial infrared scans, and (e) aerophotographic data. Although aerial radiometric measurements have been used previously in mineral prospecting, the development of useful correlative techniques based on analysis of data from large terrestrial areas employing the five parameters (a through e, above) remains to be evaluated, and could be of significant value to the need for establishing uranium resource pools to meet the nation's energy crisis. The Texas uranium survey field experiment began on June 13, 1973, employing a Martin-404 aircraft to fly gamma-ray recording equipment at a 500-ft altitude over two areas in southeast Texas. The areas surveyed are referred to as the Dubose area (approximately 120 sq. miles) and the Clay West area (approximately 24 sq. miles). This document briefly summarizes the work which has been done, describes the kind and quality of calibrations and data analysis carried out thus far and outlines recommended additional work which would bring the experiment to some degree of completion, providing a basis for evaluating the techniques

Analysis of uranium supply to 2050

International Nuclear Information System (INIS)

Underhill, D.H.

2000-01-01

Nuclear power is expected to be an important part of the world-wide energy mix at least through the next 50 years and by most projections well beyond. That is, of course, provided an adequate supply of uranium is available to sustain the nominal growth rate for nuclear power of 1 to 3% per year that is projected by many analysts. The importance that a reliable supply will have on the future of nuclear power led the IAEA to undertake a study of uranium supply-demand relationships through 2050. The ultimate goal of the study is to evaluate the adequacy of supply to meet demand, and to characterize the level of confidence that can be placed in the projected supply. This report describes key conclusions of the study. A detailed report describing the results of the study is available as an IAEA Special Publication

Uranium ores

International Nuclear Information System (INIS)

Poty, B.; Roux, J.

1998-01-01

The processing of uranium ores for uranium extraction and concentration is not much different than the processing of other metallic ores. However, thanks to its radioactive property, the prospecting of uranium ores can be performed using geophysical methods. Surface and sub-surface detection methods are a combination of radioactive measurement methods (radium, radon etc..) and classical mining and petroleum prospecting methods. Worldwide uranium prospecting has been more or less active during the last 50 years, but the rise of raw material and energy prices between 1970 and 1980 has incited several countries to develop their nuclear industry in order to diversify their resources and improve their energy independence. The result is a considerable increase of nuclear fuels demand between 1980 and 1990. This paper describes successively: the uranium prospecting methods (direct, indirect and methodology), the uranium deposits (economical definition, uranium ores, and deposits), the exploitation of uranium ores (use of radioactivity, radioprotection, effluents), the worldwide uranium resources (definition of the different categories and present day state of worldwide resources). (J.S.)

Case history of natural analogue research on sandstone type uranium occurrences, Japan

International Nuclear Information System (INIS)

Sakamaki, Y.; Kanai, Y.

1991-01-01

Previous fundamental studies on the ore genesis of uranium occurrences chiefly in Cenozoic sandstone formations in Japan, have been re-examined as the case history on natural analogue of radionuclides in high-level radioactive wastes (HLRW). Two principal mode of occurrences have been distinguished among Cenozoic uranium localities in Japan. In the Setouchi (Inland Sea) subregion, hot-spots are found in lacustrine to shallow sea facies of calm environment, corresponding to the first stage of formation of tectonic basins. As observed in Ningyo-toge and Tono area, stratabound ore bodies are generally arranged into paleo-channels. Another type of sporadic uranium indications are found within collapse basins in the 'Green-tuff' subregion, where intense volcanisms and block movements had been taken places throughout Middle miocene age. Well-developed fractures were to be favorable paths for uraniferous groundwater, as well as the suitable site for deposition of uranium. In both cases, the source material of uranium is granitic basement. Under oxidizing environment, uranium anomalies have been occasionally detected in surface- or fracture waters which passing through decomposed granite. In contrast to the behavior of uranium, one of the adequate analogues for mobile nuclides, thorium and REE are relatively immobile even under the same geologic and geochemical circumstances. In ore horizon, where reducing condition has still been kept, geochronological age of tetravalent uranium mineral is in concordance with the age of the host rock. Analysis of structural control shows that the principal factors for uranium concentration are the layout of redox front related to paleo-water tables. 234U/238U disequilibrium method has been proved to be the powerful tool for detecting mobility of uranium in the host rock throughout diagenesis and weathering process. The result of field and laboratory works on this is reported as an example. (author)

Current practices and options for confinement of uranium mill tailings

International Nuclear Information System (INIS)

1981-01-01

At the United Nations Conference on the Human Environment, which took place in Stockholm from 4 to 6 June 1972, national governments were asked to explore, with the International Atomic Energy Agency and other appropriate international organizations, international co-operation on radioactive waste matters including those of mining and tailings disposal. Since that time the IAEA has been active in the field of uranium and thorium mill tailings management. As part of this activity, the present report describes current practices and options for confinement of uranium mill tailings. It is addressed to technical and administrative personnel who are involved in planning and implementing national and industrial programmes on the management of such tailings. In 1974 and 1975 the IAEA convened meetings of experts to review matters of interest and importance in the management of uranium and thorium mine and mill tailings. These activities led to the publication in 1976 of Management of Wastes from the Mining and Milling of Uranium and Thorium Ores, a Code of Practice and Guide to the Code, IAEA Safety Series No. 44. As a continuation of this activity, the IAEA is here dealing more specifically with the design and siting considerations for the management of uranium mill tailings

Uranium extraction from Uro area phosphate ore, Nuba mountains, Sudan

International Nuclear Information System (INIS)

Mohammed, A. A.; Eltayeb, M. A. H.

2003-01-01

product has proved its nuclear purity and meets the standard commercial specification. According to the obtained results, it can be concluded that nuclear grade uranium trioxide can be successfully produced with an overall uranium recovery percentage of 93% from Uro phosphate ore. A proposed flowsheet was designed for this purpose. (Author)

Best practice in situ recovery uranium mining in Australia

International Nuclear Information System (INIS)

Lambert, I.B.; McKay, A.D.; Carson, L.J.

2010-01-01

The Australian Government policy is to ensure that uranium mining, milling and rehabilitation is based on world best practice standards. A best practice guide for in situ recovery (ISR) uranium mining has been developed to communicate the Australian Government's expectations with a view to achieving greater certainty that ISR mining projects meet Australian Government policy and consistency in the assessment of ISR mine proposals within multiple government regulatory processes. The guide focuses on the main perceived risks; impacts on groundwaters, disposal of mining residues, and radiation protection. World best practice does not amount to a universal template for ISR mining because the characteristics of individual ore bodies determine the best practice. (author)

Assay of uranium in crude diuranate cakes and MgF2 slag produced at the natural uranium conversion plants by γ-ray spectrometry

International Nuclear Information System (INIS)

Kalsi, P.C.; Iyer, R.H.

1993-01-01

A transmission-corrected γ-ray counting method has been employed for the assay of uranium in crude Na 2 U 2 O 7 cakes produced at the Uranium Conversion Facilities. A 3''*3'' NaI(Tl) detector was used in conjunction with a 400-channel analyzer. The observed count rate of the 1 MeV γ-ray emitted by the 238 U in the sample was corrected for sample self-attenuation, measured with a 65 Zn (γ-energy ≅ 1115 keV) transmission source. A calibration factor determined by measuring a standard of known amount of radioactive material in the same form and geometry as the unknown sample was used to convert the transmission corrected count rate to the amount of uranium in the weighed sample. Another γ-spectrometric method is described for the assay of the U-content in the MgF 2 slag produced during the magnesiothermic reduction of UF 4 to U-metal ingots at the natural U-conversion plant. (author) 8 refs.; 3 figs.; 1 tab

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

Fractal characters and hurst exponent of radon exhalation rate from uranium Tailings

International Nuclear Information System (INIS)

Hu Hanqiao; Tan Kaixuan; Li Chunguang; Lv Junwen; Liu Dong

2010-01-01

The uranium tailings radon exhalation is an important environmental problem. The change of the radon exhalation rate of uranium tailings with the time through laboratory experiments is measured, and the results show that the radon exhalation rate of the tailings change obviously with time in non-periodic oscillations. Applying fractal analysis to the radon exhalation rate time-series data by R/S method, the Hurst exponent of the entire time series data is 0.83, the fractal dimension is 1.17. Mobile Hurst exponent is between 0.5 and 0.8 in most cases. The Hurst exponent of the experiments in the later part are below 0.5. The exhalation rate of uranium tailings radon does not meet the long-term trend of random walk theory, the radon exhalation rate has long-term memory, but the short-term memory is not distinct. The radon exhalation from uranium tailings is a deterministic chaotic dynamics. (authors)

Pengaruh Kandungan Uranium Dalam Umpan Terhadap Efisiensi Pengendapan Uranium

OpenAIRE

Torowati

2010-01-01

PENGARUH KANDUNGAN URANIUM DALAM UMPAN TERHADAP EFISIENSI PENGENDAPAN URANIUM. Setiap aktivitas analisis di Laboratorium Kendali Kualitas, Bidang Bahan Bakar Nuklir selalu dihasilkan limbah radioaktif cair. Limbah radioaktif cair di laboratorium masih mengandung uranium yang cukup besar ± 0,600 g U/l dengan keasamaan yang cukup besar pula. Karena uranium mempunyai nilai ekonomis yang cukup tinggi maka perlu USAha untuk mengambil kembali uranium tersebut. Pada kegiatan ini telah dilak...

Nitrogen content determinations in different stages of thermal treatment involved in conversion of ammonium diuranate to uranium metal

International Nuclear Information System (INIS)

Shrivastava, K.C.; Shelke, G.P.

2017-01-01

Determination of nitrogen content in the uranium metal and uranium oxide based reactor fuels is important to meet the requirement of specifications given by fuel designer. Therefore, a systematic study was carried out to determine the variations in nitrogen content during the conversion of ammonium diuranate (ADU) to uranium oxides (UO 3 and UO 2 ), and finally to uranium metal by inert gas fusion-thermal conductivity detection (IGF-TCD) technique. To understand the measured nitrogen content variations, the thermal decomposition study of ADU was carried out using thermogravimetry (TG)/differential thermogravimetry (DTG) and differential thermal analysis (DTA) in the temperature range of 25-1073 K. Powder X-ray diffraction (XRD) technique was used to confirm the formation of uranium oxide precursors at different temperature. (author)

Uranium enrichment conference on modified contract option, Oak Ridge, Tennessee, July 22, 1975

International Nuclear Information System (INIS)

1975-01-01

The questions and answers presented in this document originated at an industry-wide meeting sponsored by the Energy Research and Development Administration held in Oak Ridge, Tennessee, on July 22, 1975, to discuss features and provisions of an ERDA plan to adjust contracts held by firms receiving uranium enriching services from ERDA. On June 19, 1975, ERDA announced terms of an expanded contract modification plan. The modified contract option broadened a previous plan proposed on January 15, 1975, by the former Atomic Energy Commission. The meeting in Oak Ridge on July 22, 1975, was designed to provide additional information on the expanded contract option and to offer ample opportunity for questions and answers prior to August 18, 1975, by which time enriching services customers who chose the one-time option had to so notify ERDA. The meeting included presentations by officials of ERDA Headquarters and ERDA's Oak Ridge Operations on the features of the contract adjustment offer, including provisions for contract termination in whole, separative work schedule adjustments, and uranium feed delivery schedule relaxation. (auth)

An ICP-AES method for the determination of trace metals in uranium by solvent extraction using KSM-17

International Nuclear Information System (INIS)

Jacob, Mary; Radhakrishnan, K.; Dhami, P.S.; Kulkarni, V.T.; Joshi, M.V.; Patwardhan, A.B.; Ramanujam, A.; Mathur, J.N.

1994-01-01

This paper describes the studies carried out for the determination of trace metallic impurities in uranium solutions. Uranium matrix is separated from the impurity elements by its selective extraction using 2-ethylhexyl hydrogen 2-ethylhexyl phosphonate (KSM-17, equivalent to PC88A). The aqueous phase is analysed for trace impurities by inductively coupled argon plasma atomic emission spectrometry. The studies also include recovery of impurities at various acidities and spectral interferences of uranium over the analyte element channels. Based on the above studies, a method has been standardised for the analysis of nineteen elements in uranium solutions. The relative standard deviation of the method for various elements is in the range of +- 1-5%. (author). 7 refs., 8 tabs., 1 fig

Glances on uranium. From uranium in the earth to electric power

International Nuclear Information System (INIS)

Valsardieu, C.

1995-01-01

This book is a technical, scientific and historical analysis of the nuclear fuel cycle from the origin of uranium in the earth and the exploitation of uranium ores to the ultimate storage of radioactive wastes. It comprises 6 chapters dealing with: 1) the different steps of uranium history (discovery, history of uranium chemistry, the radium era, the physicists and the structure of matter, the military uses, the nuclear power, the uranium industry and economics), 2) the uranium in nature (nuclear structure, physical-chemical properties, radioactivity, ores, resources, cycle, deposits), 3) the sidelights on uranium history (mining, prospecting, experience, ore processing, resources, reserves, costs), 4) the uranium in the fuel cycle, energy source and industrial product (fuel cycle, fission, refining, enrichment, fuel processing and reprocessing, nuclear reactors, wastes management), 5) the other energies in competition and the uranium market (other uranium uses, fossil fuels and renewable energies, uranium market), and 6) the future of uranium (forecasting, ecology, economics). (J.S.)

Geochemical and sedimentologic problems of uranium deposits of Texas Gulf Coastal Plain: discussion

International Nuclear Information System (INIS)

Craig, R.M.

1980-01-01

Huang (1978) stated that the mobility and accumulation of uranium in host rocks are controlled by several factors, including the hydrologic factor. Some of his statements are misleading as indicated by study of ancient stream channels in Wyoming which has led to increased discoveries of uranium deposits. Because it is believed that the transportation mechanism for uranium in paleoaquifer host rocks is groundwater, the flow of the uranium-bearing solution is a function of the infiltration or recharge into the aquifer, not necessarily of the rainfall. Huang stated that the time of accumulation depends upon the dip of the host rock. The flow of a groundwater system is largely independent of the dip of the beds as stated by Daray's (1856) law: Q = KA delta h/delta l h. Dividing this equation by the area, A, will result in the flux or average velocity of a particle. Data was included for the Wind River Formation in the Gas Hills Uranium district of Wyoming. some data differs from Huang. According the Lohman equation, groundwater velocity would be three times greater in the Texas example than in the northern Wyoming area, presuming the same porosity, groundwater gradient, and flow-path length

Developments in natural uranium - graphite reactors; Developpement des reacteurs a graphite et uranium naturel

Energy Technology Data Exchange (ETDEWEB)

Bourgeois, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Saitcevsky, B [Electricite de France (EDF), 75 - Paris (France)

1964-07-01

The French natural uranium-graphite power-reactor programme has been developing - from EDF 1 to EDF 4 - in the direction of an increase of the unit power of the installations, of the specific and volume powers, and of an improvement in the operational security conditions. The high power of EDF 4 (500 MWe) and the integration of the primary circuit into the reactor vessel, which is itself made of pre-stressed concrete, make it possible to make the most of the annular fuel elements already in use in EDF 1, and to arrive thus at a very satisfactory solution. The use of an internally cooled fuel element (an annular element) has led to a further step forward: it now becomes possible to increase the pressure of the cooling gas without danger of causing creep in the uranium tube. The use of a pre-stressed concrete vessel makes this pressure increase possible, and the integration of the primary circuit avoids the risk of a rapid depressurization which would be in this case a major danger. This report deals with the main problems presented by this new type of nuclear power station, and gives the main lines of research and studies now being carried out in France. - Neutronic and thermal research has made it possible to consider using large size fuel elements (internal diameter = 77 mm, external diameter 95 mm) while still using natural uranium. - The problems connected with the production of these elements and with their in pile behaviour are the subject of a large programme, both out of pile and in power reactors (EDF 2) and test reactors (Pegase). - The increase in the size of the element leads to a large lattice pitch (35 to 40 cm). This makes it possible to consider having one charging aperture per channel or for a small number of channels, whether the charge machine be inside or outside the pressure vessel. In conclusion are given the main characteristics of a project for a 500 MWe power station using such a fuel element. In particular this project is compared to EDF 4

The Canadian Nuclear Safety Commission Compliance Program for Uranium Mines and Mills

Energy Technology Data Exchange (ETDEWEB)

Schryer, D., E-mail: denis.schryer@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Saskatoon, Saskatchewan (Canada)

2014-05-15

The Canadian Nuclear Safety Commission (CNSC) is the principal nuclear regulator in Canada. The CNSC is empowered through the Nuclear Safety and Control Act (NSCA) and its associated regulations, to regulate the entire nuclear cycle which includes: uranium mining and milling, uranium refining and processing, fuel fabrication, power generation and nuclear waste management. A CNSC uranium mine licence is required by a proponent to site, prepare, construct, operate, decommission and abandon this nuclear facility. The CNSC licence is the legal instrument that authorizes the regulated activities and incorporates conditions and regulatory controls. Following a favourable Commission Tribunal decision to issue a licence to authorize the licensed activities, CNSC develops and executes a compliance plan of the licensee’s programs and procedures. The CNSC compliance plan is risk-informed and applies its resources to the identified higher risk areas. The compliance program is designed to encourage compliance by integrating three components: promotion, verification and enforcement and articulates the CNSC expectations to attain and maintain compliance with its regulatory requirements. The licensee performance is assessed through compliance activities and reported to the Commission to inform the licensing process during licence renewal. The application of the ongoing compliance assessment and risk management model ensures that deviations from impact predictions are addressed in a timely manner. The Uranium Mines and Mills Division of the CNSC are preparing to meet the challenges of the planned expansion of their Canadian uranium mining industry. The presentation will discuss these challenges and the measures required to address them. The Uranium Mines and Mills Division (UMMD) have adopted a structured compliance framework which includes formal procedures to conduct site inspections. New UMMD staff are trained to apply the regulations to licensed sites and to manage non

Uranium prospecting; La prospection de l'uranium

Energy Technology Data Exchange (ETDEWEB)

Roubault, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

This report is an instruction book for uranium prospecting. It appeals to private prospecting. As prospecting is now a scientific and technical research, it cannot be done without preliminary studies. First of all, general prospecting methods are given with a recall of fundamental geologic data and some general principles which are common with all type of prospecting. The peculiarities of uranium prospecting are also presented and in particular the radioactivity property of uranium as well as the special aspect of uranium ores and the aspect of neighbouring ores. In a third part, a description of the different uranium ores is given and separated in two different categories: primary and secondary ores, according to the place of transformation, deep or near the crust surface respectively. In the first category, the primary ores include pitchblende, thorianite and rare uranium oxides as euxenite and fergusonite for example. In the second category, the secondary ores contain autunite and chalcolite for example. An exhaustive presentation of the geiger-Mueller counter is given with the presentation of its different components, its functioning and utilization and its maintenance. The radioactivity interpretation method is showed as well as the elaboration of a topographic map of the measured radioactivity. A brief presentation of other detection methods than geiger-Mueller counters is given: the measurement of fluorescence and a chemical test using the fluorescence properties of uranium salts. Finally, the main characteristics of uranium deposits are discussed. (M.P.)

Opening address at the international meeting on reduced enrichment for research and test reactors

International Nuclear Information System (INIS)

Kazuo Sato

1984-01-01

The purpose of the Meeting was to exchange and discuss the most up-to-date information on the progress of variuos programs related to research and test reactor core conversion from high enriched uranium to lower enriched uranium. More detailed status of the RERTR program in Japan, as the host country is covered in this presentation

Uranium

International Nuclear Information System (INIS)

Stewart, E.D.J.

1974-01-01

A discussion is given of uranium as an energy source in The Australian economy. Figures and predictions are presented on the world supply-demand position and also figures are given on the added value that can be achieved by the processing of uranium. Conclusions are drawn about Australia's future policy with regard to uranium (R.L.)

Uranium, depleted uranium, biological effects

International Nuclear Information System (INIS)

2001-01-01

Physicists, chemists and biologists at the CEA are developing scientific programs on the properties and uses of ionizing radiation. Since the CEA was created in 1945, a great deal of research has been carried out on the properties of natural, enriched and depleted uranium in cooperation with university laboratories and CNRS. There is a great deal of available data about uranium; thousands of analyses have been published in international reviews over more than 40 years. This presentation on uranium is a very brief summary of all these studies. (author)

Standard specification for uranium oxides with a 235U content of less than 5 % for dissolution prior to conversion to nuclear-grade uranium dioxide

CERN Document Server

American Society for Testing and Materials. Philadelphia

2005-01-01

1.1 This specification covers uranium oxides, including processed byproducts or scrap material (powder, pellets, or pieces), that are intended for dissolution into uranyl nitrate solution meeting the requirements of Specification C788 prior to conversion into nuclear grade UO2 powder with a 235U content of less than 5 %. This specification defines the impurity and uranium isotope limits for such urania powders that are to be dissolved prior to processing to nuclear grade UO2 as defined in Specification C753. 1.2 This specification provides the nuclear industry with a general standard for such uranium oxide powders. It recognizes the diversity of conversion processes and the processes to which such powders are subsequently to be subjected (for instance, by solvent extraction). It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between the buyer and seller. 1.3 The scope of this specification does not comprehensively cover all provisions for prevent...

Recycling and disposal of FUSRAP materials from the Ashland 2 site at a licensed uranium mill

International Nuclear Information System (INIS)

Howard, B.; Conboy, D.; Rehmann, M.; Roberts, H.

1999-01-01

During World War II the Manhattan Engineering District (MED) used facilities near Buffalo, N.Y. to extract natural uranium from ores. Some of the byproduct material left from the ores (MED byproduct), containing low levels of uranium, thorium, and radium, was deposited on a disposal site known as Ashland 2, located in Tonawanda, NY. On behalf of the United States Army Corps of Engineers (USACE, or the Corps), ICF Kaiser Engineers (ICFKE) was tasked to provide the best value clean-up results that meet all of the criteria established in the Record of Decision for the site. International Uranium (USA) Corporation (IUC), the operator of the White Mesa Uranium Mill, a Nuclear Regulatory Commission (NRC)-licensed mill near Blanding, Utah, was selected to perform uranium extraction on the excavated materials, therefore giving the best value as it provided beneficial use of the material consistent with the Resource Conservation and Recovery Act (RCRA) intent to encourage recycling and recovery, while also providing the most cost-effective means of disposal. Challenges overcome to complete this project included (1) identifying the best-value location to accept the material; (2) meeting regulatory requirements with IUC obtaining an NRC license amendment to accept and process the material as an alternate feed; (3) excavating and preparing the material for shipment, then shipping the material to the Mill for uranium recovery; and (4) processing the material, followed by disposal of tailings from the process in the Mill's licensed uranium tailings facility. Excavation from Ashland 2 and processing of the Ashland 2 material at the White Mesa Mill resulted in a cleaner environment at Tonawanda, a cost avoidance of up to $16 million, beneficial recovery of source material, and environmentally protective disposal of byproduct material. (author)

Cost of implementing AECB interim criteria for the closeout of uranium tailings sites

International Nuclear Information System (INIS)

1981-04-01

The main purpose of this study was to arrive at a gross approximation of the costs to the Canadian uranium mining industry of meeting the proposed closeout criteria established by the Atomic Energy Control Board for tailings deposits. Two options have been investigated: on-land disposal and underlake disposal. Given the budget allocated to the study, the estimates must be understood as approximations. Overall cost figures for the Canadian uranium mining industry are linear extensions from a hypothetical base case. The results of a conference held in Ottawa on February 25 and 26 to discuss the proposed AECB interim criteria for the closeout of uranium tailings sites are also included. Representatives from mining firms, provincial regulatory authorities, universities and the Atomic Energy Control board attended the conference

Solubility measurement of uranium in uranium-contaminated soils

International Nuclear Information System (INIS)

Lee, S.Y.; Elless, M.; Hoffman, F.

1993-08-01

A short-term equilibration study involving two uranium-contaminated soils at the Fernald site was conducted as part of the In Situ Remediation Integrated Program. The goal of this study is to predict the behavior of uranium during on-site remediation of these soils. Geochemical modeling was performed on the aqueous species dissolved from these soils following the equilibration study to predict the on-site uranium leaching and transport processes. The soluble levels of total uranium, calcium, magnesium, and carbonate increased continually for the first four weeks. After the first four weeks, these components either reached a steady-state equilibrium or continued linearity throughout the study. Aluminum, potassium, and iron, reached a steady-state concentration within three days. Silica levels approximated the predicted solubility of quartz throughout the study. A much higher level of dissolved uranium was observed in the soil contaminated from spillage of uranium-laden solvents and process effluents than in the soil contaminated from settling of airborne uranium particles ejected from the nearby incinerator. The high levels observed for soluble calcium, magnesium, and bicarbonate are probably the result of magnesium and/or calcium carbonate minerals dissolving in these soils. Geochemical modeling confirms that the uranyl-carbonate complexes are the most stable and dominant in these solutions. The use of carbonate minerals on these soils for erosion control and road construction activities contributes to the leaching of uranium from contaminated soil particles. Dissolved carbonates promote uranium solubility, forming highly mobile anionic species. Mobile uranium species are contaminating the groundwater underlying these soils. The development of a site-specific remediation technology is urgently needed for the FEMP site

Characterization of the uranium--2 weight percent molybdenum alloy

International Nuclear Information System (INIS)

Hemperly, V.C.

1976-01-01

The uranium-2 wt percent molybdenum alloy was prepared, processed, and age hardened to meet a minimum 930-MPa yield strength (0.2 percent) with a minimum of 10 percent elongation. These mechanical properties were obtained with a carbon level up to 300 ppM in the alloy. The tensile-test ductility is lowered by the humidity of the laboratory atmosphere

Phosphoryl functionalized mesoporous silica for uranium adsorption

International Nuclear Information System (INIS)

Xue, Guo; Yurun, Feng; Li, Ma; Dezhi, Gao; Jie, Jing; Jincheng, Yu; Haibin, Sun; Hongyu, Gong; Yujun, Zhang

2017-01-01

Highlights: • Phosphoryl functionalized mesoporous silica (TBP-SBA-15) is synthesized. • The amino and phosphoryl groups are successfully grafted on SBA-15. • TBP-SBA-15 has high and rapid uranium adsorption capacity in broad pH range. • The U(VI) adsorption of TBP-SBA-15 is spontaneous and belongs to chemical adsorption. - Abstract: Phosphoryl functionalized mesoporous silica (TBP-SBA-15) was synthesized by modified mesoporous silica with γ-amino propyl triethoxy silane and tributyl phosphate. The obtained samples were characterized by scanning electron microscopy (SEM), transmission electron microscopy (TEM), small angle X-ray diffraction (SAXRD), thermo-gravimetric/differential thermalanalyzer (TG/DTA), N_2 adsorption–desorption (BET) and Fourier transform infrared spectroscopy (FT-IR) techniques. Results showed that TBP-SBA-15 had large surface areas with ordered channel structure. Moreover, the effects of adsorption time, sorbent dose, solution pH, initial uranium concentration and temperature on the uranium adsorption behaviors were investigated. TBP-SBA-15 showed a high uranium adsorption capacity in a broad range of pH values. The U(VI) adsorption rate of TBP-SBA-15 was fast and nearly achieved completion in 10 min with the sorbent dose of 1 g/L. The U(VI) adsorption of TBP-SBA-15 followed the pseudo-second-order kinetic model and Freundlich isotherm model, indicating that the process was belonged to chemical adsorption. Furthermore, the thermodynamic parameters (ΔG"0, ΔH"0 and ΔS"0) confirmed that the adsorption process was endothermic and spontaneous.

Phosphoryl functionalized mesoporous silica for uranium adsorption

Energy Technology Data Exchange (ETDEWEB)

Xue, Guo; Yurun, Feng; Li, Ma; Dezhi, Gao; Jie, Jing; Jincheng, Yu; Haibin, Sun [Key Laboratory for Liquid-Solid Structural Evolution & Processing of Materials of Ministry of Education, Shandong University, Jinan 250061 (China); Key Laboratory of Special Functional Aggregated Materials, Ministry of Education, Shandong University, Jinan 250061 (China); Hongyu, Gong, E-mail: gong_hongyu@163.com [Key Laboratory for Liquid-Solid Structural Evolution & Processing of Materials of Ministry of Education, Shandong University, Jinan 250061 (China); Key Laboratory of Special Functional Aggregated Materials, Ministry of Education, Shandong University, Jinan 250061 (China); Yujun, Zhang, E-mail: yujunzhangcn@163.com [Key Laboratory for Liquid-Solid Structural Evolution & Processing of Materials of Ministry of Education, Shandong University, Jinan 250061 (China); Key Laboratory of Special Functional Aggregated Materials, Ministry of Education, Shandong University, Jinan 250061 (China)

2017-04-30

Highlights: • Phosphoryl functionalized mesoporous silica (TBP-SBA-15) is synthesized. • The amino and phosphoryl groups are successfully grafted on SBA-15. • TBP-SBA-15 has high and rapid uranium adsorption capacity in broad pH range. • The U(VI) adsorption of TBP-SBA-15 is spontaneous and belongs to chemical adsorption. - Abstract: Phosphoryl functionalized mesoporous silica (TBP-SBA-15) was synthesized by modified mesoporous silica with γ-amino propyl triethoxy silane and tributyl phosphate. The obtained samples were characterized by scanning electron microscopy (SEM), transmission electron microscopy (TEM), small angle X-ray diffraction (SAXRD), thermo-gravimetric/differential thermalanalyzer (TG/DTA), N{sub 2} adsorption–desorption (BET) and Fourier transform infrared spectroscopy (FT-IR) techniques. Results showed that TBP-SBA-15 had large surface areas with ordered channel structure. Moreover, the effects of adsorption time, sorbent dose, solution pH, initial uranium concentration and temperature on the uranium adsorption behaviors were investigated. TBP-SBA-15 showed a high uranium adsorption capacity in a broad range of pH values. The U(VI) adsorption rate of TBP-SBA-15 was fast and nearly achieved completion in 10 min with the sorbent dose of 1 g/L. The U(VI) adsorption of TBP-SBA-15 followed the pseudo-second-order kinetic model and Freundlich isotherm model, indicating that the process was belonged to chemical adsorption. Furthermore, the thermodynamic parameters (ΔG{sup 0}, ΔH{sup 0} and ΔS{sup 0}) confirmed that the adsorption process was endothermic and spontaneous.

Uranium complex recycling method of purifying uranium liquors

International Nuclear Information System (INIS)

Elikan, L.; Lyon, W.L.; Sundar, P.S.

1976-01-01

Uranium is separated from contaminating cations in an aqueous liquor containing uranyl ions. The liquor is mixed with sufficient recycled uranium complex to raise the weight ratio of uranium to said cations preferably to at least about three. The liquor is then extracted with at least enough non-interfering, water-immiscible, organic solvent to theoretically extract about all of the uranium in the liquor. The organic solvent contains a reagent which reacts with the uranyl ions to form a complex soluble in the solvent. If the aqueous liquor is acidic, the organic solvent is then scrubbed with water. The organic solvent is stripped with a solution containing at least enough ammonium carbonate to precipitate the uranium complex. A portion of the uranium complex is recycled and the remainder can be collected and calcined to produce U 3 O 8 or UO 2

Analysis of uranium urinalysis and in vivo measurement results from eleven participating uranium mills

International Nuclear Information System (INIS)

Spitz, H.B.; Simpson, J.C.; Aldridge, T.L.

1984-05-01

Uranium urinalysis and in vivo examination results obtained from workers at eleven uranium mills between 1978 and 1980 were evaluated. The main purpose was to determine the degree of the mills' compliance with bioassay monitoring recommendations given in the draft NRC Regulatory Guide 8.22 (USNRC 1978). The effect of anticipated changes in the draft regulatory guidance, as expressed to PNL in May 1982, was also studied. Statistical analyses of the data showed that the bioassay results did not reliably meet the limited performance criteria given in the draft regulatory guide. Furthermore, quality control measurements of uranium in urine indicated that detection limits at α = β = 0.05 ranged from 13 μg/l to 29 μg/l, whereas the draft regulatory guidance suggests 5 μg/l as the detection limit. Recommendations for monitoring frequencies given in the draft guide were not followed consistently from mill to mill. The results of these statistical analyses indicate a need to include performance criteria for accuracy, precision, and confidence in revisions of the draft Regulatory Guide 8.22. Revised guidance should also emphasize the need for each mill to continually test the laboratory performing urinalyses by submitting quality control samples (i.e., blank and spiked urine samples as open and blind test) to insure that the performance criteria are being met. Recommendations for a bioassay audit program are also given. 25 references, 15 figures, 17 tables

National Uranium Resource Evaluation. Groundwater prospecting for sandstone-type uranium deposits: the merits of mineral-solution equilibria versus single element tracer methods. Final report

International Nuclear Information System (INIS)

Chatham, J.R.; Wanty, R.B.; Langmuir, D.

1981-02-01

Groundwaters from aquifers in two different sandstone-type uranium mining districts in Texas and Wyoming were collected and chemically analyzed. The data were used to compare the merits of using the computed saturation state of the groundwater with respect to uranium minerals, to that of single-element tracers in the groundwater for geochemical prospecting. Chemical properties of the Texas waters were influenced locally by preferred groundwater flow within buried fluvial channel deposits; upward leakage of brines along growth faults into the aquifer; and the establishment of a redox interface (Eh = 0 volts) within the aquifer. Chemical characteristics of aquifer waters in Wyoming changed gradually downdip, reflecting regional homogeneity in groundwater flow and a more gradual downdip reduction of Eh values than in Texas. The most reliable indicator of reduced uranium ore in both study sites was the saturation state of groundwater with respect to uraninite or coffinite. For both minerals, this saturation state increased from 15 to 20 log units as reduced ore deposits were approached over distances of 3 to 4.5 km in both sites. Tyuyamunite and carnotite approached or exceeded saturation in some oxidized waters of the Texas site reflecting possible occurrences of these minerals. The radiogenic elements Ta and Rn were excellent indicators of ore directly within the deposits, where anomalous values were 2 to 3 orders of magnitude above background. Helium also increased near the ore, although anomalies were generally displaced in the direction of groundwater flow. Uranium and uranium isotope values did not individually pinpoint ore, but may be used together to classify groundwater samples in terms of their position relative to uranium mineralization

Implications of using alternate fuel cycles to meet Ontario's nuclear power demand

International Nuclear Information System (INIS)

Lau, J.H.K.

1978-08-01

The use of alternate fuel cycles to meet an assumed nuclear capacity growth rate in Ontario is examined. Two criteria are used: the ability of the alternate fuel cycles to lessen the uranium demand; and the ease of commercialization. The nuclear strategies considered assume the use of the natural uranium cycle and, starting in the year 2000, the gradual introduction of an alternate fuel cycle. The alternate fuel cycles reviewed are enriched uranium, mixed oxides, and a variety of thorium cycles. The cumulative uranium requirement to the year 2070, and the growth and size of the reprocessing and fuel fabrication industries are discussed in detail. Sensitivity analyses on nuclear capacity growth rate, recycling loss and delay time are also described. (auth)

Uranium

International Nuclear Information System (INIS)

Toens, P.D.

1981-03-01

The geological setting of uranium resources in the world can be divided in two basic categories of resources and are defined as reasonably assured resources, estimated additional resources and speculative resources. Tables are given to illustrate these definitions. The increasing world production of uranium despite the cutback in the nuclear industry and the uranium requirements of the future concluded these lecture notes

Geology of Mt. Taylor uranium mine, Grants, New Mexico

International Nuclear Information System (INIS)

Alief, M.H.; Kern, R.A.

1989-01-01

The Mt. Taylor uranium mine is located 25 mi due northeast of Grants, New Mexico. Gulf Mineral Resources attained interest in the property in 1971. Surface drilling outlined several orebodies extending for 7 mi and containing over 120 million lb of uranium oxide (U 3 O 8 ). Gulf sank two shafts and developed the orebody in Sec. 24, T13N, R8W. Due to depressed markets, the mine was shut down in 1982. Chevron reopened the mine in 1985 following the 1984 Gulf-Chevron merger. The uranium ore occurs in the Westwater Canyon Sandstone Member of the Jurassic Morrison Formation. The Westwater Canyon member was deposited as part of a braided-stream channel system. Mineralization was emplaced following the deposition and possibly prior to consolidation of the host. Uranium is intimately associated with carbonaceous matter that may have been deposited as humates prior to and/or contemporaneous with the uranium mineralization. Mineralization coats sand grains and fills intergranular voids. Since 1985, Chevron has produced more than 5 million lb of U 3 O 8 , most of it from Sec. 24 and Sec. 19 (T13N, R7W). Plans are to complete extraction in these sections and to continue southeasterly into Sec. 25 (T13N, R8W) and Sec. 30 (T13N, R7W). More than 40 million lb of U 3 O 8 may be mined from the present facilities. At the current mining rate of 1.5 million lb/year, supplies should take them well beyond the year 2000

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

Analysis of beryllium and depleted uranium: An overview of detection methods in aerosols and soils

International Nuclear Information System (INIS)

Camins, I.; Shinn, J.H.

1988-06-01

We conducted a survey of commercially available methods for analysis of beryllium and depleted uranium in aerosols and soils to find a reliable, cost-effective, and sufficiently precise method for researchers involved in environmental testing at the Yuma Proving Ground, Yuma, Arizona. Criteria used for evaluation include cost, method of analysis, specificity, sensitivity, reproducibility, applicability, and commercial availability. We found that atomic absorption spectrometry with graphite furnace meets these criteria for testing samples for beryllium. We found that this method can also be used to test samples for depleted uranium. However, atomic absorption with graphite furnace is not as sensitive a measurement method for depleted uranium as it is for beryllium, so we recommend that quality control of depleted uranium analysis be maintained by testing 10 of every 1000 samples by neutron activation analysis. We also evaluated 45 companies and institutions that provide analyses of beryllium and depleted uranium. 5 refs., 1 tab

Recovery of uranium from uranium bearing black shale

International Nuclear Information System (INIS)

Das, Amrita; Yadav, Manoj; Singh, Ajay K.

2016-01-01

Black shale is the unconventional resource of uranium. Recovery of uranium from black shale has been carried out by the following steps: i) size reduction, ii) leaching of uranium in the aqueous medium, iii) fluoride ion removal, iv) solvent extraction of uranium from the aqueous leach solution, v) scrubbing of the loaded solvent after extraction to remove impurities as much as possible and vi) stripping of uranium from the loaded organic into the aqueous phase. Leaching of black shale has been carried out in hydrochloric acid. Free acidity of the leach solution has been determined by potentiometric titration method. Removal of fluoride ions has been done using sodium chloride. Solvent extraction has been carried out by both tributyl phosphate and alamine-336 as extractants. Scrubbing has been tried with oxalic acid and sulphuric acid. Stripping with sodium carbonate solution has been carried out. Overall recovery of uranium is 95%. (author)

Uranium resources, 1983

International Nuclear Information System (INIS)

1983-01-01

The specific character of uranium as energy resources, the history of development of uranium resources, the production and reserve of uranium in the world, the prospect regarding the demand and supply of uranium, Japanese activity of exploring uranium resources in foreign countries and the state of development of uranium resources in various countries are reported. The formation of uranium deposits, the classification of uranium deposits and the reserve quantity of each type are described. As the geological environment of uranium deposits, there are six types, that is, quartz medium gravel conglomerate deposit, the deposit related to the unconformity in Proterozoic era, the dissemination type magma deposit, pegmatite deposit and contact deposit in igneaus rocks and metamorphic rocks, vein deposit, sandstone type deposit and the other types of deposit. The main features of respective types are explained. The most important uranium resources in Japan are those in the Tertiary formations, and most of the found reserve belongs to this type. The geological features, the state of yield and the scale of the deposits in Ningyotoge, Tono and Kanmon Mesozoic formation are reported. Uranium minerals, the promising districts in the world, and the matters related to the exploration and mining of uranium are described. (Kako, I.)

Design project of the experimental device for studying the uranium Creep in the reactor; Predprojekat eksperimentalnog uredjaja za ispitivanje CREEP-a urana u reaktoru

Energy Technology Data Exchange (ETDEWEB)

Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Odeljenje za reaktorsku eksperimentalnu tehniku, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

The objective of this task was constructing a device for creep testing of uranium, i.e permanent deformation of the irradiated fuel. Deformation results from the influence of thermal neutron flux, temperature, time of irradiation, mechanical stress. This describes two possible technical solutions experimental device for creep testing in the vertical experimental channel and in the horizontal experimental channel of the RA reactor. In addition to the design details, the report covers calculations of heat generation, antireactivity, activation of the materials of the constructed experimental loop, mechanical calculations as well as description of measurements and regulation of the uranium sample temperature.

Uranium management activities

International Nuclear Information System (INIS)

Jackson, D.; Marshall, E.; Sideris, T.; Vasa-Sideris, S.

2001-01-01

One of the missions of the Department of Energy's (DOE) Oak Ridge Office (ORO) has been the management of the Department's uranium materials. This mission has been accomplished through successful integration of ORO's uranium activities with the rest of the DOE complex. Beginning in the 1980's, several of the facilities in that complex have been shut down and are in the decommissioning process. With the end of the Cold War, the shutdown of many other facilities is planned. As a result, inventories of uranium need to be removed from the Department facilities. These inventories include highly enriched uranium (HEU), low enriched uranium (LEU), normal uranium (NU), and depleted uranium (DU). The uranium materials exist in different chemical forms, including metals, oxides, solutions, and gases. Much of the uranium in these inventories is not needed to support national priorities and programs. (author)

Carbonate and citric acid leaching of uranium from uranium-contaminated soils: Pilot-scale studies (Phase II)

International Nuclear Information System (INIS)

Wilson, J.H.; Chernikoff, R.; DeMarco, W.D.

1995-10-01

The purpose of this document is to describe the results of the soil decontamination demonstration conducted at the Fernald Environmental Management Project (FEMP) site by the Fernald Environmental Restoration and Management Corporation (FERMCO) and the Oak Ridge National Laboratory (ORNL). This demonstration, which began in November 1993 and ended in October 1994, involved the removal of uranium from contaminated soil sampled from two FEMP sites. The demonstration was conducted so as to meet the requirements of the Fernald Site Integrated Demonstration program, as well as all environmental, safety, and health requirements of the site

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

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

Uranium industry framework

International Nuclear Information System (INIS)

Riley, K.

2008-01-01

The global uranium market is undergoing a major expansion due to an increase in global demand for uranium, the highest uranium prices in the last 20 years and recognition of the potential greenhouse benefits of nuclear power. Australia holds approximately 27% of the world's uranium resources (recoverable at under US$80/kg U), so is well placed to benefit from the expansion in the global uranium market. Increasing exploration activity due to these factors is resulting in the discovery and delineation of further high grade uranium deposits and extending Australia's strategic position as a reliable and safe supplier of low cost uranium.

High-temperature thermal conductivity of uranium chromite and uranium niobate

International Nuclear Information System (INIS)

Fedoseev, D.V.; Varshavskaya, I.G.; Lavrent'ev, A.V.; Oziraner, S.N.; Kuznetsova, D.G.

1979-01-01

The technique of determining thermal conductivity coefficient of uranium niobate and uranium chromite on heating with laser radiation is described. Determined is the coefficient of free-convective heat transfer (with provision for a conduction component) by means of a standard specimen. The thermal conductivity coefficients of uranium chromite and niobate were measured in the 1300-1700 K temperature range. The results are presented in a diagram form. It has been calculated, that the thermal conductivity coefficient for uranium niobate specimens is greater in comparison with uranium chromite specimens. The thermal conductivity coefficients of the materials mentioned depend on temperature very slightly. Thermal conductivity of the materials considerably depends on their porosity. The specimens under investigation were fabricated by the pressing method and had the following porosity: uranium chromite - 30 %, uranium niobate - 10 %. Calculation results show, that thermal conductivity of dense uranium chromite is higher than thermal conductivity of dense uranium niobate. The experimental error equals approximately 20 %, that is mainly due to the error of measuring the temperature equal to +-25 deg, with a micropyrometer

Study of reactions between uranium-plutonium mixed oxide and uranium nitride and between uranium oxide and uranium nitride; Etude des reactions entre l`oxyde mixte d`uranium-plutonium et le nitrure d`uranium et entre l`oxyde d`uranium et le nitrure d`uranium

Energy Technology Data Exchange (ETDEWEB)

Lecraz, C

1993-06-11

A new type of combustible elements which is a mixture of uranium nitride and uranium-plutonium oxide could be used for Quick Neutrons Reactors. Three different studies have been made on the one hand on the reactions between uranium nitride (UN) and uranium-plutonium mixed oxide (U,Pu)O{sub 2}, on the other hand on these between UN and uranium oxide UO{sub 2}. They show a sizeable reaction between nitride and oxide for the studied temperatures range (1573 K to 1973 K). This reaction forms a oxynitride compound, MO{sub x} N{sub y} with M=U or M=(U,Pu), whose crystalline structure is similar to oxide`s. Solubility of nitride in both oxides is studied, as the reaction kinetics. (TEC). 32 refs., 48 figs., 22 tabs.

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)

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

Energy Technology Data Exchange (ETDEWEB)

Peterson, A [AB Atomenergi, Stockholm (Sweden)

1967-06-15

The Ministry of Education was authorized in November 1945 to appoint a commission to study the organization of nuclear energy research. In April 1947 this commission, the Swedish Atomic Energy Commission, proposed the formation of a semi-state-owned company to be a central body for applied research work and development in the nuclear energy field in Sweden. In November 1947 the Atomic Energy Company (AB Atomenergi) had its statutory meeting. The State owns 4/7 of the share capital and the remaining 3/7 is owned by 71 private and municipal share-holders. Except for a part of the stock capital, all investments and running costs of the company have been financed by the Government. The company is in practice answerable to the Department of Commerce which has an advisory body, the Atomic Energy Board. AB Atomenergi is responsible for Government-financed research on the industrial applications of nuclear energy, the milling of uranium ores and refining of uranium. The total number of employees is at present about 1400, 800 of which work at the company's research establishment Studsvik about 120 km south of Stockholm. As early as 1945 the Research Institute of the Swedish National Defence started work in the field of uranium processing. Similar work was also started quite early by the Boliden Mining Company, the Swedish Shale Oil Company and Wargons AB. After the establishment of AB Atomenergi, all work in the uranium processing field was transferred to this company. In fact one of the main reasons for the formation of AB Atomenergi was the need for Swedish uranium production as there was no possibility of importing uranium at that time. As a result of research and development in uranium processing a pilot plant at Kvarntorp near Orebro in central Sweden started milling a low-grade uranium ore (shale) in 1953. The capacity of this plant was 5-10 tons of uranium a year. A uranium mill at Ranstad in south-west Sweden, near Skovde, with a capacity of 120 tons of uranium a

The sedimentology and uranium mineralization of the Klipbankskraal deposit north of Merweville, C.P

International Nuclear Information System (INIS)

Le Roux, J.P.

1982-08-01

A sedimentological study was conducted on the farm Klipbankskraal, north-west of Merweville. The orebody is located in the Poortjie Member at the base of the Teekloof Formation. The mineralised sandstone, S1, is a tabular lithosome deposited in an ephemeral, braided river environment. It consists of two major and several minor mesocycles, with the upper major cycle showing evidence of having inherited the drainage pattern of the lower mesocycle. The vector mean azimuth of the sequence as a whole is towards 059 degrees. The uranium is present as stacked, tabular lenses associated with permeable zones in the immediate vicinity of erosional inter-cycle contacts. Although no obvious relationship exists between the uranium and channels or bars, the distribution of plant material was controlled by the current velocities which also controlled the type of sedimentary structures. Uranium occurs preferentially in fissile-weathering (horizontal-bedded) sandstone and mud-pebble conglomerate, both permeable lithologies, and in mudstone or silt-stone. Uranium is genetically related to other elements such as Mn, Mo, Cu, Co and Pb, which must have been constituents of the ore fluid. Uraniferous granites in the source areas probaly supplied most of the uranium

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.

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

Geology of the uranium occurrence in the Bungua area, Siavonga District, Zambia

International Nuclear Information System (INIS)

Prasad, R.S.; Money, N.J.; Thieme, J.G.

1979-01-01

Uranium mineralization related to the fluviatile continental sandstone of the Escarpment Grit Formation of Upper Karroo System has been studied in detail in the Bungua area. Airborne and ground gamma-radiation surveys resulted in the discovery of mineralized bodies containing secondary minerals such as meta-autunite, phosphuranylite, uranocircite, abernythite, boltwoodite, etc. disseminated in various ways. Geological, radiometric, stratigraphic, sedimentological and petrological studies coupled with exploration pitting, trenching and drilling were employed to assess the nature, distribution and sub-surface continuation of mineralized bodies. Drilling, logging and XRF analysis revealed that the uranium mineralized bodies are mainly lenses at different levels, which may be concordant or discordant with bedding. The thickness and grade of ore horizons differ considerably. Mineral distribution and controls are complex and that the main deposit is controlled by reducing lithologies, organic matter, clay traps, micas, iron cementing and permeable channels. Although no definite mode of origin can be attributed to the presently seen uranium mineralized bodies, they appear to be from a pre-existing ore deposit which is mobilized and redistributed during oxidation by supergene processes. It is suggested that the original uranium was in solution as uranylion and came from the same source area as the host rocks and the uranium-bearing groundwater and streams moved in the same direction as the associated Escarpment Grit sediments. Uranium was precipitated wherever favourable conditions prevailed in the Escarpment Grit Formation. (author)

Calculation and measurement of the uranium temperature during irradiation in the experimental channel in the reflector of the RA reactor - Annex 15; Prilog 15 - Proracun i merenje temperature urana pri ozracivanju u eksperimentalnom kanalu reflektora na reaktoru RA

Energy Technology Data Exchange (ETDEWEB)

Nikolic, M; Strugar, P; Mitrovic, S [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1964-12-15

Upon demand of the Laboratory for fuel reprocessing, six domestic metal uranium pellets were exposed to neutron flux ( 4 - 5 10{sup 12} n cm{sup -2} sec {sup -1}) in the RA reactor. Irradiation of fuel demanded special analyses for safety reasons. Weight of the fuel pellets was 13 - 20 g, having diameter 20 mm. pellets were placed in leak tight aluminium capsules with helium. The irradiation was dome in the aluminium experimental channel in the graphite reflector. Theoretical study has shown that the expected fuel temperature in the core could be up to 300 deg C at nominal power. For that reason temperature of the capsule with the uranium sample was measured during irradiation by using thermocouples. Results showed the discrepancy between measure and calculated values to be about 30%.

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.

76 FR 43678 - Notice of Public Scoping Meetings and Extension of Scoping Period for the U.S. Department of...

Science.gov (United States)

2011-07-21

.... Department of Energy Uranium Leasing Program Programmatic Environmental Impact Statement AGENCY: Department... Uranium Leasing Program (ULP) Programmatic Environmental Impact Statement (hereinafter referred to as the... meetings in a subsequent Federal Register notice, as well as in local news media. DOE now announces the...

Depleted uranium

International Nuclear Information System (INIS)

Huffer, E.; Nifenecker, H.

2001-02-01

This document deals with the physical, chemical and radiological properties of the depleted uranium. What is the depleted uranium? Why do the military use depleted uranium and what are the risk for the health? (A.L.B.)

Pyrophoric behaviour of uranium hydride and uranium powders

Science.gov (United States)

Le Guyadec, F.; Génin, X.; Bayle, J. P.; Dugne, O.; Duhart-Barone, A.; Ablitzer, C.

2010-01-01

Thermal stability and spontaneous ignition conditions of uranium hydride and uranium metal fine powders have been studied and observed in an original and dedicated experimental device placed inside a glove box under flowing pure argon. Pure uranium hydride powder with low amount of oxide (Oxidation mechanisms are proposed.

RECOVERY OF URANIUM FROM ZIRCONIUM-URANIUM NUCLEAR FUELS

Science.gov (United States)

Gens, T.A.

1962-07-10

An improvement was made in a process of recovering uranium from a uranium-zirconium composition which was hydrochlorinated with gsseous hydrogen chloride at a temperature of from 350 to 800 deg C resulting in volatilization of the zirconium, as zirconium tetrachloride, and the formation of a uranium containing nitric acid insoluble residue. The improvement consists of reacting the nitric acid insoluble hydrochlorination residue with gaseous carbon tetrachloride at a temperature in the range 550 to 600 deg C, and thereafter recovering the resulting uranium chloride vapors. (AEC)

National Uranium Resource Evaluation, Scranton Quadrangle, Pennsylvania, New York, and New Jersey

International Nuclear Information System (INIS)

Baillieul, T.A.; Indelicato, G.J.; Penley, H.M.

1980-11-01

Reconnaissance and detailed geologic and radiometric investigations were conducted throughout the Scranton Quadrangle, Pennsylvania, New York, and New Jersey, to evaluate uranium favorability using National Uranium Resource Evaluation criteria. Surface and subsurface studies were augmented by aerial radiometric, hydrogeochemical and stream sediment reconnaissance, and emanometry surveys. Results of the investigations indicate four environments favorable for uranium deposits: In the Precambrian metamorphic terrain of the Reading Prong, magmatic-hydrothermal and anatectic deposits may occur in the northwestern massif; contact metasomatic deposits may occur in a portion of the southeastern massif. The alluvial-fan environment at the base of the Upper Devonian Catskill Formation appears favorable for deposits in peneconcordant channel controlled sandstones. Seven environments are considered unfavorable for uranium deposits: the southeastern massif of the Reading Prong, exclusive of that portion denoted as a favorable contact metasomatic environment; the lower Paleozoic sedimentary units; the Beemerville nepheline syenite complex; the Upper Devonian Catskill Formation, exclusive of the favorable basal alluvial-fan facies; Mississippian and Pennsylvanian units; and peat bogs. Two environments were not evaluated: the Spechty Kopf Formation, because of paucity of exposure and lack of sufficient data; and the Newark Basin, because of cultural density and inadequate subsurface information

Uranium prospecting; La prospection de l'uranium

Energy Technology Data Exchange (ETDEWEB)

Roubault, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

This report is an instruction book for uranium prospecting. It appeals to private prospecting. As prospecting is now a scientific and technical research, it cannot be done without preliminary studies. First of all, general prospecting methods are given with a recall of fundamental geologic data and some general principles which are common with all type of prospecting. The peculiarities of uranium prospecting are also presented and in particular the radioactivity property of uranium as well as the special aspect of uranium ores and the aspect of neighbouring ores. In a third part, a description of the different uranium ores is given and separated in two different categories: primary and secondary ores, according to the place of transformation, deep or near the crust surface respectively. In the first category, the primary ores include pitchblende, thorianite and rare uranium oxides as euxenite and fergusonite for example. In the second category, the secondary ores contain autunite and chalcolite for example. An exhaustive presentation of the geiger-Mueller counter is given with the presentation of its different components, its functioning and utilization and its maintenance. The radioactivity interpretation method is showed as well as the elaboration of a topographic map of the measured radioactivity. A brief presentation of other detection methods than geiger-Mueller counters is given: the measurement of fluorescence and a chemical test using the fluorescence properties of uranium salts. Finally, the main characteristics of uranium deposits are discussed. (M.P.)

Proceedings of the meeting on nuclear physics experiments using pions and muons

International Nuclear Information System (INIS)

Yamazaki, Toshimitsu; Yukawa, Tetsuyuki; Tanabe, Kosai

1978-06-01

Reports made in the meeting are presented individually. The meeting held is under circumstances of alteration in the booster meson channel and the main ring π/μ channels, with emphasis thus on propositions. It is also intended to middle energy physics. (Mori, K.)

Grouting of uranium mill tailings piles

International Nuclear Information System (INIS)

Boegly, W.J. Jr.; Tamura, T.; Williams, J.D.

1984-03-01

A program of remedial action was initiated for a number of inactive uranium mill tailings piles. These piles result from mining and processing of uranium ores to meet the nation's defense and nuclear power needs and represent a potential hazard to health and the environment. Possible remedial actions include the application of covers to reduce radon emissions and airborne transport of the tailings, liners to prevent groundwater contamination by leachates from the piles, physical or chemical stabilization of the tailings, or moving the piles to remote locations. Conventional installation of liners would require excavation of the piles to emplace the liner; however, utilization of grouting techniques, such as those used in civil engineering to stabilize soils, might be a potential method of producing a liner without excavation. Laboratory studies on groutability of uranium mill tailings were conducted using samples from three abandoned piles and employing a number of particulate and chemical grouts. These studies indicate that it is possible to alter the permeability of the tailings from ambient values of 10 -3 cm/s to values approaching 10 -7 cm/s using silicate grouts and to 10 -8 cm/s using acrylamide and acrylate grouts. An evaluation of grouting techniques, equipment required, and costs associated with grouting were also conducted and are presented. 10 references, 1 table

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 supply and demand

Energy Technology Data Exchange (ETDEWEB)

Spriggs, M J

1976-01-01

Papers were presented on the pattern of uranium production in South Africa; Australian uranium--will it ever become available; North American uranium resources, policies, prospects, and pricing; economic and political environment of the uranium mining industry; alternative sources of uranium supply; whither North American demand for uranium; and uranium demand and security of supply--a consumer's point of view. (LK)

National Uranium Resource Evaluation: Salina Quadrangle, Utah

International Nuclear Information System (INIS)

Lupe, R.D.; Campbell, J.A.; Franczyk, K.J.; Luft, S.J.; Peterson, F.; Robinson, K.

1982-09-01

Two stratigraphic units, the Late Jurassic Salt Wash Member of the Morrison Formation and the Triassic Chinle Formation, were determined to be favorable for the occurrence of uranium deposits that meet the minimum size and grade requirements of the US Department of Energy in the Salina 1 x 2 0 Quadrangle, Utah. Three areas judged favorable for the Salt Wash Member are the Tidwell and Notom districts, and the Henry Mountains mineral belt. The criteria used to establish favorability were the presence of: (1) fluvial sandstone beds deposited by low-energy streams; (2) actively moving major and minor structures such as the Paradox basin and the many folds within it; (3) paleostream transport directions approximately perpendicular to the trend of many of the paleofolds; (4) presence of favorable gray lacustrine mudstone beds; and (5) known uranium occurrences associated with the favorable gray mudstones. Four favorable areas have been outlined for the Chinle Formation. These are the San Rafael Swell, Inter River, and the Orange Cliffs subareas and the Capitol Reef area. The criteria used to establish these areas are: the sandstone-to-mudstone ratios and the geographic distribution of the Petrified Forest Member of the Chinle Formation which is considered as the probable source for the uranium

Determination of the impurities Al, Mn, Fe, Ni, Cu and Zn in nuclear grade uranium by ICP-OES

Energy Technology Data Exchange (ETDEWEB)

Kakazu, Mauricio H.; Cotrim, Marycel E.B.; Silva, Douglas B. da; Pires, Maria Aparecida F., E-mail: mhkakazu@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

Uranium compounds are specially produced for use in nuclear reactors and must meet strict physical and chemicals specifications. The current study discusses the separation of Al, Mn, Fe, Ni, Cu and Zn from uranium compounds and their quantitative determination using inductively coupled plasma optical emission spectrometry. To avoid interference effect caused by uranium in the spectroscopic emission lines of elements of interest, the chromatographic behavior of TBP impregnated macroporous Amberlite XAD-4 column was investigated. The break through curves of uranium obtained showed maximum retention of up to 11 grams of uranium and the elution curves for the elements showed reproducible recovery rate of 90% on 50 mL elution. Synthetic samples of nuclear grade uranium prepared with the addition of 250 {mu}g/g of U of the above individual elements were used to verify the performance of the method. The method showed a recovery rate of 80 to 90% for the elements under study. (author)

Determination of the impurities Al, Mn, Fe, Ni, Cu and Zn in nuclear grade uranium by ICP-OES

International Nuclear Information System (INIS)

Kakazu, Mauricio H.; Cotrim, Marycel E.B.; Silva, Douglas B. da; Pires, Maria Aparecida F.

2011-01-01

Uranium compounds are specially produced for use in nuclear reactors and must meet strict physical and chemicals specifications. The current study discusses the separation of Al, Mn, Fe, Ni, Cu and Zn from uranium compounds and their quantitative determination using inductively coupled plasma optical emission spectrometry. To avoid interference effect caused by uranium in the spectroscopic emission lines of elements of interest, the chromatographic behavior of TBP impregnated macroporous Amberlite XAD-4 column was investigated. The break through curves of uranium obtained showed maximum retention of up to 11 grams of uranium and the elution curves for the elements showed reproducible recovery rate of 90% on 50 mL elution. Synthetic samples of nuclear grade uranium prepared with the addition of 250 μg/g of U of the above individual elements were used to verify the performance of the method. The method showed a recovery rate of 80 to 90% for the elements under study. (author)

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

Deployable nuclear fleet based on available quantities of uranium and reactor types – the case of fast reactors started up with enriched uranium

Directory of Open Access Journals (Sweden)

Baschwitz Anne

2016-01-01

Full Text Available International organizations regularly produce global energy demand scenarios. To account for the increasing population and GDP trends, as well as to encompass evolving energy uses while satisfying constraints on greenhouse gas emissions, long-term installed nuclear power capacity scenarios tend to be more ambitious, even after the Fukushima accident. Thus, the amounts of uranium or plutonium needed to deploy such capacities could be limiting factors. This study first considers light-water reactors (LWR, GEN III using enriched uranium, like most of the current reactor technologies. It then examines the contribution of future fast reactors (FR, GEN IV operating with an initial fissile load and then using depleted uranium and recycling their own plutonium. However, as plutonium is only available in limited quantity since it is only produced in nuclear reactors, the possibility of starting up these Generation IV reactors with a fissile load of enriched uranium is also explored. In one of our previous studies, the uranium consumption of a third-generation reactor like an EPR™ was compared with that of a fast reactor started up with enriched uranium (U5-FR. For a reactor lifespan of 60 years, the U5-FR consumes three times less uranium than the EPR and represents a 60% reduction in terms of separative work units (SWU, though its requirements are concentrated over the first few years of operation. The purpose of this study is to investigate the relevance of U5-FRs in a nuclear fleet deployment configuration. Considering several power demand scenarios and assuming different finite quantities of available natural uranium, this paper examines what types of reactors must be deployed to meet the demand. The deployment of light-water reactors only is not sustainable in the long run. Generation IV reactors are therefore essential. Yet when started up with plutonium, the number of reactors that can be deployed is also limited. In a fleet deployment

Concentration of uranium on TiO-PAN and NaTiO-PAN composite absorbers

International Nuclear Information System (INIS)

Motl, Alois; Sebesta, Ferdinand; John, Jan; Spendlikova, Irena; Nemec, Mojmir

2013-01-01

Inorganic ion exchangers have been extensively tested for use in separation and concentration of uranium from Surface water. Except for separation of uranium from uranium -Contaminated waste water (e.g. waste water from mining and milling of uranium, Waste from nuclear fuel reprocessing) their main area of application has been foreseen to be their use for extraction of uranium from sea water which could partially cover future needs of uranium. Another perspective area of application is pre-concentration of uranium from natural waters followed by uranium determination via various specialized techniques such as TRLFS or AMS. Possibilities of uranium extraction from sea water have been subject of several international conferences (e.g. Topical meetings on the Recovery of Uranium from Seawater in 1980's, ACS National Meetings 2012 etc.) and are critically evaluated in a review by Bitte or recently by Kim. In the Czech Republic uranium-selective inorganic ion exchangers might be applied for treatment of various wastes from uranium industry, namely underground Water, uranium milling over-balance water, or acid waste water from underground uranium leaching and also like in other countries for determination of uranium isotopic composition focusing on anthropogenic and natural 236 U content. Among the best performing inorganic ion exchangers for the above listed purposes hydrated titanium dioxide (abbreviated as TiO) and sodium titanate (abbreviated as NaTiO) can be listed. Properties of TiO and NaTiO were reviewed by Lehto. From the point of view of ion-exchange, properties of hydrated titanium oxide and sodium titanate are very similar. The main disadvantage of these ion exchangers for industrial-scale application is their insufficient mechanical stability. To improve this property, the sorption materials can be embedded into a binding matrix. Modified polyacrylonitrile (PAN) has been proposed at the Czech Technical University in Prague as a universal binding matrix for

Uranium price reporting systems

International Nuclear Information System (INIS)

1987-09-01

This report describes the systems for uranium price reporting currently available to the uranium industry. The report restricts itself to prices for U 3 O 8 natural uranium concentrates. Most purchases of natural uranium by utilities, and sales by producers, are conducted in this form. The bulk of uranium in electricity generation is enriched before use, and is converted to uranium hexafluoride, UF 6 , prior to enrichment. Some uranium is traded as UF 6 or as enriched uranium, particularly in the 'secondary' market. Prices for UF 6 and enriched uranium are not considered directly in this report. However, where transactions in UF 6 influence the reported price of U 3 O 8 this influence is taken into account. Unless otherwise indicated, the terms uranium and natural uranium used here refer exclusively to U 3 O 8 . (author)

International Uranium Resources Evaluation Project (IUREP) national favourability studies: Australia

International Nuclear Information System (INIS)

1977-08-01

In Australia most exploration for uranium has been conducted by companies and individuals. The geological mapping and airborne radiometric surveying conducted by the BMR is made available to interested persons. Exploration for uranium in Australia can be divided into two periods - 1947 to 1961 and 1966-1977. During the first period the Commonwealth Government introduced measures to encourage uranium exploration including a system of rewards for the discovery of uranium ore. This reward system resulted in extensive activity by prospectors particularly in the known mineral fields. Equipped with a Geiger counter or scintillometer, individuals with little or no experience in prospecting could compete with experienced prospectors and geologists. During this period several relative small uranium deposits were discovered generally by prospectors who found outcropping mineralisation. The second phase of uranium exploration in Australia began in 1966 at which time reserves amounted to only 6,200 tonnes of uranium and by 3 977 reserves had been increased to 289,000 tonnes. Most of the exploration was done by companies with substantial exploration budgets utilising more advanced geological and geophysical techniques. In the field of airborne radiometer the development of multi-channel gamma ray spectrometers with large volume crystal detectors increased the sensitivity of the tool as a uranium detector and resulted in several major discoveries. Expenditure or exploration for uranium increased from 1966 to 1971 but has declines in recent years. After listing the major geological elements of Australia, its uranium production and resources are discussed. During the period 1954-71 the total production of uranium concentrate in Australia amounted to 7,780 tonnes of uranium, and was derived from deposits at Rum Jungle (2,990 tonnes U) and the South Alligator River (610 tonnes U) in the Northern Territory, Mary Kathleen (3,460 tonnes U) in Queensland and Radium Hill (720 tonnes U

Formation mechanism of uranium minerals at sandstone-type uranium deposits

International Nuclear Information System (INIS)

Li Shengfu; Zhang Yun

2004-01-01

By analyzing the behavior and existence form of uranium in different geochemical environments, existence form of uranium and uranium minerals species, this paper expounds the formation mechanism of main commercial uranium mineral--pitchblende: (1) uranium is a valence-changeable element. It is reactivated and migrates in oxidized environment, and is reduced and precipitated in reducing environment; (2) [UO 2 (CO 3 ) 3 ] 4- , [UO 2 (CO 3 ) 2 ] 2- coming from oxidized environment react with reductants such as organic matter, sulfide and low-valence iron at the redox front to form simple uranium oxide--pitchblende; (3)the adsorption of uranium by organic matter and clay minerals accelerates the reduction and the concentration of uranium. Therefore, it is considered, that the reduction of SO 4 2- by organic matter to form H 2 S, and the reduction of UO 2 2+ by H 2 S are the main reasons for the formation of pitchblende. This reaction is extensively and universally available in neutral and weakly alkaline carbonate solution. The existense of reductants such as H 2 S is the basic factor leading to the decrease of Eh in environments and the oversaturation of UO 2 2+ at the redox front in groundwater, thus accelerating the adsorption and the precipitation of uranium

Wind power or uranium mine: Appraisal of two energy-related environmental changes in a local context

International Nuclear Information System (INIS)

Pedersen, Eja; Johansson, Maria

2012-01-01

This study explores factors associated with the individual's appraisal of anticipated environmental changes caused by energy production facilities. The study took place in a Swedish village where exploratory drilling, that could eventually lead to a uranium mine, was being conducted at the same time as a wind farm was approved. Results from the survey, which included the total population, were interpreted in the light of cognitive stress theory. Most residents thought that the wind farm would have a positive impact on the village but that the uranium drilling would have a negative impact; these opinions were closely related to attitudes towards wind and nuclear power. Perceiving the wind farm as positive was further predicted by young age, high education, being an ordinary rather than a committed recycler and having attended a meeting about the wind farm. A negative view of uranium drilling was predicted by the individual valuing closeness to nature, being a recycler, and having attended the uranium meeting. Psychological factors such as concerns for the environment (manifested as pro-environmental behaviour), valuing closeness to nature, and involvement impinge on the appraisal process and should be considered when new developments are presented. - Highlights: ► We studied the appraisal of proposed local environmental changes due to energy facilities. ► A wind farm was appraised as beneficial and drilling for uranium mine as threatening. ► Attitudes towards wind and nuclear power were strongly associated with appraisal outcome. ► Concern for the environment, closeness to nature and participation also played a role.

Uranium enrichment

International Nuclear Information System (INIS)

1990-01-01

This report looks at the following issues: How much Soviet uranium ore and enriched uranium are imported into the United States and what is the extent to which utilities flag swap to disguise these purchases? What are the U.S.S.R.'s enriched uranium trading practices? To what extent are utilities required to return used fuel to the Soviet Union as part of the enriched uranium sales agreement? Why have U.S. utilities ended their contracts to buy enrichment services from DOE?

Australian uranium industry

Energy Technology Data Exchange (ETDEWEB)

Warner, R K

1976-04-01

Various aspects of the Australian uranium industry are discussed including the prospecting, exploration and mining of uranium ores, world supply and demand, the price of uranium and the nuclear fuel cycle. The market for uranium and the future development of the industry are described.

Uranium enrichment plans

International Nuclear Information System (INIS)

Thomas, D.C.; Gagne, R.W.

1978-01-01

The following topics are covered: the status of the Government's existing uranium enrichment services contracts, natural uranium requirements based on the latest contract information, uncertainty in predicting natural uranium requirements based on uranium enrichment contracts, and domestic and foreign demand assumed in enrichment planning

Survey of United States uranium marketing activity

International Nuclear Information System (INIS)

Combs, G.F. Jr.; Krusiewski, S.V.

1980-07-01

In 1979 US buyers contracted for a net increase of 15,400 tons U 3 O 8 in new procurement after deducting for changes to January 1, 1979, commitments. Export commitments made in 1979 totalled 2800 tons, while import commitments amounted to 1000 tons U 3 O 8 . Buyers' inventories of domestic- and foreign-origin normal and enriched uranium increased to 52,300 tons U 3 O 8 during 1979, with the larger part of the increase being in enriched uranium. The average price reported for 1979 deliveries was $23.85 per pound of U 3 O 8 . Settlements of market price contracts average $42.55 for 1979 delivery and $45.80 for 1980 delivery. Producers expect to be able to offer 33,700 tons U 3 O 8 for sale in the 1980-1985 period, about 20% less than was estimated in the 1979 survey. Utilities made sales of 500 tons U 3 O 8 for 1979-1980 delivery as well as loans of 1600 tons U 3 O 8 that are to be repaid by 1984; more than half of these sales or loans were made to uranium producers. Reactor manufacturers have sold about 1100 tons U 3 O 8 since January 1, 1979, and loaned 120 tons. Unfilled requirements have decreased more than 100,000 tons U 3 O 8 since January 1, 1978, and currently total 75,700 tons U 3 O 8 . Responses to the 1980 survey suggest that there seems to be an adequate supply of uranium to meet US demand at least through 1985

Developments in natural uranium - graphite reactors; Developpement des reacteurs a graphite et uranium naturel

Energy Technology Data Exchange (ETDEWEB)

Bourgeois, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Saitcevsky, B. [Electricite de France (EDF), 75 - Paris (France)

1964-07-01

The French natural uranium-graphite power-reactor programme has been developing - from EDF 1 to EDF 4 - in the direction of an increase of the unit power of the installations, of the specific and volume powers, and of an improvement in the operational security conditions. The high power of EDF 4 (500 MWe) and the integration of the primary circuit into the reactor vessel, which is itself made of pre-stressed concrete, make it possible to make the most of the annular fuel elements already in use in EDF 1, and to arrive thus at a very satisfactory solution. The use of an internally cooled fuel element (an annular element) has led to a further step forward: it now becomes possible to increase the pressure of the cooling gas without danger of causing creep in the uranium tube. The use of a pre-stressed concrete vessel makes this pressure increase possible, and the integration of the primary circuit avoids the risk of a rapid depressurization which would be in this case a major danger. This report deals with the main problems presented by this new type of nuclear power station, and gives the main lines of research and studies now being carried out in France. - Neutronic and thermal research has made it possible to consider using large size fuel elements (internal diameter = 77 mm, external diameter 95 mm) while still using natural uranium. - The problems connected with the production of these elements and with their in pile behaviour are the subject of a large programme, both out of pile and in power reactors (EDF 2) and test reactors (Pegase). - The increase in the size of the element leads to a large lattice pitch (35 to 40 cm). This makes it possible to consider having one charging aperture per channel or for a small number of channels, whether the charge machine be inside or outside the pressure vessel. In conclusion are given the main characteristics of a project for a 500 MWe power station using such a fuel element. In particular this project is compared to EDF 4

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

Preliminary evaluation of the uranium favorability in the Kaiparowits Plateau Region, Garfield and Kane Counties, Utah

International Nuclear Information System (INIS)

Dubyk, W.S.; Young, P.

1978-05-01

The basal sandstone of the Chinle Formation (Upper Triassic) and the Salt Wash Member of the Morrison Formation (Upper Jurassic) in the Kaiparowits Plateau, southcentral Utah, were evaluated in terms of uranium potential. Both surface and subsurface data were utilized. Favorability of the basal Chinle sandstone was based on (1) presence of intermediate-size sandstone-filled channels cut into the Moenkopi; (2) presence of carbonaceous material; (3) an adequate source of uranium; and (4) gamma-ray anomalies from test-hole logs. Favorability of the Salt Wash Member of the Morrison Formation was based on (1) sandstone-mudstone ratios that approach equality, and (2) presence of thick sandstone lenses, carbonaceous material, and halos of light-tan to brown limonite staining. Although the basal Chinle sandstone and the Salt Wash Member of the Morrison contain sizable uranium deposits throughout much of the Colorado Plateau, both units lack characteristics that are favorable for significant uranium deposits in the Kaiparowits Plateau

National uranium resource evaluation, Las Vegas Quadrangle, Nevada, Arizona, and California

International Nuclear Information System (INIS)

Johnson, C.; Glynn, J.

1982-03-01

The Las Vegas 1 0 x 2 0 quadrangle, Nevada, Arizona, and California, contains rocks and structures from Precambrian through Holocene in age. It lies within the Basin and Range physiographic province adjacent to the westernmost portion of the Colorado Plateau. Miocene nonmarine sedimentary rocks of the Horse Spring Formation contain in excess of 100 tons U 3 O 8 in deposits at a grade of 0.01% or greater, and therefore meet National Uranium Resource Evaluation base criteria for uranium favorability. One favorable area lies in the South Virgin Mountains at the type locality of the Horse Spring Formation, although the favorable environment extends into the unevaluated Lake Mead National Recreation Area and Desert National Wildlife Range. Environments within the Las Vegas Quadrangle considered unfavorable for uranium include the Shinarump Conglomerate member of the Triassic Chinle Formation, Mesozoic sediments of the Glen Canyon Group, Precambrian pegmatites, Pliocene and Quaternary calcrete, Laramide thrust faults, and a late Precambrian unconformity

U.S. reference paper on the potential and limitations of uranium to meet the anticipated needs of nuclear energy

International Nuclear Information System (INIS)

1978-10-01

A framework is provided to analyze the interrelationship between uranium availability and the deployment of fast breeder and converter reactors. Included are models which can be used to estimate the uranium price for economic parity between breeders and converters, the dates for economical commercialization of fast breeders, and the effect of breeder deployment on uranium availability. Factors such as energy demand, resources and economics which are dominant in decisions as to potential breeder commercialization are discussed. Included are examples which show that breeder breakeven introduction date could fall between the year 2000 and well beyond 2025. A principal conclusion is that the break-even introduction date is very sensitive to uncertainty in the estimate of increase in capital costs of the breeder relative to the LWR, the estimates of power demand, and the estimate of the uranium resource base available at less than $130/kg (e.g. consideration of the IUREP estimates of speculative resources which if available doubles or triples the resource base)

Use of depleted uranium silicate glass to minimize release of radionuclides from spent nuclear fuel waste packages

International Nuclear Information System (INIS)

Forsberg, C.W.

1996-01-01

A Depleted Uranium Silicate Container Backfill System (DUSCOBS) is proposed that would use small, isotopically-depleted uranium silicate glass beads as a backfill material inside repository waste packages containing spent nuclear fuel (SNF). The uranium silicate glass beads would fill the void space inside the package including the coolant channels inside SNF assemblies. Based on preliminary analysis, the following benefits have been identified. DUSCOBS improves repository waste package performance by three mechanisms. First, it reduces the radionuclide releases from SNF when water enters the waste package by creating a local uranium silicate saturated groundwater environment that suppresses (a) the dissolution and/or transformation of uranium dioxide fuel pellets and, hence, (b) the release of radionuclides incorporated into the SNF pellets. Second, the potential for long-term nuclear criticality is reduced by isotopic exchange of enriched uranium in SNF with the depleted uranium (DU) in the glass. Third, the backfill reduces radiation interactions between SNF and the local environment (package and local geology) and thus reduces generation of hydrogen, acids, and other chemicals that degrade the waste package system. Finally, DUSCOBS provides a potential method to dispose of significant quantities of excess DU from uranium enrichment plants at potential economic savings. DUSCOBS is a new concept. Consequently, the concept has not been optimized or demonstrated in laboratory experiments

Electronic trade effect of marketing channels

Directory of Open Access Journals (Sweden)

Lovreta Stipe

2009-01-01

Full Text Available E-commerce has caused many significant changes in marketing channels. Consumers had obtained multiple benefits from e-commerce. In addition, it has increased the level of competition in marketing channels. However, the focus of this paper is multichannel strategy and integration of physical (store and electronic marketing channels. E-commerce has induced dynamic development of multichannel strategy. This strategy has evolved as a consequence of multichannel consumer orientation. In developed economies, consumers are multichannel entities and active marketers aim to meet their requirements by creating multichannel offer.

Uranium enrichment plans

International Nuclear Information System (INIS)

Gagne, R.W.; Thomas, D.C.

1977-01-01

The status of existing uranium enrichment contracts in the US is reviewed and expected natural uranium requirements for existing domestic uranium enrichment contracts are evaluated. Uncertainty in natural uranium requirements associated with requirements-type and fixed-commitment type contracts is discussed along with implementation of variable tails assay

Preliminary study of the uranium potential of the Wadesboro Triassic basin, North Carolina

International Nuclear Information System (INIS)

Thayer, P.A.; Harris, W.B.

1981-11-01

This report presents results of a four-channel spectrometric survey of the Wadesboro Triassic basin and adjacent Piedmont, North and South Carolina. A total of 216 gamma-ray spectrometric measurements was taken at 165 sites in the Wadesboro Basin and at 37 sites in the adjacent Piedmont. The normal sampling density in the Wadesboro Basin is one site per 4.5 km 2 . Surface radiometric surveys reveal no anomalous radioactivity. Estimated uranium concentrations (eU) from the area are from 0.1 to 4.9 ppM. Average eU content of Triassic sandstones is 1.5 ppM, which is nearly the average for adjacent metavolcanic rocks (1.6 ppM). Granitic intrusives of the Pageland and Lilesville plutons display the highest eU concentrations in the area, averaging 3.3 ppM. The uranium/thorium ratio is consistently low throughout the area, from 0.01 to 0.54; the log uranium/log thorium ratio is from -1.11 to a maximum of 0.66. Triassic sandstones have the highest values, averaging 0.25. Granites of the Pageland and Lilesville plutons have an average uranium/thorium ratio of 0.21, and Slate Belt metavolcanic rocks average 0.15. On the basis of surface radiometric surveys and geologic studies, it is believed that sedimentary strata of the Wadesboro Basin are poor targets for further uranium exploration. This conclusion is based on the lack of many favorable characteristics associated with fluvial uranium deposits

Uranium speciation in plants

International Nuclear Information System (INIS)

Guenther, A.; Bernhard, G.; Geipel, G.; Reich, T.; Rossberg, A.; Nitsche, H.

2003-01-01

Detailed knowledge of the nature of uranium complexes formed after the uptake by plants is an essential prerequisite to describe the migration behavior of uranium in the environment. This study focuses on the determination of uranium speciation after uptake of uranium by lupine plants. For the first time, time-resolved laser-induced fluorescence spectroscopy and X-ray absorption spectroscopy were used to determine the chemical speciation of uranium in plants. Differences were detected between the uranium speciation in the initial solution (hydroponic solution and pore water of soil) and inside the lupine plants. The oxidation state of uranium did not change and remained hexavalent after it was taken up by the lupine plants. The chemical speciation of uranium was identical in the roots, shoot axis, and leaves and was independent of the uranium speciation in the uptake solution. The results indicate that the uranium is predominantly bound as uranyl(VI) phosphate to the phosphoryl groups. Dandelions and lamb's lettuce showed uranium speciation identical to lupine plants. (orig.)

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)

Hydrogeochemical modelling of an active system of uranium fixation by organic soils and sediments (Needle's Eye, Scotland)

International Nuclear Information System (INIS)

Jamet, P.; Schmitt, J.M.; Ledoux, E.; Hooker, P.J.; Escalier des Orres, P.

1993-01-01

Uranium accumulation in organic-rich sediments can be closely modelled by assuming that the dominant effect of the uranium-organic matter interaction is the direct or indirect reduction of uranyl compounds to form U(IV) minerals, especially uraninite-pitchblende. Application of this model to the Needle's Eye (Scotland) site where uranium is actively accumulating in Quaternary sediments demonstrates that uranium accumulation is both effective and rapid in environments involving shallow, organic-rich, reducing horizons. The period of uranium deposit formation at Needle's Eye is estimated to be as short as 5000 years. The transport of uranium to the site of deposition by oxidizing groundwaters and the channelling of these oxidizing uraniferous groundwaters are identified as important factors involved in the rapid accumulation of uranium. The regional hydrogeological model indicates that a fault in the area appears to act as a hydraulic screen for the uraniferous groundwaters. On one side of the fault the Quaternary sediments are well drained whilst on the other the flow of groundwater seeps out creating a major flux just at the bottom of the organic-rich layers. The local hydrogeological model shows that the groundwater flow is vertical in this area. A third significant factor in the development of these uranium accumulations is the presence of a significant nearby source of leachable primary uranium. In the case of the Needle's Eye site this is in the form of some thirty 185 ± 20 Ma, pitchblende-bearing veins. 32 refs., 10 figs., 8 tabs

Process for producing uranium oxide rich compositions from uranium hexafluoride

International Nuclear Information System (INIS)

DeHollander, W.R.; Fenimore, C.P.

1978-01-01

Conversion of gaseous uranium hexafluoride to a uranium dioxide rich composition in the presence of an active flame in a reactor defining a reaction zone is achieved by separately introducing a first gaseous reactant comprising a mixture of uranium hexafluoride and a reducing carrier gas, and a second gaseous reactant comprising an oxygen-containing gas. The reactants are separated by a shielding gas as they are introduced to the reaction zone. The shielding gas temporarily separates the gaseous reactants and temporarily prevents substantial mixing and reacting of the gaseous reactants. The flame occurring in the reaction zone is maintained away from contact with the inlet introducing the mixture to the reaction zone. After suitable treatment, the uranium dioxide rich composition is capable of being fabricated into bodies of desired configuration for loading into nuclear fuel rods. Alternatively, an oxygen-containing gas as a third gaseous reactant is introduced when the uranium hexafluoride conversion to the uranium dioxide rich composition is substantially complete. This results in oxidizing the uranium dioxide rich composition to a higher oxide of uranium with conversion of any residual reducing gas to its oxidized form

Formation conditions of uranium minerals in oxidation zone of uranium deposits

International Nuclear Information System (INIS)

Li Youzhu

2005-01-01

The paper concerns about the summary and classification of hydrothermal uranium deposit with oxidation zone. Based on the summary of observation results of forty uranium deposits located in CIS and Bulgaria which are of different sizes and industrial-genetic types, analysis on available published information concerning oxidation and uranium mineral enrichment in supergenic zone, oxidation zone classification of hydrothermal uranium had been put forward according to the general system of the exogenetic uranium concentration. (authors)

An review on geology study of carbonaceous-siliceous-pelitic rock type uranium deposit in China and the strategy for its development

International Nuclear Information System (INIS)

Zhao Fengmin

2009-01-01

Carbonaceous-siliceous-pelitic rock type uranium deposit was founded by Chinese uranium geologist, it refers to the uranium deposit hosted by non or light metamophosed carbonate,siliceous rock, pelitic rock and their intermediates. It is one of the important types uranium deposit in China. A lot of this type deposits have been discovered in China and their temporal-spatial distribution pattern and mineralization features have been basically identified, and the rich experience have layed a good foundation for the future exploration. Although the ore of this type is not favourable economically, it is still available. Because carbonaceous-siliceous-pelitic rock type uranium deposit has great resource potential, metallogenic study and exploration efforts should be projected differentially according to their economic profit so as to meet the uranium resource demand of nuclear power development in China. (authors)

Geology, geochemistry, and geophysics of the Fry Canyon uranium/copper project site, southeastern Utah - Indications of contaminant migration

Science.gov (United States)

Otton, James K.; Zielinski, Robert A.; Horton, Robert J.

2010-01-01

The Fry Canyon uranium/copper project site in San Juan County, southeastern Utah, was affected by the historical (1957-68) processing of uranium and copper-uranium ores. Relict uranium tailings and related ponds, and a large copper heap-leach pile at the site represent point sources of uranium and copper to local soils, surface water, and groundwater. This study was designed to establish the nature, extent, and pathways of contaminant dispersion. The methods used in this study are applicable at other sites of uranium mining, milling, or processing. The uranium tailings and associated ponds sit on a bench that is as much as 4.25 meters above the level of the adjacent modern channel of Fry Creek. The copper heap leach pile sits on bedrock just south of this bench. Contaminated groundwater from the ponds and other nearby sites moves downvalley and enters the modern alluvium of adjacent Fry Creek, its surface water, and also a broader, deeper paleochannel that underlies the modern creek channel and adjacent benches and stream terraces. The northern extent of contaminated groundwater is uncertain from geochemical data beyond an area of monitoring wells about 300 meters north of the site. Contaminated surface water extends to the State highway bridge. Some uranium-contaminated groundwater may also enter underlying bedrock of the Permian Cedar Mesa Sandstone along fracture zones. Four dc-resistivity surveys perpendicular to the valley trend were run across the channel and its adjacent stream terraces north of the heap-leach pile and ponds. Two surveys were done in a small field of monitoring wells and two in areas untested by borings to the north of the well field. Bedrock intercepts, salt distribution, and lithologic information from the wells and surface observations in the well field aided interpretation of the geophysical profiles there and allowed interpretation of the two profiles not tested by wells. The geophysical data for the two profiles to the north of the

Uranium industry annual 1994

International Nuclear Information System (INIS)

1995-01-01

The Uranium Industry Annual 1994 (UIA 1994) provides current statistical data on the US uranium industry's activities relating to uranium raw materials and uranium marketing during that survey year. The UIA 1994 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. It contains data for the 10-year period 1985 through 1994 as collected on the Form EIA-858, ''Uranium Industry Annual Survey.'' Data collected on the ''Uranium Industry Annual Survey'' (UIAS) provide a comprehensive statistical characterization of the industry's activities for the survey year and also include some information about industry's plans and commitments for the near-term future. Where aggregate data are presented in the UIA 1994, care has been taken to protect the confidentiality of company-specific information while still conveying accurate and complete statistical data. A feature article, ''Comparison of Uranium Mill Tailings Reclamation in the United States and Canada,'' is included in the UIA 1994. Data on uranium raw materials activities including exploration activities and expenditures, EIA-estimated 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 purchases of uranium and enrichment services, and uranium inventories, enrichment feed deliveries (actual and projected), and unfilled market requirements are shown in Chapter 2

Research on geochronology and uranium source of sandstone-hosted uranium ore-formation in major uranium-productive basins, Northern-China

International Nuclear Information System (INIS)

Xia Yuliang; Liu Hanbin; Lin Jinrong; Fan Guang; Hou Yanxian

2004-12-01

A method is developed for correcting uranium content in uranium ore samples by considering the U-Ra equilibrium coefficient, then a U-Pb isochron is drawn up. By performing the above correction ore-formation ages of sandstone-hosted uranium mineralization which may be more realistic have been obtained. The comparative research on U-Pb isotopic ages of detritic zircon in ore-hosting sandstone and zircon in intermediate-acid igneous rocks in corresponding provenance area indicates that the ore-hosting sandstone is originated from the erosion of intermediate-acid igneous rocks and the latters are the material basis for the formation of the uranium-rich sandstone beds. On the basis of the study on U-Pb isotopic system evolution of the provenance rocks and sandstones from ore-hosting series, it is verified that the uranium sources of the sandstone-hosted uranium deposit are: the intermediate-acid igneous rocks with high content of mobile uranium, and the sandstone bodies pre-concentrated uranium. (authors)

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)

Tertiary lithofacies and paleo-geographic framework and interlayer oxidation zone sandstone uranium deposits in Longjiang-Zhaozhou area

International Nuclear Information System (INIS)

Zhang Zhenqiang

2003-01-01

The main points of views for the experiment are: (1) Yi'an formation is mainly composed of limnetic facies of siltstone and fine sandstone, due to weak surface water, limited sedimentation and simple material source; (2) strengthened surface water and enormous material brought from north and west-north and enlarged sedimentation from north to south, the major deposition during Da'an period are channel facies of conglomerate and river bed facies of sandstone; (3) stronger surface water during Taikang period, led alluvial-flood plain facies brown-yellow conglomerate to develop along western margin of the basin, the channel facies of conglomerate and river bed facies of grey-green sandstone, pelitic siltstone were widely formed southward and eastward; (4) according to the lithofacies criterion for in-situ leachable sandstone uranium ore, Taikang formation is an ideal horizon, river bed facies is suitable for interlayer oxidation type uranium deposit. (author)

Control of uranium hazards - Portsmouth uranium enrichment plant

International Nuclear Information System (INIS)

Wagner, E.R.

1985-01-01

This report summarizes the Environmental, Safety and Health programs to control uranium hazards at the Portsmouth Gaseous Diffusion Plant. A description of the physical plant, the facility processes and the attendant uranium flows and effluents are provided. The hazards of uranium are discussed and the control systems are outlined. Finally, the monitoring programs are described and summaries of recent data are provided. 11 figs., 20 tabs

Correlation function measurement of uranium casting driven by tagged DT neutrons

International Nuclear Information System (INIS)

Li Jiansheng; Ye Cenming; Xie Wenxiong; Huang Po; Zeng Liheng; Jin Yu; Xie Qilin; Zhang Yi

2013-01-01

Background: In the nuclear disarmament process, the measurement and verification of uranium casting in sealed container are important to process control and treaty implementation. It is a difficult and hot problem to verify uranium casting in a sealed metal container, due to the weak intensity of neutron and gamma rays of uranium. Purpose: We want to measure the correlation functions of different casting in uranium casting verifications. Methods: Two BC501 scintillation detectors are placed outside the tagged neutron cone and in opposite position. The α detector forms the first channel pulse signal, while the two BC501 scintillation detectors form the second and third channel pulse signals. Those three pulsed time series are recorded by high speed acquisition system. The correlation functions between these signals are calculated by the time series. Results: Putting the two BC501 detectors into the tagged neutron cone, the time of flight for the 14 MeV neutron is measured. The FWHM in TOF spectrum is 2.0 ns. Putting the two BC501 detectors outside the tagged neutron cone, the correlation functions measured by high speed acquisition system and MCA are consistent. The spontaneous neutron decay constants of the castings are measured by γ rays. The decay constant of 6.5 kg Pb component is 184 μs -1 . The decay constants of 4 kg and 15 kg HEU casting are 210 μs -1 and 128 μs -1 , respectively. The correlation functions C 12 (τ), C 13 (τ) and C 23 (τ) are acquired. In C 12 (C), the γ ray peak coming from the inelastic reaction of 14-MeV neutrons with the casting is 5.0 ns before the neutron peak of fission chain. This time difference can estimate the casting position in container. The integrations of the C 12 (τ), C 13 (τ) and C 23 (τ) increase with the casting mass. The C 23 (τ) values of Pb component and DU casting are far less than the values of HEU casting. The C 23 (τ) integration of Pb component is 3.0% comparing with 15-kg HEU casting, while the

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 Industry. Annual 1984

International Nuclear Information System (INIS)

Lawrence, M.S.S.

1985-01-01

This report provides a statistical description of activities of the US uranium industry during 1984 and includes a statistical profile of the status of the industry at the end of 1984. It is based on the results of an Energy Information Administration (EIA) survey entitled ''Uranium Industry Annual Survey'' (Form EIA-858). The principal findings of the survey are summarized under two headings - Uranium Raw Materials Activities and Uranium Marketing Activities. The first heading covers exploration and development, uranium resources, mine and mill production, and employment. The second heading covers uranium deliveries and delivery commitments, uranium prices, foreign trade in uranium, inventories, and other marketing activities. 32 figs., 48 tabs

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

DUSCOBS - a depleted-uranium silicate backfill for transport, storage, and disposal of spent nuclear fuel

International Nuclear Information System (INIS)

Forsberg, C.W.; Pope, R.B.; Ashline, R.C.; DeHart, M.D.; Childs, K.W.; Tang, J.S.

1995-01-01

A Depleted Uranium Silicate COntainer Backfill System (DUSCOBS) is proposed that would use small, isotopically-depleted uranium silicate glass beads as a backfill material inside storage, transport, and repository waste packages containing spent nuclear fuel (SNF). The uranium silicate glass beads would fill all void space inside the package including the coolant channels inside SNF assemblies. Based on preliminary analysis, the following benefits have been identified. DUSCOBS improves repository waste package performance by three mechanisms. First, it reduces the radionuclide releases from SNF when water enters the waste package by creating a local uranium silicate saturated groundwater environment that suppresses (1) the dissolution and/or transformation of uranium dioxide fuel pellets and, hence, (2) the release of radionuclides incorporated into the SNF pellets. Second, the potential for long-term nuclear criticality is reduced by isotopic exchange of enriched uranium in SNF with the depleted uranium (DU) in the glass. Third, the backfill reduces radiation interactions between SNF and the local environment (package and local geology) and thus reduces generation of hydrogen, acids, and other chemicals that degrade the waste package system. In addition, the DUSCOBS improves the integrity of the package by acting as a packing material and ensures criticality control for the package during SNF storage and transport. Finally, DUSCOBS provides a potential method to dispose of significant quantities of excess DU from uranium enrichment plants at potential economic savings. DUSCOBS is a new concept. Consequently, the concept has not been optimized or demonstrated in laboratory experiments