Uranium-mill appraisal program

International Nuclear Information System (INIS)

Everett, R.J.; Cain, C.L.

1982-08-01

The results of special team appraisals at NRC-licensed uranium mills in the period May to November 1981 are reported. Since the Three Mile Island accident, NRC management has instituted a program of special team appraisals of radiation protection programs at certain NRC-licensed facilities. These appraisals were designed to identify weaknesses and strengths in NRC-licensed programs, including those areas not covered by explicit regulatory requirements. The regulatory requirements related to occupational radiation protection and environmental monitoring at uranium mills have been extensively upgraded in the past few years. In addition, there was some NRC staff concern with respect to the effectiveness of NRC licensing and inspection programs. In response to this concern and to changes in mill requirements, the NRC staff recommended that team appraisals be conducted at mills to determine the adequacy of mill programs, the effectiveness of the new requirements, and mill management implementation of programs and requirements. This report describes the appraisal scope and methodology as well as summary findings and conclusions. Significant weaknesses identified during the mill appraisals are discussed as well as recommendations for improvements in uranium mill programs and mill licensing and inspection

Geochemical orientation survey of stream sediment, stream water, and ground water near uranium prospects, Monticello area, New York. National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

Rose, A.W.; Smith, A.T.; Wesolowski, D.

1982-08-01

A detailed geochemical test survey has been conducted in a 570 sq km area around six small copper-uranium prospects in sandstones of the Devonian Catskill Formation near Monticello in southern New York state. This report summarizes and interprets the data for about 500 stream sediment samples, 500 stream water samples, and 500 ground water samples, each analyzed for 40 to 50 elements. The groundwater samples furnish distinctive anomalies for uranium, helium, radon, and copper near the mineralized localities, but the samples must be segregated into aquifers in order to obtain continuous well-defined anomalies. Two zones of uranium-rich water (1 to 16 parts per billion) can be recognized on cross sections; the upper zone extends through the known occurrences. The anomalies in uranium and helium are strongest in the deeper parts of the aquifers and are diluted in samples from shallow wells. In stream water, copper and uranium are slightly anomalous, as in an ore factor derived from factor analysis. Ratios of copper, uranium, and zinc to conductivity improve the resolution of anomalies. In stream sediment, extractable uranium, copper, niobium, vanadium, and an ore factor furnish weak anomalies, and ratios of uranium and copper to zinc improve the definition of anomalies. The uranium/thorium ratio is not helpful. Published analyses of rock samples from the nearby stratigraphic section show distinct anomalies in the zone containing the copper-uranium occurrences. This report is being issued without the normal detailed technical and copy editing, to make the data available to the public before the end of the National Uranium Reconnaissance Evaluation program

Geochemical orientation survey of stream sediment, stream water, and ground water near uranium prospects, Monticello area, New York. National Uranium Resource Evaluation Program

Energy Technology Data Exchange (ETDEWEB)

Rose, A. W.; Smith, A. T.; Wesolowski, D.

1982-08-01

A detailed geochemical test survey has been conducted in a 570 sq km area around six small copper-uranium prospects in sandstones of the Devonian Catskill Formation near Monticello in southern New York state. This report summarizes and interprets the data for about 500 stream sediment samples, 500 stream water samples, and 500 ground water samples, each analyzed for 40 to 50 elements. The groundwater samples furnish distinctive anomalies for uranium, helium, radon, and copper near the mineralized localities, but the samples must be segregated into aquifers in order to obtain continuous well-defined anomalies. Two zones of uranium-rich water (1 to 16 parts per billion) can be recognized on cross sections; the upper zone extends through the known occurrences. The anomalies in uranium and helium are strongest in the deeper parts of the aquifers and are diluted in samples from shallow wells. In stream water, copper and uranium are slightly anomalous, as in an ore factor derived from factor analysis. Ratios of copper, uranium, and zinc to conductivity improve the resolution of anomalies. In stream sediment, extractable uranium, copper, niobium, vanadium, and an ore factor furnish weak anomalies, and ratios of uranium and copper to zinc improve the definition of anomalies. The uranium/thorium ratio is not helpful. Published analyses of rock samples from the nearby stratigraphic section show distinct anomalies in the zone containing the copper-uranium occurrences. This report is being issued without the normal detailed technical and copy editing, to make the data available to the public before the end of the National Uranium Reconnaissance Evaluation program.

Uranium removal from soils: An overview from the Uranium in Soils Integrated Demonstration program

International Nuclear Information System (INIS)

Francis, C.W.; Brainard, J.R.; York, D.A.; Chaiko, D.J.; Matthern, G.

1994-01-01

An integrated approach to remove uranium from uranium-contaminated soils is being conducted by four of the US Department of Energy national laboratories. In this approach, managed through the Uranium in Soils Integrated Demonstration program at the Fernald Environmental Management Project, Fernald, Ohio, these laboratories are developing processes that selectively remove uranium from soil without seriously degrading the soil's physicochemical characteristics or generating waste that is difficult to manage or dispose of. These processes include traditional uranium extractions that use carbonate as well as some nontraditional extraction techniques that use citric acid and complex organic chelating agents such as naturally occurring microbial siderophores. A bench-scale engineering design for heap leaching; a process that uses carbonate leaching media shows that >90% of the uranium can be removed from the Fernald soils. Other work involves amending soils with cultures of sulfur and ferrous oxidizing microbes or cultures of fungi whose role is to generate mycorrhiza that excrete strong complexers for uranium. Aqueous biphasic extraction, a physical separation technology, is also being evaluated because of its ability to segregate fine particulate, a fundamental requirement for soils containing high levels of silt and clay. Interactions among participating scientists have produced some significant progress not only in evaluating the feasibility of uranium removal but also in understanding some important technical aspects of the task

National uranium resource evaluation: Clifton Quadrangle, Arizona and New Mexico

International Nuclear Information System (INIS)

White, D.L.; Foster, M.

1982-05-01

The Clifton Quadrangle, Arizona and New Mexico, was evaluated to identify environments and delineate areas favorable for uranium deposits. The evaluation used criteria formulated for the National Uranium Resource Evaluation program. Evidence for the evaluation was based on surface studies, hydrogeochemical and stream-sediment reconnaissance, and aerial radiometric surveys. The quadrangle encompasses parts of three physiographic provinces: the Colorado Plateau, the transition zone, and the Basin and Range. The one environment determined, during the present study, to be favorable for uranium deposits is the Whitewater Creek member of the Cooney tuff, which is favorable for magmatic-hydrothermal uranium deposits on the west side of the Bursum caldera. No other areas were favorable for uranium deposits in sandstone, limestone, volcanogenic, igneous, or metamorphic environments. The subsurface is unevaluated because of lack of information, as are areas where access is a constraint

National uranium resource evaluation program. Hydrogeochemical and stream sediment reconnaissance basic data for Oklahoma City NTMS Quadrangle, Oklahoma. Uranium resource evaluation project

International Nuclear Information System (INIS)

1978-01-01

Field and laboratory data are presented for 812 groundwater samples and 847 stream sediment samples. Statistical and areal distributions of uranium and other possibly uranium-related variables are displayed. A generalized geologic map of the survey area is provided, and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed. Based on the results from groundwater sampling, the most promising formations for potential uranium mineralization in the quadrangle are the Permian Bison, Purcell-Salt Plains-Kingman, Fairmont, Dog Creek, Chickasha, Duncan, and Cedar Hills Formations. These units are characterized by relatively high average concentrations of uranium, conductivity, arsenic, calcium, lithium, molybdenum, and sulfate. In addition, groundwaters from the Pennsylvanian Oscar Formation are characterized by values above the 85th percentile for uranium, conductivity, the uranium/sulfate ratio, arsenic, and vanadium. Results of stream sediment sampling indicate that the most promising formations for potential uranium mineralization include the same Permian Formation as indicated by groundwater sampling (Bison, Purcell-Salt Plains-Kingman, Fairmont, Dog-Creek, Chickasha, Duncan, and Cedar Hill Formations) in an area where these formations crop out north of the North Canadian River. Stream sediment samples from this area are characterized by concentrations above the 85th percentile for uranium, thorium, arsenic, lithium, manganese, and vanadium

National uranium resource evaluation: Lemmon quadrangle, South Dakota and North Dakota

International Nuclear Information System (INIS)

Sewell, J.M.; Pickering, L.A.

1982-06-01

The Lemmon Quadrangle was evaluated to identify and delineate geologic environments favorable for the occurrence of uranium deposits using criteria developed for the National Uranium Resource Evaluation program. Surface studies included investigation of uranium occurrences, general surface reconnaissance, and detailed rock sampling in selected areas. In addition, followup studies were conducted on carborne spectrometric, aerial radiometric, and hydrogeochemical and stream-sediment surveys. Subsurface investigations included examination of geophysical well logs and ground-water geochemical data. These investigations indicate environments favorable for sandstone-type uranium deposits in the Upper Cretaceous strata and lignite-type deposits in the Paleocene strata. Environments unfavorable for uranium deposits include Tertiary sandstones and Jurassic and Cretaceous strata, exclusive of the Upper Cretaceous sandstones

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

National uranium resource evaluation: Nogales Quadrangle, Arizona

International Nuclear Information System (INIS)

Luning, R.H.; Brouillard, L.A.

1982-04-01

Literature research, surface geologic investigations, rock sampling, and radiometric surveys were conducted in the Nogales Quadrangle, Arizona, to identify environments and to delineate areas favorable for uranium deposits according to criteria formulated during the National Uranium Resource Evaluation program. The studies were augmented by aerial radiometric and hydrogeochemical and stream-sediment surveys. No favorable environments were identified. Environments that do display favorable characteristics include magmatic-hydrothermal and authigenic environments in Precambrian and Jurassic intrusives, as well as in certain Mesozoic and Cenozoic igneous and sedimentary rocks

National Uranium Resource Evaluation: Baker Quadrangle, Oregon and Idaho

International Nuclear Information System (INIS)

Bernardi, M.L.; Robins, J.W.

1982-05-01

The Baker Quadrangle, Oregon, and Idaho, was evaluated to identify areas containing geologic environments favorable for uranium deposits. The criteria used was developed for the National Uranium Resource Evaluation program. Stream-sediment reconnaissance and detailed surface studies were augmented by subsurface-data interpretion and an aerial radiometric survey. Results indicate that lower Pliocene sedimentary rocks in the Lower Powder River Valley-Virtue Flat basin are favorable characteristics, they remain unevaluated because of lack of subsurface data. Tertiary sandstones, possibly present at depth in the Long and Cascade Valleys, also remain unevaluated due to lack of subsurface data. All remaining environments in the Baker Quadrangle are unfavorable for all classes of uranium deposits

Background report for the uranium-mill-tailings-sites remedial-action program

International Nuclear Information System (INIS)

1981-04-01

The Uranium Mill Tailings Radiation Control Act of 1978, Public Law 95-604, mandates remedial action responsibilities to the Department of Energy for designated inactive uranium processing sites. To comply with the mandates of the Act, a program to survey and evaluate the radiological conditions at inactive uranium processing sites and at vicinity properties containing residual radioactive material derived from the sites is being conducted; the Remedial Action Program Office, Office of the Assistant Secretary for Nuclear Energy is implementing remedial actions at these processing sites. This report provides a brief history of the program, a description of the scope of the program, and a set of site-specific summaries for the 22 locations specified in the Act and three additional locations designated in response to Federal Register notices issued on August 17 and September 5, 1979. It is designed to be a quick source of background information on sites covered by the implementation program for Public Law 95-604

National uranium resource evaluation, NURE 1979: annual activity report

International Nuclear Information System (INIS)

1980-03-01

NURE is a DOE-directed program with the major goal of establishing reliable and timely comprehensive estimates of the uranium resources of the nation. To develop and compile geologic, geophysical, and other information which will contribute to assessing the distribution and magnitude of uranium resources and to determine areas favorable for the occurrence of uranium in the United States, NURE has been organized into the following elements: (1) quadrangle evaluation; (2) aerial radiometric reconnaissance; (3) subsurface investigations; (4) hydrogeochemical and stream-sediment reconnaissance; (5) geologic studies; (6) technology applications; and (7) information dissemination. The extensive effort now under way on each of these NURE program elements will result in a systematic collection and compilation of data which will be culminating in a comprehensive report covering certain priority areas of the United States. This report summarizes the technical activities undertaken during 1979 to support this program

Environmental monitoring program design for uranium refining and conversion operations

International Nuclear Information System (INIS)

1984-08-01

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

National Uranium Resource Evaluation Program. Hydrogeochemical and stream sediment reconnaissance basic data for Beeville NTMS Quadrangle, Texas. Uranium resource evaluation project

Energy Technology Data Exchange (ETDEWEB)

1979-10-31

Results of a reconnaissance geochemical survey of the Beeville Quadrangle, Texas are reported. Field and laboratory data are presented for 373 groundwater and 364 stream sediment samples. Statistical and areal distributions of uranium and possible uranium-related variables are displayed. A generalized geologic map of the survey area is provided, and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed. The groundwater data indicate that the northwestern corner of the quadrangle is the most favorable for potential uranium mineralization. Favorability is indicated by high uranium concentrations; high arsenic, molybdenum, and vanadium concentrations; and proximity and similar geologic setting to the mines of the Karnes County mining district. Other areas that appear favorable are an area in Bee and Refugio Counties and the northeastern part of the quadrangle. Both areas have water chemistry similar to the Karnes County area, but the northeastern area does not have high concentrations of pathfinder elements. The stream sediment data indicate that the northeastern corner of the quadrangle is the most favorable for potential mineralization, but agricultural practices and mineralogy of the outcropping Beaumont Formation may indicate a false anomaly. The northwestern corner of the quadrangle is considered favorable because of its proximity to the known uranium deposits, but the data do not seem to support this.

National Uranium Resource Evaluation Program. Hydrogeochemical and stream sediment reconnaissance basic data for Beeville NTMS Quadrangle, Texas. Uranium resource evaluation project

International Nuclear Information System (INIS)

1979-01-01

Results of a reconnaissance geochemical survey of the Beeville Quadrangle, Texas are reported. Field and laboratory data are presented for 373 groundwater and 364 stream sediment samples. Statistical and areal distributions of uranium and possible uranium-related variables are displayed. A generalized geologic map of the survey area is provided, and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed. The groundwater data indicate that the northwestern corner of the quadrangle is the most favorable for potential uranium mineralization. Favorability is indicated by high uranium concentrations; high arsenic, molybdenum, and vanadium concentrations; and proximity and similar geologic setting to the mines of the Karnes County mining district. Other areas that appear favorable are an area in Bee and Refugio Counties and the northeastern part of the quadrangle. Both areas have water chemistry similar to the Karnes County area, but the northeastern area does not have high concentrations of pathfinder elements. The stream sediment data indicate that the northeastern corner of the quadrangle is the most favorable for potential mineralization, but agricultural practices and mineralogy of the outcropping Beaumont Formation may indicate a false anomaly. The northwestern corner of the quadrangle is considered favorable because of its proximity to the known uranium deposits, but the data do not seem to support this

National logging program for the National Uranium Resource Evaluation. Final report

International Nuclear Information System (INIS)

The Mineral Engineering Division (MED) of High Life Helicopters, Inc., operated from May, 1979, through August, 1981, as a subcontractor to the Department of Energy (DOE) to acquire downhole geophysical log information in support of the National Uranium Resource Evaluation program (NURE). MED acquired downhole geophysical log information in 26 1 0 x 2 0 NTMS quadrangles in Colorado, Montana, Nebraska, North Dakota, South Dakota, and Wyoming. MED obtained the log information by gaining permission to log oil and gas wells, water wells, and coal exploration holes. Actual geophysical logging was subcontracted to Century Geophysical Corporation. After logging of each well and completed, MED submitted the log information and other pertinent data to Bendix Field Engineering Corporation (BFEC) for evaluation. MED collected over 700,000 feet of geophysical logs. Additionally, MED conducted a search of log libraries for existing log data for twelve of the quadrangles included in the program. It should be noted that ERTEC, Inc. conducted geophysical logging and a log library search to five quadrangles in Wyoming. These areas were later assigned to MED. The location of all wells logged by MED and ERTEC and the location of other log data is shown on the enclosed maps. Detailed information that pertains to each well is provided following each map

10 CFR 760.1 - Uranium leases on lands controlled by DOE. (Domestic Uranium Program Circular No. 760.1, formerly...

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Uranium leases on lands controlled by DOE. (Domestic Uranium Program Circular No. 760.1, formerly (AEC) Domestic Uranium Program Circular 8, 10 CFR 60.8). 760.1 Section 760.1 Energy DEPARTMENT OF ENERGY DOMESTIC URANIUM PROGRAM § 760.1 Uranium leases on lands...

US Geological Survey uranium and thorium resource assessment and exploration research program, fiscal year 1981

International Nuclear Information System (INIS)

Offield, T.W.

1980-01-01

The US Geological Survey (USGS) uranium-thorium program is continuing to emphasize multidisciplinary studies to define the settings and habitats of uranium deposits and to elucidate the processes by which the ore deposits formed. As with the uranium scene generally, some uncertainty characterizes the program's transition from FY 1980 to FY 1981. As of the beginning of the new fiscal year, a cut of 15% in base funding of the USGS uranium program has been effected by Congress. Such a cut parallels the major curtailment of the NURE program. The USGS in FY 1980 completed almost all of its commitment to the NURE program quadrangle-evaluation work, and only a relatively modest continuing involvement in the NURE world-class and intermediate-grade studies remains for FY 1981. Objectives and program scope, noteworthy results of FY 1980 research, and program activities for FY 1981 are presented in this report

Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Zoller, J.N.; Rosen, R.S.; Holliday, M.A. [and others

1995-06-30

With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management Program consists of three major program elements: Engineering Analysis, Cost Analysis, and an Environmental Impact Statement. This Technology Assessment Report is the first part of the Engineering Analysis Project, and assesses recommendations from interested persons, industry, and Government agencies for potential uses for the depleted uranium hexafluoride stored at the gaseous diffusion plants in Paducah, Kentucky, and Portsmouth, Ohio, and at the Oak Ridge Reservation in Tennessee. Technologies that could facilitate the long-term management of this material are also assessed. The purpose of the Technology Assessment Report is to present the results of the evaluation of these recommendations. Department management will decide which recommendations will receive further study and evaluation. These Appendices contain the Federal Register Notice, comments on evaluation factors, independent technical reviewers resumes, independent technical reviewers manual, and technology information packages.

Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 1

International Nuclear Information System (INIS)

Zoller, J.N.; Rosen, R.S.; Holliday, M.A.

1995-01-01

With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management Program consists of three major program elements: Engineering Analysis, Cost Analysis, and an Environmental Impact Statement. This Technology Assessment Report is the first part of the Engineering Analysis Project, and assesses recommendations from interested persons, industry, and Government agencies for potential uses for the depleted uranium hexafluoride stored at the gaseous diffusion plants in Paducah, Kentucky, and Portsmouth, Ohio, and at the Oak Ridge Reservation in Tennessee. Technologies that could facilitate the long-term management of this material are also assessed. The purpose of the Technology Assessment Report is to present the results of the evaluation of these recommendations. Department management will decide which recommendations will receive further study and evaluation. These Appendices contain the Federal Register Notice, comments on evaluation factors, independent technical reviewers resumes, independent technical reviewers manual, and technology information packages

National Uranium Resource Evaluation: Providence Quadrangle, Connecticut, Rhode Island, and Massachusetts

International Nuclear Information System (INIS)

Zollinger, R.C.; Blauvelt, R.P.; Chew, R.T. III.

1982-09-01

The Providence Quadrangle, Connecticut, Rhode Island, and Massachusetts, was evaluated to a depth of 1500 m to identify environments and delineate areas favorable for uranium deposits. Criteria for this evaluation were developed by the National Uranium Resource Evaluation program. Environments were recognized after literature research, surface and subsurface geologic reconnaissance, and examination of known uranium occurrences and aeroradioactivity anomalies. Environments favorable for authigenic uranium deposits were found in the Quincy and Cowesett Granites. An environment favorable for contact-metasomatic deposits is in and around the borders of the Narragansett Pier Granite where it intrudes the Pennsylvanian sediments of the Narragansett Basin. An environment favorable for authigenic deposits in metamorphic rocks is in a migmatite on the eastern edge of the Scituate Granite Gneiss batholith. Environments favorable for contact-metasomatic deposits occur at the contacts between many of the granitic rocks and metamorphic rocks of the Blackstone Series. Results of this study also indicate environments favorable for sandstone-type uranium deposits are present in the rocks of the Narragansett Basin. Environments unfavorable for uranium deposits in the quadrangle include all granites not classified as favorable and the metamorphic rocks of eastern Connecticut. Glacial deposits and Cretaceous-Tertiary sediments remain unevaluated

Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 2

International Nuclear Information System (INIS)

Zoller, J.N.; Rosen, R.S.; Holliday, M.A.

1995-01-01

With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management Program consists of three major program elements: Engineering Analysis, Cost Analysis, and an Environmental Impact Statement. This Technology Assessment Report is the first part of the Engineering Analysis Project, and assesses recommendations from interested persons, industry, and Government agencies for potential uses for the depleted uranium hexafluoride stored at the gaseous diffusion plants in Paducah, Kentucky, and Portsmouth, Ohio, and at the Oak Ridge Reservation in Tennessee. Technologies that could facilitate the long-term management of this material are also assessed. The purpose of the Technology Assessment Report is to present the results of the evaluation of these recommendations. Department management will decide which recommendations will receive further study and evaluation

Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Zoller, J.N.; Rosen, R.S.; Holliday, M.A. [and others

1995-06-30

With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management Program consists of three major program elements: Engineering Analysis, Cost Analysis, and an Environmental Impact Statement. This Technology Assessment Report is the first part of the Engineering Analysis Project, and assesses recommendations from interested persons, industry, and Government agencies for potential uses for the depleted uranium hexafluoride stored at the gaseous diffusion plants in Paducah, Kentucky, and Portsmouth, Ohio, and at the Oak Ridge Reservation in Tennessee. Technologies that could facilitate the long-term management of this material are also assessed. The purpose of the Technology Assessment Report is to present the results of the evaluation of these recommendations. Department management will decide which recommendations will receive further study and evaluation.

Hydrogeochemical and stream sediment reconnaissance of the National Uranium Resource Evaluation Program. Progress report, January--March 1978

Energy Technology Data Exchange (ETDEWEB)

Weaver, T.A.; Bunker, M.E.; Hansel, J.M. Jr.

1978-10-01

The modifications to the Los Alamos Scientific Laboratory (LASL) Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) program, necessary to incorporate the expansion and revision of the overall HSSR program as required by the Department of Energy, have been completed. To date, approximately 57% of the total area assigned to the LASL in the Rocky Mountain region and Alaska has been sampled and plans are well under way to sample an additional 28% during FY 78. Contracts have been let to complete the sampling of the LASL area in the lower states and bids to sample an additional 33% of Alaska are being evaluated. Twenty reports (2 in press and 18 in preparation) are presently scheduled to be open filed within six months, reporting uranium data only for 18 complete quadrangles and multielement data for 11 complete quadrangles. In addition, data releases are being prepared to open file the uranium data from portions of 13 quadrangles that are now outside the LASL reporting boundary but which had been sampled by the LASL prior to the establishment of the new boundary in October 1977. By the end of the quarter, all multielement analysis systems were operational. Water samples from 7780 locations and sediment samples from 4170 locations were analyzed for uranium. Samples from approximately 6500 locations were analyzed by one or more of the multielement methods.

Hydrogeochemical and stream sediment reconnaissance of the National Uranium Resource Evaluation Program. Progress report, January--March 1978

International Nuclear Information System (INIS)

Weaver, T.A.; Bunker, M.E.; Hansel, J.M. Jr.

1978-10-01

The modifications to the Los Alamos Scientific Laboratory (LASL) Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) program, necessary to incorporate the expansion and revision of the overall HSSR program as required by the Department of Energy, have been completed. To date, approximately 57% of the total area assigned to the LASL in the Rocky Mountain region and Alaska has been sampled and plans are well under way to sample an additional 28% during FY 78. Contracts have been let to complete the sampling of the LASL area in the lower states and bids to sample an additional 33% of Alaska are being evaluated. Twenty reports (2 in press and 18 in preparation) are presently scheduled to be open filed within six months, reporting uranium data only for 18 complete quadrangles and multielement data for 11 complete quadrangles. In addition, data releases are being prepared to open file the uranium data from portions of 13 quadrangles that are now outside the LASL reporting boundary but which had been sampled by the LASL prior to the establishment of the new boundary in October 1977. By the end of the quarter, all multielement analysis systems were operational. Water samples from 7780 locations and sediment samples from 4170 locations were analyzed for uranium. Samples from approximately 6500 locations were analyzed by one or more of the multielement methods

Data release on the Salton Sea Quadrangle, California and Arizona. National Uranium Resource Evaluation

International Nuclear Information System (INIS)

Chew, R.T. III; Antrim, D.R.

1982-10-01

The purpose of the National Uranium Resource Evaluation (NURE) was to delineate and evaluate all geologic environments favorable for the occurrence of uranium deposits. A favorable environment was defined as having the potential to contain an occurrence of at least 100 tons of U 3 O 8 at an average grade of not less than 0.01% U 3 O 8 . In the Salton Sea Quadrangle, reported uranium occurrences were evaluated, and geologic environments thought to be favorable were examined. This report includes the field data collected during that work and a summary of the quadrangle geology and uranium favorability. This is the final report to be prepared on this quadrangle under the NURE program

Evaluation of uranium resources in Antarctica

International Nuclear Information System (INIS)

Zeller, E.J.; Dreschhoff, G.A.M.

1980-01-01

The continent of Antarctica comprises roughly nine per cent of the total land surface of the earth and is the only large land area that has been left almost totally unexplored for uranium resources. In 1976 the first systematic uranium resource evaluation, entitled Antarctica International Radiometric Survey, was started as a part of the US Antarctic Research Program. This project was staffed jointly by scientists from the University of Kansas and the Bundesanstalt fuer Geowissenschaften und Rohstoffe of the Federal Republic of Germany. The survey has continued for three antarctic field seasons and an extension of operations for the next four years has been approved. Two areas in the Transantarctic Mountains and one part of Marie Byrd Land have been surveyed by airborne gamma-ray spectrometric methods. The work that has been conducted demonstrates clearly that radiometric surveys can be performed successfully under the rigorous climatic conditions in Antarctica, and that significant and reproducible data can be obtained. So far no substantial concentrations of uranium have been detected but deposits of thorium minerals have been found. (author)

Uranium resources evaluation model as an exploration tool

International Nuclear Information System (INIS)

Ruzicka, V.

1976-01-01

Evaluation of uranium resources, as conducted by the Uranium Resources Evaluation Section of the Geological Survey of Canada, comprises operations analogous with those performed during the preparatory stages of uranium exploration. The uranium resources evaluation model, simulating the estimation process, can be divided into four steps. The first step includes definition of major areas and ''unit subdivisions'' for which geological data are gathered, coded, computerized and retrieved. Selection of these areas and ''unit subdivisions'' is based on a preliminary appraisal of their favourability for uranium mineralization. The second step includes analyses of the data, definition of factors controlling uranium minearlization, classification of uranium occurrences into genetic types, and final delineation of favourable areas; this step corresponds to the selection of targets for uranium exploration. The third step includes geological field work; it is equivalent to geological reconnaissance in exploration. The fourth step comprises computation of resources; the preliminary evaluation techniques in the exploration are, as a rule, analogous with the simplest methods employed in the resource evaluation. The uranium resources evaluation model can be conceptually applied for decision-making during exploration or for formulation of exploration strategy using the quantified data as weighting factors. (author)

Evaluation of Uranium Measurements in Water by Various Methods - 13571

Energy Technology Data Exchange (ETDEWEB)

Tucker, Brian J. [Shaw Environmental and Infrastructure Group, 150 Royall Street, Canton, MA (United States); Workman, Stephen M. [ALS Laboratory Group, Environmental Division, 225 Commerce Drive, Fort Collins, CO 80524 (United States)

2013-07-01

In December 2000, EPA amended its drinking water regulations for radionuclides by adding a Maximum Contaminant Level (MCL) for uranium (so called MCL Rule)[1] of 30 micrograms per liter (μg/L). The MCL Rule also included MCL goals of zero for uranium and other radionuclides. Many radioactively contaminated sites must test uranium in wastewater and groundwater to comply with the MCL rule as well as local publicly owned treatment works discharge limitations. This paper addresses the relative sensitivity, accuracy, precision, cost and comparability of two EPA-approved methods for detection of total uranium: inductively plasma/mass spectrometry (ICP-MS) and alpha spectrometry. Both methods are capable of measuring the individual uranium isotopes U-234, U- 235, and U-238 and both methods have been deemed acceptable by EPA. However, the U-238 is by far the primary contributor to the mass-based ICP-MS measurement, especially for naturally-occurring uranium, which contains 99.2745% U-238. An evaluation shall be performed relative to the regulatory requirement promulgated by EPA in December 2000. Data will be garnered from various client sample results measured by ALS Laboratory in Fort Collins, CO. Data shall include method detection limits (MDL), minimum detectable activities (MDA), means and trends in laboratory control sample results, performance evaluation data for all methods, and replicate results. In addition, a comparison will be made of sample analyses results obtained from both alpha spectrometry and the screening method Kinetic Phosphorescence Analysis (KPA) performed at the U.S. Army Corps of Engineers (USACE) FUSRAP Maywood Laboratory (UFML). Many uranium measurements occur in laboratories that only perform radiological analysis. This work is important because it shows that uranium can be measured in radiological as well as stable chemistry laboratories and it provides several criteria as a basis for comparison of two uranium test methods. This data will

Evaluation of Uranium Measurements in Water by Various Methods - 13571

International Nuclear Information System (INIS)

Tucker, Brian J.; Workman, Stephen M.

2013-01-01

In December 2000, EPA amended its drinking water regulations for radionuclides by adding a Maximum Contaminant Level (MCL) for uranium (so called MCL Rule)[1] of 30 micrograms per liter (μg/L). The MCL Rule also included MCL goals of zero for uranium and other radionuclides. Many radioactively contaminated sites must test uranium in wastewater and groundwater to comply with the MCL rule as well as local publicly owned treatment works discharge limitations. This paper addresses the relative sensitivity, accuracy, precision, cost and comparability of two EPA-approved methods for detection of total uranium: inductively plasma/mass spectrometry (ICP-MS) and alpha spectrometry. Both methods are capable of measuring the individual uranium isotopes U-234, U- 235, and U-238 and both methods have been deemed acceptable by EPA. However, the U-238 is by far the primary contributor to the mass-based ICP-MS measurement, especially for naturally-occurring uranium, which contains 99.2745% U-238. An evaluation shall be performed relative to the regulatory requirement promulgated by EPA in December 2000. Data will be garnered from various client sample results measured by ALS Laboratory in Fort Collins, CO. Data shall include method detection limits (MDL), minimum detectable activities (MDA), means and trends in laboratory control sample results, performance evaluation data for all methods, and replicate results. In addition, a comparison will be made of sample analyses results obtained from both alpha spectrometry and the screening method Kinetic Phosphorescence Analysis (KPA) performed at the U.S. Army Corps of Engineers (USACE) FUSRAP Maywood Laboratory (UFML). Many uranium measurements occur in laboratories that only perform radiological analysis. This work is important because it shows that uranium can be measured in radiological as well as stable chemistry laboratories and it provides several criteria as a basis for comparison of two uranium test methods. This data will

Evaluation of flexible membrane liners as long-term barriers for uranium mill tailings

International Nuclear Information System (INIS)

1984-07-01

The National Uranium Tailings Program has commissioned a study to evaluate flexible membrane liners (geomembranes) as long-term barriers for Canadian uranium mill tailings. This study reviews the common liner type and addresses flexible liners (polymeric membranes and asphalt) in detail. Liner fabrication, design, installation, and performance are reviewed. Conceptual designs are presented for basins to accommodate 20 years accumulation of uranium tailings from mills in Elliot Lake and southeastern Athabasca. Nine polymeric and three asphalt liner types have been considered with respect to the physical and chemical environment in the uranium producing areas of Canada. All materials indicate good chemical resistance to uranium wastes but are subject to installation problems

National Uranium Resource Evaluation, Tonopah quadrangle, Nevada

International Nuclear Information System (INIS)

Hurley, B.W.; Parker, D.P.

1982-04-01

The Tonopah Quadrangle, Nevada, was evaluated using National Uranium Resource Evaluation criteria to identify and delineate areas favorable for uranium deposits. Investigations included reconnaissance and detailed surface geologic and radiometric studies, geochemical sampling and evaluation, analysis and ground-truth followup of aerial radiometric and hydrogeochemical and stream-sediment reconnaissance data, and subsurface data evaluation. The results of these investigations indicate environments favorable for hydroallogenic uranium deposits in Miocene lacustrine sediments of the Big Smoky Valley west of Tonopah. The northern portion of the Toquima granitic pluton is favorable for authigenic uranium deposits. Environments considered unfavorable for uranium deposits include Quaternary sediments; intermediate and mafic volcanic and metavolcanic rocks; Mesozoic, Paleozoic, and Precambrian sedimentary and metasedimentary rocks; those plutonic rocks not included within favorable areas; and those felsic volcanic rocks not within the Northumberland and Mount Jefferson calderas

Uranium storage bed accident hazards evaluation

International Nuclear Information System (INIS)

Longhurst, G.R.; Shmayda, W.T.

1989-01-01

To properly assess hazards and risks associated with the use of uranium beds as tritium storage devices in fusion reactor systems, it is necessary to understand the consequences occurring in the event of an accident. Accidents involving uranium beds are postulated, and the possible results are considered. A research program to more fully and accurately understand those results has been initiated involving the Idaho National Engineering Laboratory and Ontario Hydro. The plan and objectives of that program are presented. 11 refs., 1 tab

Uranium storage bed accident hazards evaluation

International Nuclear Information System (INIS)

Longhurst, G.R.; Shmayda, W.T.

1989-10-01

To properly assess hazards and risks associated with the use of uranium beds as tritium storage devices in fusion reactor systems, it is necessary to understand the consequences occurring in the event of an accident. Accidents involving uranium beds are postulated, and the possible results are considered. A research program to more fully and accurately understand those results has been initiated involving the Idaho National Engineering Laboratory and Ontario Hydro. The plan and objectives of that program are presented. 11 refs., 1 tab

Liner evaluation for uranium mill tailings. Final report

International Nuclear Information System (INIS)

Buelt, J.L.

1983-09-01

The Liner Evaluation for Uranium Mill Tailings Program was conducted to evaluate the need for and performance of prospective lining materials for the long-term management of inactive uranium mill tailings piles. On the basis of program results, two materials have been identified: natural foundation soil amended with 10% sodium bentonite; catalytic airblown asphalt membrane. The study showed that, for most situations, calcareous soils typical of Western US sites adequately buffer tailings leachates and prevent groundwater contamination without additional liner materials or amendments. Although mathematical modeling of disposal sites is recommended on a site-specific basis, there appears to be no reason to expect significant infiltration through the cover for most Western sites. The major water source through the tailings would be groundwater movement at sites with shallow groundwater tables. Even so column leaching studies showed that contaminant source terms were reduced to near maximum contaminant levels (MCL's) for drinking water within one or two pore volumes; thus, a limited source term for groundwater contamination exists. At sites where significant groundwater movement or infiltration is expected and the tailings leachates are alkaline, however, the sodium bentonite or asphalt membrane may be necessary

National uranium resource evaluation, Hot Springs Quadrangle, South Dakota and Nebraska

International Nuclear Information System (INIS)

Truesdell, D.B.; Daddazio, P.L.; Martin, T.S.

1982-06-01

The Hot Springs Quadrangle, South Dakota and Nebraska, was evaluated to a depth of 1500 m to identify environments and delineate areas favorable for the occurrence of uranium deposits. The evaluation used criteria developed by the National Uranium Resource Evaluation program. Surface reconnaissance was conducted using a portable scintillometer and a gamma spectrometer. Geochemical sampling was carried out in all geologic environments accessible within the quadrangle. Additional investigations included the followup of aerial radiometric and hydrogeochemical anomalies and a subsurface study. Environments favorable for sandstone-type deposits occur in the Inyan Kara Group and Chadron Member of the White River Group. Environments favorable for marine black-shale deposits occur in the Hayden Member of the Minnelusa Formation. A small area of the Harney Peak Granite is favorable for authigenic deposits. Environments considered unfavorable for uranium deposits are the Precambrian granitic and metasedimentary rocks and Paleozoic, Mesozoic, and Tertiary sedimentary rocks other than those previously mentioned

Data analysis and management for the Uranium Resource Evaluation Project

International Nuclear Information System (INIS)

Kane, V.E.

1980-01-01

The Department of Energy has funded a large data collection effort with the purpose of determining the US uranium resources. This Uranium Resource Evaluation (URE) Project required a large data management effort which involved collection, retrieval, processing, display, and analysis of large volumes of data. Many of the characteristics of this data processing system are relevant to other applications, particularly where routine processing involves analyses for input into numerous technical reports. The URE Project computing system has a modular program structure which has enabled a straightforward interface with both special and general graphics and analysis packages such as SAS, BMDP, and SURFACE II. Other topics include cost-effective computing, data quality, report quality computer output, and test versus production program development

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

Improved uranium-utilization program, Phase I. First semiannual report, September 1979-March 1980

International Nuclear Information System (INIS)

Hopkins, G.C.

1980-11-01

The Improved Uranium Utilization Program includes a Phase I evaluation of BWR design alternatives which have potential to reduce uranium ore requirements in once-through fuel cycles. The Phase I project is evaluating the alternatives in detail, including considerations of reliability, performance, manufacturing, safety and economics; is establishing implementation development requirements, costs and schedules; is selecting the most promising alternatives; and is developing detailed plans for Phase II projects for implementation. Emphasis is being placed on developing practical alternatives which can be demonstrated at the earliest possible date in existing operating BWR nuclear power stations. Priority is being given to alternatives which have the maximum payoff, measured by reduction of the nation's uranium resource requirements, on the shortest schedule. Alternatives included in current evaluations are: improved refueling and control rod pattern optimization, spectral shift, extended burnup, reduction in gadolinia residual, axial blanket optimization, reconstitution, and combinations of these alternatives

National Uranium Resource Evaluation: Okanogan Quadrangle, Washington

International Nuclear Information System (INIS)

Bernardi, M.L.; Powell, L.K.; Wicklund, M.A.

1982-06-01

The Okanogan Quadrangle, Washington, was evaluated to identify and delineate areas containing environments favorable for the occurrence of uranium deposits using criteria developed for the National Uranium Resource Evaluation program. Reconnaissance and detailed surface studies were augmented by aerial radiometric surveys and hydrogeochemical and stream-sediment reconnaissance studies. The results of the investigations indicate six environments favorable for uranium deposits. They are unclassified, anatectic, allogenic, and contact-metasomatic deposits in Late Precambrian and (or) Early Paleozoic mantling metamorphic core-complex rocks of the Kettle gneiss dome; magmatic-hydrothermal deposits in the Gold Creek pluton, the Magee Creek pluton, the Wellington Peak pluton, and the Midnite Mine pluton, all located in the southeast quadrant of the quadrangle; magmatic-hydrothermal allogenic deposits in Late Paleozoic and (or) Early Mesozoic black shales in the Castle Mountain area; allogenic deposits in Early Paleozoic metasedimentary rocks in the Harvey Creek area and in Late Precambrian metasedimentary rocks in the Blue Mountain area; and sandstone deposits in Eocene sedimentary rocks possibly present in the Enterprise Valley. Seven geologic units are considered unfavorable for uranium deposits. They are all the remaining metamorphic core-complex rocks, Precambrian metasedimentary rocks,Tertiary sedimentary and volcanic rocks, and all Pleistocene and Recent deposits; and, excluding those rocks in the unevaluated areas, include all the remaining plutonic rocks, Paleozoic miogeoclinical rocks, and Upper Paleozoic and Mesozoic eugeosynclinal rocks. Three areas, the Cobey Creek-Frosty Creek area, the Oregon City Ridge-Wilmont Creek area, and the area underlain by the Middle Cambrian Metaline Formation and its stratigraphic equivalents may possibly be favorable but are unevaluated due to lack of data

Summary report on reprocessing evaluation of selected inactive uranium mill tailings sites

International Nuclear Information System (INIS)

1983-09-01

Sandia National Laboratories has been assisting the Department of Energy in the Uranium Mill Tailings Remedial Actions Program (UMTRAP) the purpose of which is to implement the provisions of Title I of Public Law 95-604, ''Uranium Mill Tailings Radiation Control Act of 1978.'' As part of this program, there was a need to evaluate the mineral concentration of the residual radioactive materials at some of the designated processing sites to determine whether mineral recovery would be practicable. Accordingly, Sandia contracted Mountain States Research and Development (MSRD), a division of Mountain States Mineral Enterprises, to drill, sample, and test tailings at 12 sites to evaluate the cost of and the revenue that could be derived from mineral recovery. UMTRAP related environmental and engineering sampling and support activities were performed in conjunction with the MSRD operations. This summary report presents a brief description of the various activities in the program and of the data and information obtained and summarizes the results. 8 refs., 9 tabs

National uranium resource evaluation: Sheridan Quadrangle, Wyoming and Montana

International Nuclear Information System (INIS)

Damp, J.N.; Jennings, M.D.

1982-04-01

The Sheridan Quadrangle of north-central Wyoming was evaluated for uranium favorability according to specific criteria of the National Uranium Resource Evaluation program. Procedures consisted of geologic and radiometric surveys; rock, water, and sediment sampling; studying well logs; and reviewing the literature. Five favorable environments were identified. These include portions of Eocene Wasatch and Upper Cretaceous Lance sandstones of the Powder River Basin and Lower Cretaceous Pryor sandstones of the Bighorn Basin. Unfavorable environments include all Precambrian, Cambrian, Ordovician, Permian, Triassic, and Middle Jurassic rocks; the Cretaceous Thermopolis, Mowry, Cody, Meeteetse, and Bearpaw Formations; the Upper Jurassic Sundance and Morrison, the Cretaceous Frontier, Meseverde, Lance, and the Paleocene Fort Union and Eocene Willwood Formations of the Bighorn Basin; the Wasatch Formation of the Powder River Basin, excluding two favorable areas and all Oligocene and Miocene rocks. Remaining rocks are unevaluated

National uranium resource evaluation: Sheridan Quadrangle, Wyoming and Montana

Energy Technology Data Exchange (ETDEWEB)

Damp, J N; Jennings, M D

1982-04-01

The Sheridan Quadrangle of north-central Wyoming was evaluated for uranium favorability according to specific criteria of the National Uranium Resource Evaluation program. Procedures consisted of geologic and radiometric surveys; rock, water, and sediment sampling; studying well logs; and reviewing the literature. Five favorable environments were identified. These include portions of Eocene Wasatch and Upper Cretaceous Lance sandstones of the Powder River Basin and Lower Cretaceous Pryor sandstones of the Bighorn Basin. Unfavorable environments include all Precambrian, Cambrian, Ordovician, Permian, Triassic, and Middle Jurassic rocks; the Cretaceous Thermopolis, Mowry, Cody, Meeteetse, and Bearpaw Formations; the Upper Jurassic Sundance and Morrison, the Cretaceous Frontier, Meseverde, Lance, and the Paleocene Fort Union and Eocene Willwood Formations of the Bighorn Basin; the Wasatch Formation of the Powder River Basin, excluding two favorable areas and all Oligocene and Miocene rocks. Remaining rocks are unevaluated.

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

National/international R and D programs on uranium mill tailings

International Nuclear Information System (INIS)

Hamel, P.E.

1981-05-01

The mining and milling of uranium ores results in the production of large quantities of wastes containing low concentrations of radionuclides such as uranium, thorium, radium, radon and their daughter products. The current concern of the regulatory authorities is with the extent of the problems and the disposal methods that must be required now to ensure that an acceptable level of protection is maintained in the long term. This concern is the subject of a number of R and D programs. In Canada, the Technical Planning Group on Uranium Tailings was established to review ongoing activities and to plan a research program on the management of wastes after the mine and mill have shut down. The Group has completed its review and a report containing its conclusions and recommendations for a proposed national R and D program has been prepared. Included is a proposal for a centralized organizational structure for the coordination and managment of the total program which is to be supported jointly by the federal government, two (Ontario, Saskatchewan) provincial governments, and uranium producers. At the international level, the Nuclear Energy Agency originated, in 1979, a program to study the extent of the long-term problems of uranium mill tailings, and to develop an internationally acceptable methodology for making rational decisions regarding their long-term management taking into account the ICRP principles and system of dose limitation

Nuclear criticality safety parameter evaluation for uranium metallic alloy

Energy Technology Data Exchange (ETDEWEB)

Sanchez, Andrea; Abe, Alfredo, E-mail: andreasdpz@hotmail.com, E-mail: abye@uol.com.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Centro de Energia Nuclear

2013-07-01

Nuclear criticality safety during fuel fabrication process, transport and storage of fissile and fissionable materials requires criticality safety analysis. Normally the analysis involves computer calculations and safety parameters determination. There are many different Criticality Safety Handbooks where such safety parameters for several different fissile mixtures are presented. The handbooks have been published to provide data and safety principles for the design, safety evaluation and licensing of operations, transport and storage of fissile and fissionable materials. The data often comprise not only critical values, but also subcritical limits and safe parameters obtained for specific conditions using criticality safety calculation codes such as SCALE system. Although many data are available for different fissile and fissionable materials, compounds, mixtures, different enrichment level, there are a lack of information regarding a uranium metal alloy, specifically UMo and UNbZr. Nowadays uranium metal alloy as fuel have been investigated under RERTR program as possible candidate to became a new fuel for research reactor due to high density. This work aim to evaluate a set of criticality safety parameters for uranium metal alloy using SCALE system and MCNP Monte Carlo code. (author)

National Uranium Resource Evaluation, Tularosa Quadrangle, New Mexico

International Nuclear Information System (INIS)

Berry, V.P.; Nagy, P.A.; Spreng, W.C.; Barnes, C.W.; Smouse, D.

1981-12-01

Uranium favorability of the Tularosa Quadrangle, New Mexico, was evaluated to a depth of 1500 m using National Uranium Resource Evaluation criteria. Uranium occurrences reported in the literature were located, sampled, and described in detail. Areas of anomalous radioactivity, interpreted from an aerial radiometric survey, and geochemical anomalies, interpreted from hydrogeochemical and stream-sediment reconnaissance, were also investigated. Additionally, several hundred rock samples were studied in thin section, and supplemental geochemical analyses of rock and water samples were completed. Fluorometric analyses were completed for samples from the Black Range Primitive Area to augment previously available geochemical data. Subsurface favorability was evaluated using gamma-ray logs and descriptive logs of sample cuttings. One area of uranium favorability was delineated, based on the data made available from this study. This area is the Nogal Canyon cauldron margin zone. Within the zone, characterized by concentric and radial fractures, resurgent doming, ring-dike volcanism, and intracauldron sedimentation, uranium conentration is confined to magmatic-hydrothermal and volcanogenic uranium deposits

Savannah River Laboratory semiannual report, April-September 1979. Hydrogeochemical and stream sediment reconnaissance: National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

1979-10-01

This report summarizes the accomplishments, status, and program of the Savannah River Laboratory (SRL) contribution to the National Uranium Resource Evaluation (NURE) program. SRL has accepted responsibility for Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) of 1,500,000 square miles in 30 eastern and 7 far-western states. The report is a progress report covering the period April 1979 through September 1979. SRL efforts in the following areas are discussed: reconnaissance and detailed studies in geological programs; management, analysis, and interpretation of analytical and field data; reporting of HSSR results; sample preparation methods; and neutron activation analysis and other analytical techniques. Appendix A to the report summarizes the SRL-NURE production of the April 1979-September 1979 period and the program plans for the first half of FY-1980. Page-scale maps are included that show the status of completed sampling, analysis, and data reports placed on open file

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

International Nuclear Information System (INIS)

1977-08-01

Before 1959 a private individual (Mr. Rene Abularach) is reported to have made an airborne radiometric survey of the Sierra de las Minas and Sierra Madre Ranges. Although many anomalies were detected by this survey, none were verified in the ground survey followup, despite apparently adequate flight control. In 1968 a United Nations Special Fund Mineral Survey Project completed over 1,000 km of carborne radiometric survey with geiger counter readings at 500 m intervals. No anomalies were detected, but background radioactivity for several formations and geologic environments was established. In 1969 the Guatemalan government solicited the IAEA for technical assistance In conducting a preliminary uranium favorability study designed to formulate recommendations for a national radioactive ore prospecting program. A carborne radiometric survey was made of environments theoretically favorable for uranium deposition, with spot geological and radiometric examinations being .conducted in the more favorable areas. All Important mining regions of Guatemala except the leterites and the ultrabasics were visited. No evidence of a uranium province was observed 1n these field investigations and the recommendation was made that the government not embark on a more detailed national prospecting program at that time. At the time of completion of the IAEA-Guatemalan government (GOG) reconnaissance program in 1971, no uranium reserves or resources were known. More recent information on uranium occurrences and resources 1n Guatemala does not appear to be available. Information on more recent uranium reconnaissance than that undertaken during 1971 IAEA-GOG study is lacking. However, in more recent years the country's mineral potential has been generally evaluated with the aid of the UN and ICAITI (Central American Research Institute for Industry). Except for quarry materials, the state owns all minerals. The state has priority on purchase of any mineral production needed for the country

Speculative resources of uranium. A review of International Uranium Resources Evaluation Project (IUREP) estimates 1982-1983

International Nuclear Information System (INIS)

1983-01-01

On a country by country basis the International Uranium Resources Evaluation Project (IUREP) estimates 1982-1983 are reviewed. Information provided includes exploration work, airborne survey, radiometric survey, gamma-ray spectrometric survey, estimate of speculative resources, uranium occurrences, uranium deposits, uranium mineralization, agreements for uranium exploration, feasibilities studies, geological classification of resources, proposed revised resource range, production estimate of uranium

National Uranium Resource Evaluation: intermediate-grade uranium resource assessment project for part of the Maybell District, Sand Wash Basin, Colorado

International Nuclear Information System (INIS)

Goodknight, C.S.

1983-04-01

Intermediate-grade uranium resources in the Miocene Browns Park Formation were assessed for part of the Maybell district in the Sand Wash Basin, Colorado, as part of the National Uranium Resource Evaluation program conducted by Bendix Field Engineering Corporation for the US Department of Energy. Two sites, each 2 mi 2 (5 km 2 ) in size, in the district were selected to be assessed. Site selection was based on evaluation of geologic, geophysical, and geochemical data that were collected from a larger project area known to contain uranium enrichment. The assessment of the sites was accomplished primarily by drilling 19 holes through the Browns Park Formation and by using the geophysical and geochemical data from those holes and from a larger number of industry-drilled holes. Analytical results of samples from uranium prospects, mainly along faults in the sites, were also used for the assessment. Data from surface samples and from drill-hole samples and logs of the site south of Lay Creek indicate that no intermediate-grade uranium resources are present. However, similar data from the site north of Lay Creek verify that approximately 25 million lb (11.2 million kg) of intermediate-grade uranium resources may be present. This assessment assumes that an average uranium-enriched thickness of 10 ft (3 m) at a grade of 0.017% U 3 O 8 is present in at least two thirds of the northern site. Uranium enrichment in this site occurs mainly in the lower 150 ft (45 m) of the Browns Park Formation in fine- to medium-grained sandstone that contains abundant clay in its matrix. Facies variations within the Browns Park preclude correlation of individual beds or zones of uranium enrichment between closely spaced drill holes

National Uranium Resource Evaluation: Durango Quadrangle, Colorado

International Nuclear Information System (INIS)

Theis, N.J.; Madson, M.E.; Rosenlund, G.C.; Reinhart, W.R.; Gardner, H.A.

1981-06-01

The Durango Quadrangle (2 0 ), Colorado, was evaluated using National Uranium Resource Evaluation criteria to determine environments favorable for uranium deposits. General reconnaissance, geologic and radiometric investigations, was augmented by detailed surface examination and radiometric and geochemical studies in selected areas. Eight areas favorable for uranium deposits were delineated. Favorable geologic environments include roscoelite-type vanadium-uranium deposits in the Placerville and Barlow Creek-Hermosa Creek districts, sandstone uranium deposits along Hermosa Creek, and vein uranium deposits in the Precambrian rocks of the Needle Mountains area and in the Paleozoic rocks of the Tuckerville and Piedra River Canyon areas. The major portions of the San Juan volcanic field, the San Juan Basin, and the San Luis Basin within the quadrangle were judged unfavorable. Due to lack of information, the roscoelite belt below 1000 ft (300 m), the Eolus Granite below 0.5 mi (0.8 km), and the Lake City caldera are unevaluated. The Precambrian Y melasyenite of Ute Creek and the Animas Formation within the Southern Ute Indian Reservation are unevaluated due to lack of access

World nuclear-fuel procurement: relationships between uranium and enrichment markets. Final report. International energies studies program

International Nuclear Information System (INIS)

Neff, T.L.

1982-03-01

This article explores the relationships between international uranium and enrichment markets under current contracting and equity arrangements and in comparison with actual feed requirements for existing and committed reactors. We begin with an overview of the world situation, examining current and prospective conditions. We then consider enrichment and uranium supply and demand situations of the three consumer nations outside the United States with the largest nuclear programs: France, Japan, and the Federal Republic of Germany. We conclude with an evaluation of likely directions of change in the coupled markets for uranium and enrichment services

Uranium Mill Tailings Remedial Action Project Vicinity Property Program

International Nuclear Information System (INIS)

Little, L.E.; Potter, R.F.; Arpke, P.W.

1988-01-01

The Department of Energy Uranium Mill Tailings Remedial Action (UMTRA) Grand Junction Project Vicinity Property Program is a $165 million program for the removal and disposal of uranium mill tailings that were used in the construction of approximately 4,000 residences, commercial buildings, and institutional facilities in the City of Grand Junction and surrounding Mesa County, Colorado. This paper discusses the UMTRA Vicinity Property Program and the economic benefits of this program for the City of Grand Junction and Mesa County, Colorado. The Bureau of Reclamation Economic Assessment Model (BREAM) was used to estimate the increases in employment and increases in personal income in Mesa County that result from the Vicinity Property Program. The effects of program-related changes in income and taxable expenditures on local and state tax revenue are also presented

Extraction of uranium from seawater: evaluation of uranium resources and plant siting

International Nuclear Information System (INIS)

Rodman, M.R.; Gordon, L.I.; Chen, A.C.T.

1979-02-01

This report deals with the evaluation of U.S. coastal waters as a uranium resource and with the selection of a suitable site for construction of a large-scale plant for uranium extraction. Evaluation of the resource revealed that although the concentration of uranium is quite low, about 3.3 ppB in seawater of average oceanic salinity, the amount present in the total volume of the oceans is very great, some 4.5 billion metric tons. Of this, perhaps only that uranium contained in the upper 100 meters or so of the surface well-mixed layer should be considered accessible for recovery, some 160 million tonnes. The study indicated that open ocean seawater acquired for the purpose of uranium extraction would be a more favorable resource than rivers entering the sea, cooling water of power plants, or the feed or effluent streams of existing plants producing other products such as magnesium, bromine, or potable and/or agricultural water from seawater. Various considerations led to the selection of a site for a pumped seawater coastal plant at a coastal location. Puerto Yabucoa, Puerto Rico was selected. Recommendations are given for further studies. 21 figures, 8 tables

Extraction of uranium from seawater: evaluation of uranium resources and plant siting

Energy Technology Data Exchange (ETDEWEB)

Rodman, M.R.; Gordon, L.I.; Chen, A.C.T.

1979-02-01

This report deals with the evaluation of U.S. coastal waters as a uranium resource and with the selection of a suitable site for construction of a large-scale plant for uranium extraction. Evaluation of the resource revealed that although the concentration of uranium is quite low, about 3.3 ppB in seawater of average oceanic salinity, the amount present in the total volume of the oceans is very great, some 4.5 billion metric tons. Of this, perhaps only that uranium contained in the upper 100 meters or so of the surface well-mixed layer should be considered accessible for recovery, some 160 million tonnes. The study indicated that open ocean seawater acquired for the purpose of uranium extraction would be a more favorable resource than rivers entering the sea, cooling water of power plants, or the feed or effluent streams of existing plants producing other products such as magnesium, bromine, or potable and/or agricultural water from seawater. Various considerations led to the selection of a site for a pumped seawater coastal plant at a coastal location. Puerto Yabucoa, Puerto Rico was selected. Recommendations are given for further studies. 21 figures, 8 tables.

Demonstration and evaluation of solid state photomultiplier tube for uranium exploration instrumentation. National uranium resources evaluation. Final report

International Nuclear Information System (INIS)

Polichar, R.M.

1982-06-01

The purpose of this program has been to evaluate the recently developed solid state photomultiplier tube (SSPMT) technology as a potential improvment to future uranium exploration instrumentation. To this end, six SSPMTs have been constructed and evaluated in a manner similar to that of conventional phototubes. Special regard has been placed on the measurement of pulse height resolution and the factors that affect it in tube design and manufacture. The tubes were subjected to a number of tests similar to those performed on conventional photomultiplier tubes. The results indicate that good, high-resolution spectra can be obtained from the tubes and that they behave generally in a predictable manner. They exhibited a linear gain increase with applied potential. They show only slight dependence of performance with applied potential. Their sensitivity is, for the most part, uniform and predictable. However, several characteristics were found that were not predictable. These include a general drop in measured quantum efficiency, a worsening resolution with operation, and a bump in the sensitivity curve corresponding to the shape of the projected dimension of the anode. The SSPMT remains an attractive new technology in gamma-ray spectroscopy, and promises to make significant improvements in the area of uranium exploration instrumentation. 16 figures, 5 tables

Foreign research reactor uranium supply program: The Y-12 national security complex process

International Nuclear Information System (INIS)

Nelson, T.; Eddy, B.G.

2010-01-01

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

Nuclear characteristics evaluation for Kyoto University Research Reactor with low-enriched uranium core

Energy Technology Data Exchange (ETDEWEB)

Nakajima, Ken; Unesaki, Hironobu [Kyoto University Research Reactor Institute, Kumatori-cho Sennan-gun Osaka (Japan)

2008-07-01

A project to convert the fuel of Kyoto University Research Reactor (KUR) from highly enriched uranium (HEU) to low-enriched uranium (LEU) is in progress as a part of RERTR program. Prior to the operation of LEU core, the nuclear characteristics of the core have been evaluated to confirm the safety operation. In the evaluation, nuclear parameters, such as the excess reactivity, shut down margin control rod worth, reactivity coefficients, were calculated, and they were compared with the safety limits. The results of evaluation show that the LEU core is able to satisfy the safety requirements for operation, i.e. all the parameters satisfy the safety limits. Consequently, it was confirmed that the LEU fuel core has the proper nuclear characteristics for the safety operation. (authors)

Evaluation and analysis of geological condition of in-situ fragmentation leaching uranium

International Nuclear Information System (INIS)

Yang Jianming; Tan Kaixuan; Huang Xiaonai

2003-01-01

The ore geological condition, hydrogeological condition, engineering geological condition and technological mineralogical character of in-situ fragmentation leaching uranium are analyzed, and it is considered that the implementation of in-situ fragmentation leaching uranium technology is decided by different geological factor. Previously prospecting and geological condition evaluation of uranium ore is based on traditional mining method. If in-situ fragmentation leaching uranium method is adopted, one must re-evaluate previously prospected deposits before they are mined, or one must evaluate new prospecting deposits according to geological conditions of in-situ fragmentation leaching uranium method. The feasibility evaluation method of uranium deposit by in-situ fragmentation leaching uranium put forward by B. N. Mociniets is introducd, and it is considered that B. N. Mociniets method has guidable significance for geological condition evaluation before uranium deposits are mined. A feasibility study is done by applying B. N. Mociniets method to a uranium deposit. (authors)

Health physics program for the Edgemont Uranium Mill decommissioning project

International Nuclear Information System (INIS)

Polehn, J.L.; Wallace, R.G.; Reed, R.P.; Wilson, G.T.

1986-01-01

The Tennessee Valley Authority (TVA) is actively involved in decommissioning a uranium mill located near the town of Edgemont, South Dakota. The Edgemont Mill Decommissioning Project, which is unique in many respects, will involve dismantlement of the old inactive mill building and excavation and transportation of several million tons of uranium mill tailings to a permanent disposal site. To ensure that workers are adequately protected from radiation exposure during decommissioning operations, a health physics program appropriate for the decommissioning situation was developed. The Edgemont Mill Decommissioning Project Health Physics Manual (HPM) gives the programmatic requirements for worker radiation protection. The requirements of the HPM are implemented by means of detailed onsite operating procedures. The Edgemont project health physics program was developed using currently available regulations and guidance for an operating uranium mill with appropriate modifications for decommissioning. This paper discusses the development, implementation, and documentation of that program

National Uranium Resource Evaluation: Spartanburg Quadrangle, South Carolina and North Carolina

International Nuclear Information System (INIS)

Schot, E.H.; Galipeau, J.M.

1980-11-01

The Spartanburg Quadrangle, South Carolina and North Carolina, was evaluated for uranium favorability using National Uranium Resource Evaluation criteria. The evaluation included the study and analysis of published and collected geologic, geophysical, and geochemical data from subsurface, surface, and aerial studies. Five environments are favorable for uranium deposits. The Triassic Wadesboro Basin has ground waters with anomalously high uranium concentrations and uranium-to-conductivity ratios. The Upper Cretaceous Tuscaloosa-Middendorf Formation is near a uranium source and has sediments favorable for uranium deposition. The contact-metamorphic aureoles associated with the Liberty Hill-Kershaw and Winnsboro-Rion plutonic complexes are close to uranium sources and contain the reductants (sulfides, graphite) necessary for precipitation. The East Fork area in the Charlotte Belt has ground waters with uranium concentrations 4 to 132 times the mean concentration reported for the surrounding Piedmont area. Unfavorable environments include the Catawba Granite, the area west of the Winnsboro-Rion complex, gold-quartz veins, the vermiculite district, and the Western Monazite Belt

Comprehensive evaluation on rationality of ventilation system in uranium underground mine

International Nuclear Information System (INIS)

Zhou Qinglin

1991-01-01

A new method is presented for evaluating rationality of uranium mine ventilation system using fuzzy mathematics. The mathematical models for fuzzy comprehensive evaluation are introduced. Based on practice of uranium mine ventilation, the evaluation factors and the evaluation procedure are given. Using the presented method, a comprehensive evaluation was carried out for ventilation systems before and after regulation in Fuzhou Uranium Mine

Search for uranium: a perspective

International Nuclear Information System (INIS)

Grutt, E.W. Jr.

1975-01-01

The history of uranium mining in the USA is reviewed. It is postulated that some two million tons of U 3 O 8 will be needed to provide fuel for US nuclear power plants through the year 2000. World resources of U ores are reviewed. The functions of the ERDA National Uranium Resources Evaluation Program (NURE), including aerial surveying, in relation to the assessment of potential uranium reserves in the USA are discussed. The scope of ERDA research and development programs are briefly reviewed. (U.S.)

Analysis of AEC-ERDA-DOE and USGS uranium program data: disipline reviews and summary reports. Final report

International Nuclear Information System (INIS)

1980-03-01

Most of the literature dealing with the econmic geology and exploitation of uranium deposits in the United States has been published since 1950, primarily by the Department of Energy (DOE) and its predecessor agencies. The limited availability of much of these data, combined with the inexperience of many electric power utilities and, to some extent, mining companies with regard to uranium exploration, frequently resulted in the inauguration of ill-conceived and duplicative efforts. To assess the value of this literature in light of present knowledge, a systematic review of those publications dealing with uranium exploration, and the economic geology, evaluation, and exploitation of uranium deposits was undertaken. Matrix reports (summaries) have been prepared for each of the nearly 2500 documents reviewed. This material is available through the computerized literature search services of the Oak Ridge National Laboratory. In addition, thirteen discipline reviews and summary reports were compiled within the broad fields of uraium geology and mining engineering frm which any advances in knowledge would have the greatest impact on the future discovery and exploitation of uranium deposits. A final chapter presents a critique of the DOE National Uranium Resource Evaluation Program, as judged by members of the uranium industry. A two-part report summarizes and analyzes the results of this investigation. Part 1 is primarily an introduction to the various types of uranium deposits, the geologic and structural environments in which they occur, and the mechanisms for their emplacement. Part 2 considers the various techniques used to explore, evaluate, and exploit uranium deposits. The report is intended to serve as a major source of basic information concerning previous uranium-related studies for all those involved with the search for and utilization of uranium

High-uranium-loaded U3O8--Al fuel element development program

International Nuclear Information System (INIS)

Martin, M.M.

1978-01-01

The High-Uranium-Loaded U 3 O 8 --Al Fuel Development Program supports Argonne National Laboratory efforts to develop high-uranium-density research and test reactor fuel to accommodate use of low-uranium enrichment. The goal is to fuel most research and test reactors with uranium of less than 20% enrichment for the purpose of lowering the potential for diversion of highly-enriched material for nonpeaceful usages

National uranium resource evaluation, Rapid City Quadrangle, South Dakota

International Nuclear Information System (INIS)

Nanna, R.F.; Milton, E.J.

1982-04-01

The Rapid City (1 0 x 2 0 ) Quadrangle, South Dakota, was evaluated for environments favorble for uranium deposits to a depth of 1500 m. Criteria used were those of the National Uranium Resource Evaluation. Field reconnaissance involved the use of hand-held scintillometers to investigate uranium occurrences reported in the literature and anomalies in aerial radiometric surveys, and geochemical samples of stream sediments and well waters. Gamma-ray logs were used to define the favorable environments in the subsurface. Environments favorable for sandstone-type uranium deposits occur in the Inyan Kara Group, the Fox Hills Sandstone, and the Hell Creek Formation. Environments considered unfavorable for uranium deposits include all Precambrian, Paleozoic, Mesozoic, and Tertiary rocks other than those identified as favorable

Depleted uranium disposal options evaluation

International Nuclear Information System (INIS)

Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D.

1994-05-01

The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ''waste,'' but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity

Supplement to hydrogeochemical and stream-sediment reconnaissance basic data reports K/UR-445 through K/UR-457 [GJBX-165(82) through GJBX-177(82)]. National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

1982-01-01

The objective of the Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) Program was to provide information to be used in accomplishing the overall National Uranium Resource Evaluation (NURE) Program objectives. This was accomplished by a reconnaissance of surface water, groundwater, stream sediment, and lake sediment. The survey was conducted by Los Alamos National Laboratory, Oak Ridge Gaseous Diffusion Plant, and Savannah River Laboratory. The samples in the reports were collected by SRL and analyzed by the Uranium Resource Evaluation Project in Oak Ridge, Tennessee. Laboratory analyses were completed in August 1982. The following quadrangles located in the states of California, Nevada, Oregon, Arizona, Maine, Washington, and South Carolina are covered in this report: Adel, Bangor, Bath, Boise, Challis, Caliente, Death Valley, Elko, Ely, Fresno, Hailey, Idaho Falls, Jordan Valley, Lund, Mariposa, Phoenix, San Luis Obispo, Sacramento, Santa Cruz, Twin Falls, and Vya

Uranium concentrations in natural waters, South Park, Colorado. [Part of National Uranium Resource Evaluation program

Energy Technology Data Exchange (ETDEWEB)

Sharp, R.R. Jr.; Aamodt, P.L.

1976-08-01

During the summer of 1975, 464 water samples from 149 locations in South Park, Colorado, were taken for the Los Alamos Scientific Laboratory in order to test the field sampling and analytical methodologies proposed for the NURE Hydrogeochemical and Stream Sediment Reconnaissance for uranium in the Rocky Mountain states and Alaska. The study showed, in the South Park area, that the analytical results do not vary significantly between samples which were untreated, filtered and acidified, filtered only, or acidified only. Furthermore, the analytical methods of fluorometry and delayed-neutron counting, as developed at the LASL for the reconnaissance work, provide fast, adequately precise, and complementary procedures for analyzing a broad range of uranium in natural waters. The data generated using this methodology does appear to identify uraniferous areas, and when applied using sound geochemical, geological, and hydrological principles, should prove a valuable tool in reconnaissance surveying to delineate new districts or areas of interest for uranium exploration.

Geology and mineral resources of the Florence, Beaufort, Rocky Mount, and Norfolk 10 x 20 NTMS quadrangles. National Uranium Resource Evaluation program

International Nuclear Information System (INIS)

Harris, W.B.

1982-08-01

This document provides geologic and mineral resources data for previously-issued Savannah River Laboratory hydrogeochemical and stream sediment reports of the Beaufort, Florence, Norfolk, and Rocky Mount 1 0 x 2 0 National Topographic Map Series quadrangles in the southeastern United States. This report is issued in draft form, without detailed technical and copy editing. This was done to make the report available to the public before the end of the National Uranium Resource Evaluation program

Evaluation of economical at a uranium enrichment demonstration plant

International Nuclear Information System (INIS)

Sugitsue, Noritake

2001-01-01

In this report, the economy of technical achievement apply in the uranium enrichment demonstration plant is evaluated. From the evaluation, it can be concluded that the expected purpose was achieved because there was a definite economic prospect to commercial plant. The benefit analysis of thirteen years operation of the uranium enrichment demonstration plant also provides a financial aspect of the uranium enrichment business. Therefore, the performance, price and reliability of the centrifuge is an important factor in the uranium enrichment business. And the continuous development of a centrifuge while considering balance with the development cost is necessary for the business in the future. (author)

Uranium enrichment activities: the SILVA program

International Nuclear Information System (INIS)

Guyot, J.; Cazalet, J.; Camarcat, N.; Figuet, J.

1994-01-01

Through its commitment to a nuclear electricity generation policy, France holds today a specific position in the uranium enrichment market thanks to the modern multinational EURODIF gaseous diffusion plant. France has, altogether, a long-term goal in developing SILVA, a laser uranium enrichment process, based on the selective photo-ionization of U-235. After reviewing the fundamentals of SILVA (the laser system with copper vapor lasers and dye lasers and the separator system), a description of the general organization of the R and D program is provided going through basic research, subsystems assessment, production demonstrations and simulations (with the LACAN code), plant design and economics. The general schedule of SILVA is outlined, leading to the possible construction of a commercial plant. 7 figs., 11 refs

Fitting a three-parameter lognormal distribution with applications to hydrogeochemical data from the National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

Kane, V.E.

1979-10-01

The standard maximum likelihood and moment estimation procedures are shown to have some undesirable characteristics for estimating the parameters in a three-parameter lognormal distribution. A class of goodness-of-fit estimators is found which provides a useful alternative to the standard methods. The class of goodness-of-fit tests considered include the Shapiro-Wilk and Shapiro-Francia tests which reduce to a weighted linear combination of the order statistics that can be maximized in estimation problems. The weighted-order statistic estimators are compared to the standard procedures in Monte Carlo simulations. Bias and robustness of the procedures are examined and example data sets analyzed including geochemical data from the National Uranium Resource Evaluation Program

Structuring a risk-based bioassay program for uranium usage in university laboratories

Science.gov (United States)

Dawson, Johnne Talia

Bioassay programs are integral in a radiation safety program. They are used as a method of determining whether individuals working with radioactive material have been exposed and have received a resulting dose. For radionuclides that are not found in nature, determining an exposure is straightforward. However, for a naturally occurring radionuclide like uranium, it is not as straightforward to determine whether a dose is the result of an occupational exposure. The purpose of this project is to address this issue within the University of Nevada, Las Vegas's (UNLV) bioassay program. This project consisted of two components that studied the effectiveness of a bioassay program in determining the dose for an acute inhalation of uranium. The first component of the plan addresses the creation of excretion curves, utilizing MATLAB that would allow UNLV to be able to determine at what time an inhalation dose can be attributed to. The excretion curves were based on the ICRP 30 lung model, as well as the Annual Limit Intake (ALI) values located in the Nuclear Regulatory Commission's 10CFR20 which is based on ICRP 30 (International Commission on Radiological Protection). The excretion curves would allow UNLV to be able to conduct in-house investigations of inhalation doses without solely depending on outside investigations and sources. The second component of the project focused on the creation of a risk based bioassay program to be utilized by UNLV that would take into account bioassay frequency that depended on the individual. Determining the risk based bioassay program required the use of baseline variance in order to minimize the investigation of false positives among those individuals who undergo bioassays for uranium work. The proposed program was compared against an evaluation limit of 10 mrem per quarter, an investigational limit of 125 mrem per quarter, and the federal/state requirement of 1.25 rem per quarter. It was determined that a bioassay program whose bioassay

National Uranium Resource Evaluation: Wichita Falls Quadrangle, Texas and Oklahoma

International Nuclear Information System (INIS)

Edwards, M.B.; Andersen, R.L.

1982-08-01

The uranium favorability of the Wichita Falls Quadrangle, Texas and Oklahoma, was determined by using National Uranium Resource Evaluation criteria; by subsurface studies of structure, facies distribution, and gamma-ray anomalies in well logs to a depth of 1500 m; and by surface studies involving extensive field sampling and radiometric surveying. These were supplemented by both aerial radiometric and hydrogeochemical and stream-sediment reconnaissance studies. Favorable environments were identified in fluviodeltaic to fan-delta sandstones in the upper Strawn, Canyon, and Cisco Groups (Pennsylvania to Lower Permian), which occur exclusively in the subsurface. Evaluation was based on the presence of a good uranium source, abundant feldspar, good hydrogeologic characteristics, association with carbonaceous shales, presence of coal and oil fields, and anomalies in gamma logs. Additional favorable environments include deltaic to alluvial sandstones in the Wichita-Albany Group (Lower Permian), which crops out widely and occurs in the shallow subsurface. Evaluation was based on high uranium values in stream-sediment samples, a small uranium occurrence located during the field survey, anomalous gamma logs, good uranium source, and hydrogeologic characteristics. Unfavorable environments include Cambrian to Permian limestones and shales. Pennsylvanian to Permian fluviodeltaic systems that have poor uranium sources, and Permian, Cretaceous, and Pleistocene formations that lack features characteristic of known uranium occurrences

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

Evaluation of the uranium enrichment demonstration plant project

International Nuclear Information System (INIS)

Sugitsue, Noritake

2001-01-01

In this report, the organization system of the uranium enrichment business is evaluated, based on the operation of the uranium enrichment demonstration plant. As a result, in uranium enrichment technology development or business, it was acknowledged that maintenance of the organization which has the Trinity of a research/engineering/operation was necessary in an industrialization stage by exceptional R and D cycle. Japan Nuclear Fuel Ltd. (JNFL) set up the Rokkashomura Aomori Uranium Enrichment Research and Development Center in November 2000. As a result, the system that company directly engaged in engineering development was prepared. And results obtained in this place is expected toward certain establishment of the uranium enrichment business of Japan. (author)

Evaluation of bioassay program at uranium fuel fabrication plants

International Nuclear Information System (INIS)

Biggs, D.

1981-03-01

Results of a comprehensive study of urinalysis, lung burden and personal air sample measurements for workers at a uranium fuel fabrication plant are presented. Correlations between measurements were found and regression models used to explain the relationship between lung burden, daily intakes and urinary excretions of uranium. Assuming the ICRP lung model, the lung burden histories of ten workers were used to estimate the amounts in each of the long-term compartments of the lung. Estimates of the half lives of each compartment and of the maximum relative contributions to the urine from each compartment are given. These values were then used to predict urinary excretions from the long-term compartments for workers at another fuel fabrication plant. The standard error of estimate compared well with the daily variation in urinary excretion. (author)

Environmental monitoring program of the uranium enrichment facility Almirante Alvaro Alberto

International Nuclear Information System (INIS)

Hiromoto, G.; Jacomino, V.M.F.; Venturini, L.; Moreira, S.R.D.; Gordon, A.M.P.L.; Duarte, C.L.; Pocequilo, B.R.S.; Mazzilli, B.P.

1988-11-01

In this report, the Environmental Monitoring Program of the Uranium Enrichment Facility Almirante Alvaro Alberto is outlined and the results obtained during the preoperational period are presented. Information concerning the population distribution, the use of water and land, the local agricultural production and the local meteorology are also available. In order to evaluate the levels of the background radiation, sample of water, air and biological and terrestrial indicators were analysed. Measurements were performed of natural gamma emitters concentrations levels and of uranium in air, surface water, precipitation, groundwater, river sediment, soil, grass, vegetation and various foodstuffs. For direct measurement of background radiation levels a solid state dosimeter network was used. Results are also presented for the analysis of non radioactive pollutants in the water samples and for the particles and gaseous fluorides concentration in the atmosphere. (author) [pt

Development of the disposal technology research component of the national uranium tailings program

International Nuclear Information System (INIS)

Melis, L.A.

1983-03-01

The National Technical Planning Group on Uranium Tailings Research, organized by CANMET in 1980, recommended the establishment of a National Uranium Tailings Program to develop research on the long-term abandonment of uranium mine tailings. This report deals with the disposal technology component of this program and attempts to provide recommendations with respect to potential research avenues in this area. A description of uranium tailings in Canada is provided in order to identify the current situation with uranium tailings management. Uranium mining sites described include the Elliot Lake and Bancroft area of Ontario, the northern Saskatchewan properties and the two abandoned sites in the North West Territories. The description of the sites was facilitated by subdividing the tailings into inactive sites, active sites, new tailings sites and areas of tailings in a close-out situation. Methods identified as promising include subsurface disposal, in-situ leaching, prevention of pyrite oxidation and reclamation studies at abandoned sites

Validation of the Monte Carlo Criticality Program KENO V. a for highly-enriched uranium systems

Energy Technology Data Exchange (ETDEWEB)

Knight, J.R.

1984-11-01

A series of calculations based on critical experiments have been performed using the KENO V.a Monte Carlo Criticality Program for the purpose of validating KENO V.a for use in evaluating Y-12 Plant criticality problems. The experiments were reflected and unreflected systems of single units and arrays containing highly enriched uranium metal or uranium compounds. Various geometrical shapes were used in the experiments. The SCALE control module CSAS25 with the 27-group ENDF/B-4 cross-section library was used to perform the calculations. Some of the experiments were also calculated using the 16-group Hansen-Roach Library. Results are presented in a series of tables and discussed. Results show that the criteria established for the safe application of the KENO IV program may also be used for KENO V.a results.

Validation of the Monte Carlo Criticality Program KENO V.a for highly-enriched uranium systems

International Nuclear Information System (INIS)

Knight, J.R.

1984-11-01

A series of calculations based on critical experiments have been performed using the KENO V.a Monte Carlo Criticality Program for the purpose of validating KENO V.a for use in evaluating Y-12 Plant criticality problems. The experiments were reflected and unreflected systems of single units and arrays containing highly enriched uranium metal or uranium compounds. Various geometrical shapes were used in the experiments. The SCALE control module CSAS25 with the 27-group ENDF/B-4 cross-section library was used to perform the calculations. Some of the experiments were also calculated using the 16-group Hansen-Roach Library. Results are presented in a series of tables and discussed. Results show that the criteria established for the safe application of the KENO IV program may also be used for KENO V.a results

Uranium: a basic evaluation

International Nuclear Information System (INIS)

Crull, A.W.

1978-01-01

All energy sources and technologies, including uranium and the nuclear industry, are needed to provide power. Public misunderstanding of the nature of uranium and how it works as a fuel may jeopardize nuclear energy as a major option. Basic chemical facts about uranium ore and uranium fuel technology are presented. Some of the major policy decisions that must be made include the enrichment, stockpiling, and pricing of uranium. Investigations and lawsuits pertaining to uranium markets are reviewed, and the point is made that oil companies will probably have to divest their non-oil energy activities. Recommendations for nuclear policies that have been made by the General Accounting Office are discussed briefly

Comprehensive Evaluation of Soil Near Uranium Tailings, Beishan City, China.

Science.gov (United States)

Xun, Yan; Zhang, Xinjia; Chaoliang, Chen; Luo, Xuegang; Zhang, Yu

2018-06-01

To evaluate the impact of uranium tailings on soil composition and soil microbial, six soil samples at different distance from the uranium tailings (Beishan City, China) were collected for further analysis. Concentrations of radionuclides ( 238 U and 232 Th), heavy metals (Mn, Cd, Cr, Ni, Zn, and Pb) and organochlorine pesticide were determined by ICP-MS and GC, they were significantly higher than those of the control. And the Average Well Color Development as well as the Shannon, the Evenness, and the Simpson index were calculated to evaluate the soil microbial diversity. The carbon utilization model of soil microbial community was also analyzed by Biolog-eco. All results indicated that uranium tailings leaded to excessive radionuclides and heavy metals, and decreased the diversity of the soil microbial community. Our study will provide a valuable basis for soil quality evaluation around uranium tailing repositories and lay a foundation for the management and recovery of uranium tailings.

Hydrogeochemical and stream-sediment reconnaissance, orientation study, Ouachita Mountain area, Arkansas. National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

Steele, K.F.

1982-08-01

A hydrogeochemical ground water orientation study was conducted in the multi-mineralized area of the Ouachita Mountains, Arkansas in order to evaluate the usefulness of ground water as a sampling medium for uranium exploration in similar areas. Ninety-three springs and nine wells were sampled in Clark, Garland, Hot Springs, Howard, Montgomery, Pike, Polk, and Sevier Counties. Manganese, barite, celestite, cinnabar, stibnite, copper, lead, and zinc are present. The following parameters were determined: pH, conductivity, alkalinity, U, Br, Cl, F, He, Mn, Na, V, Al, Dy, NO 3 , NH 3 , SO 4 , and PO 4 . The minerals appear to significantly affect the chemistry of the ground water. This report is issued in draft form, without detailed technical and copy editing. This was done to make the report available to the public before the end of the National Uranium Resource Evaluation

High-Uranium-Loaded U3O8-Al fuel element development program. Part 1

International Nuclear Information System (INIS)

Martin, M.M.

1993-01-01

The High-Uranium-Loaded U 3 O 8 -Al Fuel Element Development Program supports Argonne National Laboratory efforts to develop high-uranium-density research and test reactor fuel to accommodate use of low-uranium enrichment. The goal is to fuel most research and test reactors with uranium of less than 20% enrichment for the purpose of lowering the potential for diversion of highly-enriched material for nonpeaceful usages. The specific objective of the program is to develop the technological and engineering data base for U 3 O 8 -Al plate-type fuel elements of maximal uranium content to the point of vendor qualification for full scale fabrication on a production basis. A program and management plan that details the organization, supporting objectives, schedule, and budget is in place and preparation for fuel and irradiation studies is under way. The current programming envisions a program of about four years duration for an estimated cost of about two million dollars. During the decades of the fifties and sixties, developments at Oak Ridge National Laboratory led to the use of U 3 O 8 -Al plate-type fuel elements in the High Flux Isotope Reactor, Oak Ridge Research Reactor, Puerto Rico Nuclear Center Reactor, and the High Flux Beam Reactor. Most of the developmental information however applies only up to a uranium concentration of about 55 wt % (about 35 vol % U 3 O 8 ). The technical issues that must be addressed to further increase the uranium loading beyond 55 wt % U involve plate fabrication phenomena of voids and dogboning, fuel behavior under long irradiation, and potential for the thermite reaction between U 3 O 8 and aluminum

An example of economical evaluation of stratiform uranium ore deposit

International Nuclear Information System (INIS)

Miyata, Hatsuho; Tabuchi, Akihiro; Ushijima, Kenichi.

1992-01-01

The Power Reactor and Nuclear Fuel Development corp. has carried out the business of uranium resource investigation and exploration in foreign countries aiming at securing uranium resources. If there is the possibility of economically developing the discovered uranium deposit, it is transferred to a Japanese private enterprise. In this paper, among the economical evaluation works that were carried out for the uranium deposits discovered by the Corp., the example of the initial economical evaluation for a stratiform uranium deposit carried out recently is reported. The deposit is located at the depth of 50 m - 70 m, and is a stratiform deposit having the extension of 4000 m x 1000 m. The boring investigation of about 350 holes was carried out for it. The estimation of the amount of uranium was done, and the production plan was made considering the scale of production, the characteristics of the ore, the circumstances of the site and so on. Based on the production plan, the initial expenses and the operation expenses were calculated. The design of the optimal pit which affects most the profitability and the economical evaluation were carried out. (K.I.)

Overview of the nuclear fuel resources – seawater uranium recovery program sponsored by the U.S. Department of Energy

International Nuclear Information System (INIS)

Kung, S.

2014-01-01

. Structure-based computational design methods are being used to identify more selective and stable ligands. The most promising candidates are being synthesized, tested and evaluated for incorporation onto a support matrix. Fundamental thermodynamic and kinetic studies are being carried out to improve the adsorption efficiency, the selectivity of uranium over other elements, and the durability of the adsorbents. Understanding the rate-limiting step of uranium uptake from seawater is essential in designing an effective uranium recovery system. Economic analyses have been used to guide the technology development and highlight what parameters, such as capacity, recyclability, and stability, have the largest impact on the cost of extraction of uranium from seawater. Initially, cost estimates by Japanese researchers for extraction of uranium from seawater with braided polymeric fibers functionalized with amidoxime ligands were evaluated and updated. The economic analyses were subsequently updated to reflect the results of the U.S. program while providing insight for cost reductions in the adsorbent development through “cradle-to-grave” case studies for the extraction process. (author)

Occupational safety and health program for a model uranium mill

International Nuclear Information System (INIS)

Miller, H.T.

1981-01-01

The basic purpose of this paper is to suggest procedures and practices to insure that no employee working in a uranium milling operation receives exposure to radioactive, toxic, or other materials or agents that might produce a permanent, deleterious effect upon his physical health and well-being. This program is also designed to insure that each employee can carry out his assigned duties without risk to his health or to that of his fellow workers. The total program is envisioned as a balanced combination of occupational hygiene and radiation monitoring. This includes surveying, air sampling, personnel dosimetry, bioassay, medical surveillance, epidemiology, and training - all backed by a thoroughly tested and evaluated set of emergency procedures. The program, as presented, is keyed to the results of monitoring, surveying, air sampling, medical surveillance, and epidemiology - it being obvious that no problem can result when no hazard can be identified

National Uranium Resource Evaluation: Marfa Quadrangle, Texas

International Nuclear Information System (INIS)

Henry, C.D.; Duex, T.W.; Wilbert, W.P.

1982-09-01

The uranium favorability of the Marfa 1 0 by 2 0 Quadrangle, Texas, was evaluated in accordance with criteria established for the National Uranium Resource Evaluation. Surface and subsurface studies, to a 1500 m (5000 ft) depth, and chemical, petrologic, hydrogeochemical, and airborne radiometric data were employed. The entire quadrangle is in the Basin and Range Province and is characterized by Tertiary silicic volcanic rocks overlying mainly Cretaceous carbonate rocks and sandstones. Strand-plain sandstones of the Upper Cretaceous San Carlos Formation and El Picacho Formation possess many favorable characteristics and are tentatively judged as favorable for sandstone-type deposits. The Tertiary Buckshot Ignimbrite contains uranium mineralization at the Mammoth Mine. This deposit may be an example of the hydroauthigenic class; alternatively, it may have formed by reduction of uranium-bearing ground water produced during diagenesis of tuffaceous sediments of the Vieja Group. Although the presence of the deposit indicates favorability, the uncertainty in the process that formed the mineralization makes delineation of a favorable environment or area difficult. The Allen intrusions are favorable for authigenic deposits. Basin fill in several bolsons possesses characteristics that suggest favorability but which are classified as unevaluated because of insufficient data. All Precambrian, Paleozoic, other Mesozoic, and other Cenozoic environments are unfavorable

Final Environmental assessment for the Uranium Lease Management Program

International Nuclear Information System (INIS)

1995-07-01

The US Department of Energy (DOE) has prepared a programmatic environmental assessment (EA) of the proposed action to continue leasing withdrawn lands and DOE-owned patented claims for the exploration and production of uranium and vanadium ores. The Domestic Uranium Program regulation, codified at Title 10, Part 760.1, of the US Code of Federal Regulations (CFR), gives DOE the flexibility to continue leasing these lands under the Uranium Lease Management Program (ULMP) if the agency determines that it is in its best interest to do so. A key element in determining what is in DOE's ''best interest'' is the assessment of the environmental impacts that may be attributable to lease tract operations and associated activities. On the basis of the information and analyses presented in the EA for the ULMP, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined in the National Environmental Policy Act (NEPA) of 1969 (42 United States Code 4321 et seq.), as amended.Therefore, preparation of an environmental impact statement is not required for the ULMP,and DOE is issuing this Finding, of No Significant Impact (FONSI)

Final Environmental assessment for the Uranium Lease Management Program

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

The US Department of Energy (DOE) has prepared a programmatic environmental assessment (EA) of the proposed action to continue leasing withdrawn lands and DOE-owned patented claims for the exploration and production of uranium and vanadium ores. The Domestic Uranium Program regulation, codified at Title 10, Part 760.1, of the US Code of Federal Regulations (CFR), gives DOE the flexibility to continue leasing these lands under the Uranium Lease Management Program (ULMP) if the agency determines that it is in its best interest to do so. A key element in determining what is in DOE`s ``best interest`` is the assessment of the environmental impacts that may be attributable to lease tract operations and associated activities. On the basis of the information and analyses presented in the EA for the ULMP, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined in the National Environmental Policy Act (NEPA) of 1969 (42 United States Code 4321 et seq.), as amended.Therefore, preparation of an environmental impact statement is not required for the ULMP,and DOE is issuing this Finding, of No Significant Impact (FONSI).

BASIC program to compute uranium density and void volume fraction in laboratory-scale uranium silicide aluminum dispersion plate-type fuel

International Nuclear Information System (INIS)

Ugajin, Mitsuhiro

1991-05-01

BASIC program simple and easy to operate has been developed to compute uranium density and void volume fraction for laboratory-scale uranium silicide aluminum dispersion plate-type fuel, so called miniplate. An example of the result of calculation is given in order to demonstrate how the calculated void fraction correlates with the microstructural distribution of the void in a miniplate prepared in our laboratory. The program is also able to constitute data base on important parameters for miniplates from experimentally-determined values of density, weight of each constituent and dimensions of miniplates. Utility programs pertinent to the development of the BASIC program are also given which run in the popular MS-DOS environment. All the source lists are attached and brief description for each program is made. (author)

Technical evaluation of a radon daughter continuous monitor in an underground uranium mine

International Nuclear Information System (INIS)

Bigu, J.; Grenier, M.

1982-07-01

An evaluation of a radon daughter monitor was carried out in an underground uranium mine. The monitor operates on continuous sampling and time integrating principles. Experimental and theoretical data were compared. Experimental results show that the monitor underestimates the Working Level, a fact which is partly attributed to plate-out of decay products in the monitor sampling head. However, a correction factor experimentally determined by standard calibration procedures can be programmed into the monitor to take into account losses by plate-out and other losses. Although the monitor was originally designed for radon daughters, it can equally be used in thoron daughter atmospheres and radon daughter/thoron daughter mixtures such as those encountered in some Canadian uranium mines. An analytical procedure is outlined to allow the calculation of Working Levels in radon daughter/thoron daughter atmospheres from the monitor α-count rate. The memory capability of the monitor should make it quite useful and flexible in underground and surface environments in the uranium mining industry

Metabolic fate and evaluation of injury in rats and dogs following exposure to the hydrolysis products of uranium hexafluoride: implications for a bioassay program related to potential releases of uranium hexafluoride, July 1979-October 1981

International Nuclear Information System (INIS)

Morrow, P.E.; Leach, L.J.; Smith, F.A.

1982-12-01

This final report summarizes the experimental studies undertaken in rats and dogs in order to help provide adequate biological bases for quantifying and evaluating uranium hexafluoride (UF 6 ) exposures. Animals were administered the hydrolysis products of UF 6 by inhalation exposures, intratracheal instillations and intravenous injections. Attention was given to dose-effect relationships appropriate to the kidney, the unique site of subacute toxicity; to the rates of uranium excretion; and to uranium retention in renal tissue. These criteria were examined in both naive and multiply-exposed animals. The findings of these studies partly substantiate the ICRP excretion model for hexavalent uranium; generally provide a lower renal injury threshold concentration than implicit in the MPC for natural uranium; indicate distinctions in response (for example, uranium excretion) are based on exposure history; compare and evaluate various biochemical indices of renal injury; raise uncertainties about prevailing views of reversible renal injury, renal tolerance and possible hydrogen fluoride synergism with uranium effects; and reveal species differences in several areas, for example, renal retention of uranium. While these studies present some complicating features to extant bioassay practice, they nevertheless supply data supportive of the bioassay concept

Using low-enriched uranium in research reactors: The RERTR program

International Nuclear Information System (INIS)

Travelli, A.

1994-01-01

The goal of the RERTR program is to minimize and eventually eliminate use of highway enriched uranium (HEU) in research and test reactors. The program has been very successful, and has developed low-enriched uranium (LEU) fuel materials and designs which can be used effectively in approximately 90 percent of the research and test reactors which used HEU when the program began. This progress would not have been possible without active international cooperation among fuel developers, commercial vendors, and reactor operators. The new tasks which the RERTR program is undertaking at this time include development of new and better fuels that will allow use of LEU fuels in all research and test reactors; cooperation with Russian laboratories, which will make it possible to minimize and eventually eliminate use of HEU in research reactors throughout the world, irrespective of its origin; and development of an LEU-based process for the production of 99 Mo. Continuation and intensification of international cooperation are essential to the achievement of the ultimate goals of the RERTR program

Uranium evaluation and mining techniques

International Nuclear Information System (INIS)

1980-01-01

Full text: Report on an IAEA/NEA/IANEC international symposium, Buenos Aires, Argentina, 1-5 October 1979. The symposium was attended by 162 participants from 35 countries and five international organizations, with 35 observers also registered. Twenty-nine papers and two informal discussions were presented in seven sessions. Planning nuclear power programmes is fraught with a very wide range of uncertainties, some of which are the uncertainties associated with rising costs and ever-lengthening lead times, the uncertainties of the rate of growth of nuclear energy, the uncertainties caused by anti-nuclear activities, and the uncertainties of uranium resources and availability of uranium supplies. Present known resources, not all of which may actually become uranium supply before the year 2025, are slightly less than 5 million tonnes uranium. Even if all these resources could be produced, production rates from them would drop seriously in the mid-1990s. It is, therefore, most important that the uncertainty of uranium resources and availability of supply be dealt with promptly. In this respect many countries of the world have begun national programmes either to determine their uranium potential, or to explore for uranium deposits. The symposium held in Buenos Aires at the invitation of the Government of Argentina sought to provide these countries with a state-of-the-art report on the various methods of uranium resource evaluation. Developments and improvements in both new and old techniques of mineral assessment proliferate. Notable among the 'newer' methods are geostatistical estimation of ore reserves, a sophisticated method which, although still under development, has gained wide recognition. In the domain of objective measurements and sample-based estimation procedures, the older classical methods also yield acceptable estimates when properly used. But uranium ore reserves are always inadequate for long-range planning, seldom exceeding a few years' demand. An

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

The main advance and achievements in the potential evaluation of uranium resource in China

International Nuclear Information System (INIS)

Zhang Jindai; Guo Qingyin; Li Youliang; Li Ziying; Cai Yuqi; Han Changqing

2012-01-01

The national uranium resources potential evaluation is one of the important national census in China. The evaluation is based on the data and results accomplished by nuclear geological industry in last decades and wholly performed on GIS platform by absorbing related technology and geological achievement in home and broad, and has figured out 329 uranium predicted mineralization areas and estimated more than 2000000 tones resource on a national scale. Innovative achievements has been made in the classification of uranium deposit type and mineralization belt, integration of geological-geophysical-geochemical-remote sensing information and research of uranium mineralization pattern. For the first time, the potential evaluation has been performed totally by digitalisation and information, the evaluation will provide important evidence for developing middle-long term planning of uranium exploration and laid good foundation to future dynamic and regular evaluation of uranium resource in China. (authors)

Surplus Highly Enriched Uranium Disposition Program plan

International Nuclear Information System (INIS)

1996-10-01

The purpose of this document is to provide upper level guidance for the program that will downblend surplus highly enriched uranium for use as commercial nuclear reactor fuel or low-level radioactive waste. The intent of this document is to outline the overall mission and program objectives. The document is also intended to provide a general basis for integration of disposition efforts among all applicable sites. This plan provides background information, establishes the scope of disposition activities, provides an approach to the mission and objectives, identifies programmatic assumptions, defines major roles, provides summary level schedules and milestones, and addresses budget requirements

Uranium industry seminar: proceedings

International Nuclear Information System (INIS)

1981-01-01

The eleventh annual Uranium Industry Seminar, sponsored by the Grand Junction Area Office of the US Department of Energy (DOE), was held in Grand Junction, Colorado, on October 21 and 22, 1981. There were 491 registered attendees as compared to 700 attending the previous year. The attendees were largely from uranium and other energy resource companies, electric utility firms, energy consultants and service companies, and governmental agencies. In addition, there were representatives present from Indian tribes, universities, the media, DOE laboratories, and foreign countries and organizations. Papers presented at the seminar dealt with uranium policies, exploration, resources, supply, enrichment, and market conditions. There also were papers on the National Uranium Resource Evaluation Program and international activities. Thirteen papers included in this report have been abstracted and indexed

National Uranium Resource Evaluation: Athens Quadrangle, Georgia and South Carolina

International Nuclear Information System (INIS)

Lee, C.H.

1979-09-01

Reconnaissance and detailed geologic and radiometric investigations were conducted throughout the Athens Quadrangle, Georgia and South Carolina, to evaluate the uranium favorability using National Uranium Resource Evaluation criteria. Surface and subsurface studies were augmented by aerial radiometric surveys, emanometry studies and hydrogeochemical and stream-sediment reconnaissance studies. The results of the investigations indicate environments favorable for allogenic deposits in metamorphic rocks adjacent to granite plutons, and Texas roll-type sandstone deposits in the Coastal Plain Province. Environments considered unfavorable for uranium deposits are the placers of the Monazite Belt, pegmatites, and base- and precious-metal veins associated with faults and shear zones in metamorphic rocks

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)

National Uranium Resource Evaluation: Lamar quadrangle, Colorado and Kansas

International Nuclear Information System (INIS)

Maarouf, A.M.; Johnson, V.C.

1982-01-01

Uranium resources of the Lamar Quadrangle, Colorado and Kansas, were evaluated using National Uranium Resource Evaluation criteria. The environment favorable for uranium is the Lower Cretaceous Dakota Sandstone in the area east of John Martin Reservoir for south Texas roll-type sandstone deposits. Carbonaceous trash and sulfides are abundant in the Dakota Sandstone. The unit underlies a thick Upper Cretaceous section that contains bentonitic beds and uraniferous marine black shale. Water samples from the Dakota Sandstone aquifer contain as much as 122 ppB U 3 O 8 . Geologic units considered unfavorable include most of the Paleozoic rocks, except in the Brandon Fault area; the Upper Cretaceous rocks; and the Ogallala Formation. The Dockum Group, Morrison Formation, and Lytle Member of the Purgatoire Formation are unevaluated because of lack of data

Evaluation of an automatic uranium titration system

International Nuclear Information System (INIS)

Lewis, K.

1980-01-01

The titration system utilizes the constant current coulometric titration of Goldbeck and Lerner. U(VI) is reduced to U(IV) by Fe(II). V(V) is generated to titrate the U(IV), and the titration is followed potentiometrically. The evaluation shows that the recovery of uranium is 100% at the 40-mg level. The accuracy is generally +-0.10% or better. The smallest sample weight at which reliable results were obtained was 40 mg of uranium. Time for one analysis is 15 minutes. Advantages and disadvantages of the automated titrator are listed

Profile of World Uranium Enrichment Programs-2009

International Nuclear Information System (INIS)

Laughter, Mark D.

2009-01-01

demonstrated commercially. In the early 1980s, six countries developing gas centrifuge technology (United States, United Kingdom, Germany, the Netherlands, Japan, and Australia) along with the International Atomic Energy Agency and the European Atomic Energy Community began developing effective safeguards techniques for GCEPs. This effort was known as the Hexapartite Safeguards Project (HSP). The HSP had the goal of maximizing safeguards effectiveness while minimizing the cost to the operator and inspectorate, and adopted several recommendations, such as the acceptance of limited-frequency unannounced access inspections in cascade halls, and the use of nondestructive assay measurements and tamper-indicating seals. While only the HSP participants initially committed to implementing all the measures of the approach, it has been used as a model for the safeguards applied to GCEPs in additional states. Uranium enrichment capacity has continued to expand on all fronts in the last few years. GCEP capacity is expanding in anticipation of the eventual shutdown of the less-efficient GDPs, the termination of the U.S.-Russia HEU blend-down program slated for 2013, and the possible resurgence of nuclear reactor construction as part of an expected 'Nuclear Renaissance'. Overall, a clear trend in the world profile of uranium enrichment plant operation is the continued movement towards multinational projects driven by commercial and economic interests. Along this vein, the safeguards community is continuing to develop new safeguards techniques and technologies that are not overly burdensome to enrichment plant operators while delivering more effective and efficient results. This report provides a snapshot overview of world enrichment capacity in 2009, including profiles of the uranium enrichment programs of individual states. It is a revision of a 2007 report on the same topic; significant changes in world enrichment programs between the previous and current reports are emphasized. It is

Geology and mineral resources of the Florence, Beaufort, Rocky Mount, and Norfolk 1/sup 0/ x 2/sup 0/ NTMS quadrangles. National Uranium Resource Evaluation program

Energy Technology Data Exchange (ETDEWEB)

Harris, W.B.

1982-08-01

This document provides geologic and mineral resources data for previously-issued Savannah River Laboratory hydrogeochemical and stream sediment reports of the Beaufort, Florence, Norfolk, and Rocky Mount 1/sup 0/ x 2/sup 0/ National Topographic Map Series quadrangles in the southeastern United States. This report is issued in draft form, without detailed technical and copy editing. This was done to make the report available to the public before the end of the National Uranium Resource Evaluation program.

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

Criticality safety evaluation for the Advanced Test Reactor enhanced low enriched uranium fuel elements

Energy Technology Data Exchange (ETDEWEB)

Montierth, Leland M. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-07-19

The Global Threat Reduction Initiative (GTRI) convert program is developing a high uranium density fuel based on a low enriched uranium (LEU) uranium-molybdenum alloy. Testing of prototypic GTRI fuel elements is necessary to demonstrate integrated fuel performance behavior and scale-up of fabrication techniques. GTRI Enhanced LEU Fuel (ELF) elements based on the ATR-Standard Size elements (all plates fueled) are to be fabricated for testing in the Advanced Test Reactor (ATR). While a specific ELF element design will eventually be provided for detailed analyses and in-core testing, this criticality safety evaluation (CSE) is intended to evaluate a hypothetical ELF element design for criticality safety purposes. Existing criticality analyses have analyzed Standard (HEU) ATR elements from which controls have been derived. This CSE documents analysis that determines the reactivity of the hypothetical ELF fuel elements relative to HEU ATR elements and whether the existing HEU ATR element controls bound the ELF element. The initial calculations presented in this CSE analyzed the original ELF design, now referred to as Mod 0.1. In addition, as part of a fuel meat thickness optimization effort for reactor performance, other designs have been evaluated. As of early 2014 the most current conceptual designs are Mk1A and Mk1B, that were previously referred to as conceptual designs Mod 0.10 and Mod 0.11, respectively. Revision 1 evaluates the reactivity of the ATR HEU Mark IV elements for a comparison with the Mark VII elements.

Criticality safety evaluation for the Advanced Test Reactor enhanced low enriched uranium fuel elements

International Nuclear Information System (INIS)

Montierth, Leland M.

2016-01-01

The Global Threat Reduction Initiative (GTRI) convert program is developing a high uranium density fuel based on a low enriched uranium (LEU) uranium-molybdenum alloy. Testing of prototypic GTRI fuel elements is necessary to demonstrate integrated fuel performance behavior and scale-up of fabrication techniques. GTRI Enhanced LEU Fuel (ELF) elements based on the ATR-Standard Size elements (all plates fueled) are to be fabricated for testing in the Advanced Test Reactor (ATR). While a specific ELF element design will eventually be provided for detailed analyses and in-core testing, this criticality safety evaluation (CSE) is intended to evaluate a hypothetical ELF element design for criticality safety purposes. Existing criticality analyses have analyzed Standard (HEU) ATR elements from which controls have been derived. This CSE documents analysis that determines the reactivity of the hypothetical ELF fuel elements relative to HEU ATR elements and whether the existing HEU ATR element controls bound the ELF element. The initial calculations presented in this CSE analyzed the original ELF design, now referred to as Mod 0.1. In addition, as part of a fuel meat thickness optimization effort for reactor performance, other designs have been evaluated. As of early 2014 the most current conceptual designs are Mk1A and Mk1B, that were previously referred to as conceptual designs Mod 0.10 and Mod 0.11, respectively. Revision 1 evaluates the reactivity of the ATR HEU Mark IV elements for a comparison with the Mark VII elements.

Synthesis of uranium metal using laser-initiated reduction of uranium tetrafluoride by calcium metal

International Nuclear Information System (INIS)

West, M.H.; Martinez, M.M.; Nielsen, J.B.; Court, D.C.; Appert, Q.D.

1995-09-01

Uranium metal has numerous uses in conventional weapons (armor penetrators) and nuclear weapons. It also has application to nuclear reactor designs utilizing metallic fuels--for example, the former Integral Fast Reactor program at Argonne National Laboratory. Uranium metal also has promise as a material of construction for spent-nuclear-fuel storage casks. A new avenue for the production of uranium metal is presented that offers several advantages over existing technology. A carbon dioxide (CO 2 ) laser is used to initiate the reaction between uranium tetrafluoride (UF 4 ) and calcium metal. The new method does not require induction heating of a closed system (a pressure vessel) nor does it utilize iodine (I 2 ) as a chemical booster. The results of five reductions of UF 4 , spanning 100 to 200 g of uranium, are evaluated, and suggestions are made for future work in this area

Risk evaluation of uranium mining: a new kinetic approach

Energy Technology Data Exchange (ETDEWEB)

Scislewski, Alexandro [Brazilian Nuclear Energy Comission (CNEN), Avenida Santana, 680, Centro, Caetite-Bahia, 46400-000 (Brazil); Zuddas, Pierpaolo [Universite Pierre et Marie Curie, Paris-Sorbonne, ISTEP place Jussieu, Tour 56-55, case 116, F75252 Paris Cedex 05 (France)

2013-07-01

Release of uranium and associated heavy metals is the main environmental concern regarding exploitation and processing of U-ore. Increasing uranium mining activities potentially increase the risks linked to radiation exposure. As a tool to evaluate these risks, a geochemical inverse modeling approach was developed to estimate the water-mineral interaction in the presence of uranium. Our methodology is based on the estimation of dissolution rate and reactive surface area of the different minerals participating in the reaction by reconstructing the chemical evolution of the interacting fluids. We found that the reactive surface area of parent-rock minerals changes over several orders of magnitude during the investigated reaction time. We propose that the formation of coatings on dissolving mineral surfaces significantly reduces reactivity. Our results show that negatively charged uranium complexes decrease when alkalinity and rock buffer capacity is similarly lower, indicating that the dissolved carbonate is an important parameter impacting uranium mobility. (authors)

Risk evaluation of uranium mining: a new kinetic approach

International Nuclear Information System (INIS)

Scislewski, Alexandro; Zuddas, Pierpaolo

2013-01-01

Release of uranium and associated heavy metals is the main environmental concern regarding exploitation and processing of U-ore. Increasing uranium mining activities potentially increase the risks linked to radiation exposure. As a tool to evaluate these risks, a geochemical inverse modeling approach was developed to estimate the water-mineral interaction in the presence of uranium. Our methodology is based on the estimation of dissolution rate and reactive surface area of the different minerals participating in the reaction by reconstructing the chemical evolution of the interacting fluids. We found that the reactive surface area of parent-rock minerals changes over several orders of magnitude during the investigated reaction time. We propose that the formation of coatings on dissolving mineral surfaces significantly reduces reactivity. Our results show that negatively charged uranium complexes decrease when alkalinity and rock buffer capacity is similarly lower, indicating that the dissolved carbonate is an important parameter impacting uranium mobility. (authors)

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 tailings sampling manual

International Nuclear Information System (INIS)

Feenstra, S.; Reades, D.W.; Cherry, J.A.; Chambers, D.B.; Case, G.G.; Ibbotson, B.G.

1985-01-01

The purpose of this manual is to describe the requisite sampling procedures for the application of uniform high-quality standards to detailed geotechnical, hydrogeological, geochemical and air quality measurements at Canadian uranium tailings disposal sites. The selection and implementation of applicable sampling procedures for such measurements at uranium tailings disposal sites are complicated by two primary factors. Firstly, the physical and chemical nature of uranium mine tailings and effluent is considerably different from natural soil materials and natural waters. Consequently, many conventional methods for the collection and analysis of natural soils and waters are not directly applicable to tailings. Secondly, there is a wide range in the physical and chemical nature of uranium tailings. The composition of the ore, the milling process, the nature of tailings depositon, and effluent treatment vary considerably and are highly site-specific. Therefore, the definition and implementation of sampling programs for uranium tailings disposal sites require considerable evaluation, and often innovation, to ensure that appropriate sampling and analysis methods are used which provide the flexibility to take into account site-specific considerations. The following chapters describe the objective and scope of a sampling program, preliminary data collection, and the procedures for sampling of tailings solids, surface water and seepage, tailings pore-water, and wind-blown dust and radon

National Uranium Resource Evaluation: Wells Quadrangle, Nevada, Idaho, and Utah

International Nuclear Information System (INIS)

Proffitt, J.L.; Mayerson, D.L.; Parker, D.P.; Wolverson, N.; Antrim, D.; Berg, J.; Witzel, F.

1982-08-01

The Wells 2 0 Quadrangle, Nevada, Idaho, and Utah, was evaluated using National Uranium Resource Evaluation criteria to delineate areas favorable for uranium deposits. Our investigation has resulted in the delineation of areas that contain Tertiary sedimentary rocks favorable for hydroallogenic deposits in the Mountain City area (Favorable Area A) and in the Oxley Peak area north of Wells (Favorable Area B). Environments considered to be unfavorable for uranium deposits include Tertiary felsic volcanic, felsic plutonic, intermediate to mafic volcanic, Paleozoic and Mesozoic sedimentary rocks, Precambrian rocks, and most Tertiary sedimentary rocks located outside the favorable areas. Present-day basins are unevaluated environments because of a paucity of adequate outcrop and subsurface data. However, the scarce data indicate that some characteristics favorable for uranium deposits are present in the Susie Creek-Tule Valley-Wild Horse basin, the Contact-Granite Range-Tijuana John stocks area, the Charleston Reservoir area, and the Wells-Marys River basin

The uranium industry of Bulgaria

International Nuclear Information System (INIS)

Pool, T.C.

1991-01-01

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

Uranium enrichment

International Nuclear Information System (INIS)

1989-01-01

GAO was asked to address several questions concerning a number of proposed uranium enrichment bills introduced during the 100th Congress. The bill would have restructured the Department of Energy's uranium enrichment program as a government corporation to allow it to compete more effectively in the domestic and international markets. Some of GAO's findings discussed are: uranium market experts believe and existing market models show that the proposed DOE purchase of a $750 million of uranium from domestic producers may not significantly increase production because of large producer-held inventories; excess uranium enrichment production capacity exists throughout the world; therefore, foreign producers are expected to compete heavily in the United States throughout the 1990s as utilities' contracts with DOE expire; and according to a 1988 agreement between DOE's Offices of Nuclear Energy and Defense Programs, enrichment decommissioning costs, estimated to total $3.6 billion for planning purposes, will be shared by the commercial enrichment program and the government

Uranium industry seminar

International Nuclear Information System (INIS)

1980-01-01

The tenth annual Uranium Industry Seminar, sponsored by the US Department of Energy's (DOE) Grand Junction Office, was held in Grand Junction, Colorado, on October 22 and 23, 1980. There were 700 registered attendees as compared to 833 attending the previous year. The attendees were drawn largely from uranium and other energy resource companies, electric utility firms, energy consultants and service companies, and governmental agencies. In addition, there were representatives present from Indian tribes, universities, the media, DOE laboratories, and foreign countries and organizations. There were 14 papers presented at the seminar by speakers from the Department of Energy, US Geological Survey, and Bendix Field Engineering Corporation which is the on-site prime contractor for DOE's Grand Junction Office. The topics the papers dealt with were uranium policies, exploration, respources, supply, enrichment, and market conditions. There also were papers describing the National Uranium Resource Evaluation program and international activities. All 14 papers in this Proceedings have been abstracted and indexed

Evaluation of precision in measurements of uranium isotope ratio by thermionic mass spectrometry

International Nuclear Information System (INIS)

Moraes, N.M.P. de; Rodrigues, C.

1977-01-01

The parameters which affect the precision and accuracy of uranium isotopic ratios measurements by thermionic mass spectrometry are discussed. A statistical designed program for the analysis of the internal and external variances are presented. It was done an application of this statistical methods, in order to get mass discrimination factor, and its standard mean deviation, by using some results already published for 235 U/ 238 U ratio in NBS uranium samples, and natural uranium [pt

Uranium in alkaline rocks

Energy Technology Data Exchange (ETDEWEB)

Murphy, M.; Wollenberg, H.; Strisower, B.; Bowman, H.; Flexser, S.; Carmichael, I.

1978-04-01

Geologic and geochemical criteria were developed for the occurrence of economic uranium deposits in alkaline igneous rocks. A literature search, a limited chemical analytical program, and visits to three prominent alkaline-rock localities (Ilimaussaq, Greenland; Pocos de Caldas, Brazil; and Powderhorn, Colorado) were made to establish criteria to determine if a site had some uranium resource potential. From the literature, four alkaline-intrusive occurrences of differing character were identified as type-localities for uranium mineralization, and the important aspects of these localities were described. These characteristics were used to categorize and evaluate U.S. occurrences. The literature search disclosed 69 U.S. sites, encompassing nepheline syenite, alkaline granite, and carbonatite. It was possible to compare two-thirds of these sites to the type localities. A ranking system identified ten of the sites as most likely to have uranium resource potential.

Uranium in alkaline rocks

International Nuclear Information System (INIS)

Murphy, M.; Wollenberg, H.; Strisower, B.; Bowman, H.; Flexser, S.; Carmichael, I.

1978-04-01

Geologic and geochemical criteria were developed for the occurrence of economic uranium deposits in alkaline igneous rocks. A literature search, a limited chemical analytical program, and visits to three prominent alkaline-rock localities (Ilimaussaq, Greenland; Pocos de Caldas, Brazil; and Powderhorn, Colorado) were made to establish criteria to determine if a site had some uranium resource potential. From the literature, four alkaline-intrusive occurrences of differing character were identified as type-localities for uranium mineralization, and the important aspects of these localities were described. These characteristics were used to categorize and evaluate U.S. occurrences. The literature search disclosed 69 U.S. sites, encompassing nepheline syenite, alkaline granite, and carbonatite. It was possible to compare two-thirds of these sites to the type localities. A ranking system identified ten of the sites as most likely to have uranium resource potential

International Uranium Resources Evaluation Project (IUREP) orientation phase mission report: Bolivia. Draft

International Nuclear Information System (INIS)

Leroy, Jacques; Mueller-Kahle, Eberhard

1982-08-01

The uranium exploration done so far in Bolivia has been carried out by COBOEN, partly with IAEA support, and AGIP S.p.A. of Italy, which between 1974 and 1978 explored four areas in various parts of Bolivia under a production sharing contract with COBOEN. The basic objective of the International Uranium Resources Evaluation Project (IUREP) is to 'review the present body of knowledge pertinent to the existence of uranium resources, to review and evaluate the potential for discovery of additional uranium resources, and to suggest new exploitation efforts which might be carried out in promising areas in collaboration with the country concerned'. Following the initial bibliographic study which formed Phase I of IUREP, it was envisaged that a further assessment in cooperation with, and within, the country concerned would provide a better delineation of areas of high potential and a more reliable estimate as to the degree of favourability for the discovery of additional uranium resources. It was planned that such work would be accomplished through field missions to the country concerned and that these field missions and the resulting report would be known as the Orientation Phase of IUREP. The purpose of the Orientation Phase mission to Bolivia was a) to develop a better understanding of the uranium potential of the country, b) to make an estimate of the Speculative Resources of the country, c) to delineate areas favourable for the discovery of these uranium resources, d) to make recommendations as appropriate on the best methods for evaluating the favourable areas, operating procedures and estimated possible costs, e) to develop the logistical data required to carry out any possible further work, and f) to compile a report which would be immediately available to the Bolivian authorities. The mission reports contains information about a general introduction, non-uranium exploration and mining in Bolivia, manpower in exploration, geological review of Bolivia, past uranium

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

Radiological protection in underground uranium mines

International Nuclear Information System (INIS)

Napolitano, Celia Marina

1978-01-01

The radiosanitary hazards that workers of an uranium ore can suffer were studied. The more used control methods for the the evaluation of doses received by the workers was studied too. It was developed a technique using the scintillation chamber method for the detection of radon. Emanation and diffusion methods were used for extraction of radon from water. A program of radiological protection based on ICRP recommendation was analysed for uranium mines. This program includes: ventilation needs calculation methods, a study of radiological protection optimization based on 'cost-benefit' analysis, a monitoring plan and a study about radioactive waste management. (author)

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

International Nuclear Information System (INIS)

Morales, M.; Lopez Romero, A.

1996-01-01

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

National Uranium Resource Evaluation. General procedure for calibration and reduction of aerial gamma-ray measurements: specification BFEC 1250-B

International Nuclear Information System (INIS)

Purvance, D.; Novak, E.

1983-12-01

The information contained in this specification was acquired over the course of the US Department of Energy (DOE) National Uranium Resource Evaluation (NURE) program during the period 1974 through 1982. NURE was a program of the DOE Grand Junction Area Office to acquire and compile geologic and other information with which to assess the magnitude and distribution of uranium resources and to determine areas favorable for the occurrence of uranium in the United States. Bendix Field Engineering Corporation (BFEC) has been the operating contractor for the DOE Grand Junction facility. The requirements stipulated herein had been incorporated as contractual specifications for the various subcontractors engaged in the aerial gamma-ray surveys, which were a major aspect of the NURE program. Although this phase of NURE activities has been completed, there exists valuable knowledge gained from these years of experience in the calibration of gamma-ray spectrometer systems and in the reduction of calibration data. Specification BFEC 1250-B is being open-filed by the US Department of Energy at this time to make this knowledge available to those desiring to apply gamma-ray spectrometry to other geophysical problems

Internal dosimetric evaluation due to uranium aerosols

International Nuclear Information System (INIS)

Garcia Aguilar Juan; Delgado Avila Gustavo

1991-01-01

The present work has like object to carry out the internal dosimetric evaluation to the occupationally exposed personnel, due to the inhalation of aerosols of natural uranium and enriched in the pilot plant of nuclear fuel production of the National Institute of Nuclear Research

NURE uranium deposit model studies

International Nuclear Information System (INIS)

Crew, M.E.

1981-01-01

The National Uranium Resource Evaluation (NURE) Program has sponsored uranium deposit model studies by Bendix Field Engineering Corporation (Bendix), the US Geological Survey (USGS), and numerous subcontractors. This paper deals only with models from the following six reports prepared by Samuel S. Adams and Associates: GJBX-1(81) - Geology and Recognition Criteria for Roll-Type Uranium Deposits in Continental Sandstones; GJBX-2(81) - Geology and Recognition Criteria for Uraniferous Humate Deposits, Grants Uranium Region, New Mexico; GJBX-3(81) - Geology and Recognition Criteria for Uranium Deposits of the Quartz-Pebble Conglomerate Type; GJBX-4(81) - Geology and Recognition Criteria for Sandstone Uranium Deposits in Mixed Fluvial-Shallow Marine Sedimentary Sequences, South Texas; GJBX-5(81) - Geology and Recognition Criteria for Veinlike Uranium Deposits of the Lower to Middle Proterozoic Unconformity and Strata-Related Types; GJBX-6(81) - Geology and Recognition Criteria for Sandstone Uranium Deposits of the Salt Wash Type, Colorado Plateau Province. A unique feature of these models is the development of recognition criteria in a systematic fashion, with a method for quantifying the various items. The recognition-criteria networks are used in this paper to illustrate the various types of deposits

The use of uranium isotopes and the U/Th ratio to evaluate the fingerprint of plants following uranium releases from fuel cycle settlements

International Nuclear Information System (INIS)

Pourcelot, L.; Boulet, B.; Cariou, N.

2015-01-01

This paper uses data from the environmental monitoring of fuel cycle settlements. It aims to evaluate uranium released into the terrestrial environment. Measurement of uranium isotopes in terrestrial plants allows illustrating the consequences of chronic and incidental releases of depleted uranium into the atmosphere. However, such an analytical approach reaches its limits when natural uranium is released. Indeed, distinguishing natural uranium from releases and uranium from the radiological background is difficult. For this reason, we propose normalizing uranium activity measured in plants taken in the surroundings of nuclear sites with respect to 232 Th, considering that the source of this latter is the background. (authors)

National Uranium Resource Evaluation: Albany Quadrangle, Massachusetts, New York, Connecticut, Vermont, and New Hampshire

Energy Technology Data Exchange (ETDEWEB)

Field, M T; Truesdell, D B

1982-09-01

The Albany 1/sup 0/ x 2/sup 0/ Quadrangle, Massachusetts, New York, Connecticut, Vermont, and New Hampshire, was evaluated to a depth of 1500 m for uranium favorability using National Uranium Resource Evaluation criteria. Areas of favorable geology and aeroradioactivity anomalies were examined and sampled. Most Triassic and Jurassic sediments in the Connecticut Basin, in the central part of the quadrangle, were found to be favorable for sandstone uranium deposits. Some Precambrian units in the southern Green Mountains of Vermont were found favorable for uranium deposits in veins in metamorphic rocks.

National Uranium Resource Evaluation: Albany Quadrangle, Massachusetts, New York, Connecticut, Vermont, and New Hampshire

International Nuclear Information System (INIS)

Field, M.T.; Truesdell, D.B.

1982-09-01

The Albany 1 0 x 2 0 Quadrangle, Massachusetts, New York, Connecticut, Vermont, and New Hampshire, was evaluated to a depth of 1500 m for uranium favorability using National Uranium Resource Evaluation criteria. Areas of favorable geology and aeroradioactivity anomalies were examined and sampled. Most Triassic and Jurassic sediments in the Connecticut Basin, in the central part of the quadrangle, were found to be favorable for sandstone uranium deposits. Some Precambrian units in the southern Green Mountains of Vermont were found favorable for uranium deposits in veins in metamorphic rocks

High-uranium-loaded U3O8-Al fuel element development program [contributed by N.M. Martin, ORNL

International Nuclear Information System (INIS)

Martin, M.M.

1993-01-01

The High-Uranium-Loaded U 3 O 8 -Al Fuel Element Development Program supports Argonne National Laboratory efforts to develop high-uranium-density research and test reactor fuel to accommodate use of low-uranium enrichment. The goal is to fuel most research and test reactors with uranium of less than 20% enrichment for the purpose of lowering the potential for diversion of highly-enriched material for nonpeaceful usages. The specific objective of the program is to develop the technological and engineering data base for U 3 O 8 -Al plate-type fuel elements of maximal uranium content to the point of vendor qualification for full scale fabrication on a production basis. A program and management plan that details the organization, supporting objectives, schedule, and budget is in place and preparation for fuel and irradiation studies is under way. The current programming envisions a program of about four years duration for an estimated cost of about two million dollars. During the decades of the fifties and sixties, developments at Oak Ridge National Laboratory led to the use of U 3 O 8 -Al plate-type fuel elements in the High Flux Isotope Reactor, Oak Ridge Research Reactor, Puerto Rico Nuclear Center Reactor, and the High Flux Beam Reactor. Most of the developmental information however applies only up to a uranium concentration of about 55 wt % (about 35 vol % U 3 O 8 ). The technical issues that must be addressed to further increase the uranium loading beyond 55 wt % involve plate fabrication phenomena of voids and dogboning, fuel behavior under long irradiation, and potential for the thermite reaction between U 3 O 8 and aluminum. (author)

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

Environmental Development Plan: uranium mining, milling, and conversion

International Nuclear Information System (INIS)

1979-08-01

This Environmental Development Plan (EDP) identifies the planning and management requirements and schedules needed to evaluate and assess the environmental, health, and safety (EH and S) aspects of the uranium mining, milling, and conversion technologies. The plan represents the collective perceptions of EH and S concerns and requirements and knowledge of ongoing research programs of most of the Federal agencies involved in significant EH and S R and D program management, standards setting, or regulatory activities associated with uranium mining, milling, and conversion

Radiation pathways and potential health impacts from inactive uranium mill tailings

International Nuclear Information System (INIS)

1978-07-01

Radiation exposure pathways and potential health impacts were estimated as part of the evaluation of radioactive uranium mill tailings at the sites of inactive mills in eight western states. The purpose of this report is to describe in detail the methodology used in performing the pathway analysis and health effects estimations. In addition, specific parameters are presented for each of the 22 uranium mill sites that were evaluated. A computer program, RADAD, developed as part of this program, is described and listed

Automated electron microprobe identification of minerals in stream sediments for the national uranium resources evaluation program

International Nuclear Information System (INIS)

Mosley, W.C. Jr.

1979-01-01

Over 500 stream sediment particles have been analyzed. About 96% have been identified as distinct minerals. Most of the others appeared to be mixtures. Only zinc-bearing gahnite had to be analyzed further for positive identification. Monazite and zircon were the only minerals with concentrations of uranium significantly above the detection limit. The Frantz Isodynamic Magnetic Separator isolated the monazite into the 1.0 fraction. Monazite particles in anomalous sediments contained up to 3.7 wt % uranium. This uranium concentration is unusually high for monazite, which normally has about 0.5 wt % uranium, and may be the cause of the anomaly

Annual status report on the Uranium Mill Tailings Remedial Action Program

International Nuclear Information System (INIS)

1989-12-01

This eleventh annual status report summarizes activities of the Uranium Mill Tailings Remedial Action (UMTRA) Project undertaken during Fiscal Year (FY) 1989 by the US Department of Energy (DOE) and other agencies. Project goals for FY 1990 are also presented. An annual report of this type was a statutory requirement through January 1, 1986, pursuant to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95--604. The DOE will continue to submit an annual report through project completion in order to inform the public of yearly project status. Title I of the UMTRCA authorizes the DOE, in cooperation with affected states and Indian tribes within whose boundaries designated uranium processing sites are located, to provide a program of assessment and remedial action at such sites. The purpose of the remedial action is to stabilize and control the tailings and other residual radioactive materials located on the inactive uranium processing sites in a safe and environmentally sound manner and to minimize or eliminate potential radiation health hazards. Commercial and residential properties in the vicinity of designated processing sites that are contaminated with material from the sites, herein referred to as ''vicinity properties,'' are also eligible for remedial action. Included in the UMTRA Project are 24 inactive uranium processing sites and associated vicinity properties located in 10 states, and the vicinity properties associated with Edgemont, South Dakota, an inactive uranium mill currently owned by the Tennessee Valley Authority (TVA)

Annual status report on the Uranium Mill Tailings Remedial Action Program

Energy Technology Data Exchange (ETDEWEB)

1989-12-01

This eleventh annual status report summarizes activities of the Uranium Mill Tailings Remedial Action (UMTRA) Project undertaken during Fiscal Year (FY) 1989 by the US Department of Energy (DOE) and other agencies. Project goals for FY 1990 are also presented. An annual report of this type was a statutory requirement through January 1, 1986, pursuant to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95--604. The DOE will continue to submit an annual report through project completion in order to inform the public of yearly project status. Title I of the UMTRCA authorizes the DOE, in cooperation with affected states and Indian tribes within whose boundaries designated uranium processing sites are located, to provide a program of assessment and remedial action at such sites. The purpose of the remedial action is to stabilize and control the tailings and other residual radioactive materials located on the inactive uranium processing sites in a safe and environmentally sound manner and to minimize or eliminate potential radiation health hazards. Commercial and residential properties in the vicinity of designated processing sites that are contaminated with material from the sites, herein referred to as vicinity properties,'' are also eligible for remedial action. Included in the UMTRA Project are 24 inactive uranium processing sites and associated vicinity properties located in 10 states, and the vicinity properties associated with Edgemont, South Dakota, an inactive uranium mill currently owned by the Tennessee Valley Authority (TVA).

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

International Nuclear Information System (INIS)

1977-08-01

No information is available on past uranium exploration in El Salvador. The foetallogenic map of Central America (ICAITI, 1970) shows no uranium occurrences, and no descriptions of occurrences are available for this study. Information on current uranium exploration in El Salvador is not available. The 1922 mining code, as amended, covers all minerals, with special rules applicable to phosphates, petroleum and other hydrocarbons. The state owns all minerals, including phosphates, except for salt and other common materials. Mineral and surface rights are distinct. Both citizens and aliens may acquire mineral rights. There is a possibility of uranium potential in the clastic sediments containing interbedded volcanics, particularly where the latter are tuffaceous. These rocks occur chiefly in the north western part of the country and are of limited areal extent. The possibility of uranium occurrences associated with acid volcanics cannot be discounted, but it is difficult to evaluate rocks of this type for uranium with the present state of knowledge. Accordingly, potential resources are estimated at between 0 and 1,000 tonnes uranium

Uranium resources in the United States

International Nuclear Information System (INIS)

Grenon, Michel.

1975-01-01

The United States are certainly the country which is the most concerned by a better evaluation of uranium resources. This is so because of the importance of the American nuclear program and because of a certain number of doubts in their uranium supply. This is probably why studies concerning American uranium resources have been very frequent in recent months. Although, most of these studies are not yet finished it is perhaps possible to draw a few conclusions in order to better see the framework of this important uranium resources problem. This is what this article attempts, using among other studies, the one carried-out for the National Science Foundation which is among the most complete, especially concerning the complete range of resources [fr

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)

Detailed geochemical study of the Dan River-Danville Triassic Basin, North Carolina and Virginia. National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

Thayer, P.A.; Cook, J.R.

1982-08-01

This abbreviated data report presents results of surface geochemical reconnaissance in the Dan River-Danville Triassic Basin of north-central North Carolina and south-central Virginia. Unweathered rock samples were collected at 380 sites within the basin at a nominal sampling density of one site per square mile. Field measurements and observations are reported for each site; analytical data and field measurements are presented in tables and maps. A detailed four-channel spectrometric survey was conducted, and the results are presented as a series of symbol plot maps for eU, eTh, and eU/eTh. Data from rock sample sites (on microfiche in pocket) include rock type and color and elemental analyses for U, Th, Hf, Al, Ce, Dy, Eu, Fe, La, Lu, Mn, Na, Sc, Sm, Ti, V, and Yb. Elemental uranium in 362 sedimentary rock samples from the Dan River-Danville Basin ranges from a low of 0.1 to a maximum of 13.3 parts per million (ppM). The log mean uranium concentration for these same samples is 0.37 ppM, and the log standard deviation is 0.24 ppM. Elemental uranium in 10 diabase dike samples from within the basin is in the range 0.1 to 0.7 ppM. The log mean uranium concentration for diabase samples is -.65 ppM, and the log standard deviation is 0.27. This report is issued in draft form, without detailed technical and copy editing. This was done to make the report available to the public before the end of the NURE program

Evaluation of the uranium market and its consequences in the strategy of a nuclear fuel supplier that is also a uranium producer

International Nuclear Information System (INIS)

Esteves, R.G.

2005-01-01

On January 2005, the uranium spot market price reached the value of $21.00/lbU3O8. One month before, at the end of December, the average price was $20.70/lbU3O8 and in November the spot price registered $20.50. When we review this abstract, on July 2005, the price has reached $30.00/lbU3O8. In 1984, the uranium spot price dropped below the twenties and remained so reaching meanwhile even one-digit values, even considering that the uranium offer in this period was always below the demand. The main reason for that distortion in the market was and still is, the interference of the developing countries governments after the end of the cold war The Industrias Nucleares do Brasil - INB is in an odd situation in the market of fuel suppliers due to being also a uranium producer and in short future will also be an enrichment services supplier. This peculiar position brings additional advantages due to the flexibility to play with the uranium costs versus tail assay to optimize its nuclear fuel costs. That odd position, equivalent only in the market to AREVA, allows INB to exchange uranium by SWU and vice versa according to its uranium cost (not market sell price) and in the future to the SWU's costs obtaining a better margin that can not be reached by other fuel suppliers. In the first part of this paper it is evaluated, based on the recent market information, the consequences in the 2004 uranium spot price, expected to be more emphasized during 2005. This paper also evaluate the market mechanisms for expecting the price to cross the $40/lbU3O8 in short time The market supply mechanisms used up to now to fulfil the market deficit may be interrupted in case the developing countries governments stop the availability of the non civil uranium reserves from its stockpile. Different hypotheses for supplying the primary uranium deficit in this last case are analyzed in this work and evaluated its consequences. The solution of reducing the actual tails assay used aiming at

Evaluation formulas of manpower needs for dismantling of equipments in uranium refining and conversion plant

International Nuclear Information System (INIS)

Izumo, Sari; Usui, Hideo; Kubota, Shintaro; Tachibana, Mitsuo; Kawagoshi, Hiroshi; Tokuyasu, Takashi; Takahashi, Nobuo; Morimoto, Yasuyuki; Tanaka, Yoshio; Sugitsue, Noritake

2014-07-01

Japan Atomic Energy Agency has developed PROject management data evaluation code for DIsmantling Activities (PRODIA) to make an efficient decommissioning for nuclear facilities. PRODIA is a source code which provides estimated value such as manpower needs, costs, etc., for dismantling by evaluation formulas according to the type of nuclear facility. Evaluation formulas of manpower needs for dismantling of equipments about reprocessed uranium conversion in Uranium Refining and Conversion Plant (URCP) have been developed in this report. In the result, evaluation formulas of manpower needs for dismantling of equipment were derived based on the classifications of equipment's functions or work items. These evaluation formulas are widely applicable to the estimation of the manpower needs for dismantling the other nuclear facilities, in particular uranium handling facilities. It was confirmed that some of these evaluation formulas with the same applicable condition could be unified to some inclusive evaluation formulas. It turned out that all steel equipment contaminated by uranium could be evaluated by one evaluation formula. (author)

National Uranium Resource Evaluation: Lovelock Quadrangle, Nevada and California

International Nuclear Information System (INIS)

Berry, V.P.; Bradley, M.T.; Nagy, P.A.

1982-08-01

Uranium resources of the Lovelock Quadrangle, Nevada and California, were evaluated to a depth of 1500 m using available surface and subsurface geological information. Uranium occurrences reported in the literature and in reports of the Atomic Energy Commission were located, sampled, and described in detail. Areas of anomalous radioactivity, as interpreted from the aerial radiometric reconnaissance survey and from the hydrochemical and stream-sediment reconnaissance survey reports, were also investigated. A general reconnaissance of the geologic environments exposed in surface outcrops was carried out; and over 400 rock, sediment, and water geochemical analyses were made from the samples taken. Additionally, 119 rock samples were petrographically studied. A total of 21 occurrences were located, sampled, and described in detail. Six uranium occurrences, previously unreported in the literature, were located during hydrogeochemical and stream-sediment reconnaissance, aerial radiometric reconnaissance survey followup, or general outcrop reconnaissance. Nine areas of uranium favorability were delineated within the Lovelock Quadrangle. One area, which contains the basal units of the Hartford Hill Rhyolite, is favorable for hydroallogenic uranium deposits. Eight areas are favorable for uranium deposits in playa sediments. These playas are considered favorable for nonmarine carbonaceous sediment deposits and evaporative deposits. The total volume of rock in favorable areas of the Lovelock Quadrangle is estimated to be 190 km 3 . The remaining geologic units are considered to be unfavorable for uranium deposits. These include upper Paleozoic and Mesozoic volcanic, plutonic, sedimentary, and metamorphic rocks. Also unfavorable are Tertiary and Quaternary volcanic flows and intrusive phases, tuffs, and sediments

Research on interactive genetic-geological models to evaluate favourability for undiscovered uranium resources

International Nuclear Information System (INIS)

Finch, W.I.; Granger, H.C.; Lupe, R.; McCammon, R.B.

1980-01-01

Current methods of evaluating favourability for undiscovered uranium resources are unduly subjective, quite possibly inconsistent and, as a consequence, of questionable reliability. This research is aimed at reducing the subjectivity and increasing the reliability by designing an improved method that depends largely on geological data and their statistical frequency of occurrence. This progress report outlines a genetic approach to modelling the geological factors that controlled uranium mineralization in order to evaluate the favourability for the occurrence of undiscovered uranium deposits of the type modelled. A genetic model is constructed from all the factors that describe the processes, in chronological sequence, that formed uranium deposits thought to have a common origin. The field and laboratory evidence for the processes constitute a geologic-occurrence base that parallels the chronological sequence of events. The genetic model and the geologic-occurrence base are portrayed as two columns of an interactive matrix called the ''genetic-geologic model''. For each column, eight chronological stages are used to describe the overall formation of the uranium deposits. These stages consist of (1) precursor processes; (2) host-rock formation; (3) preparation of host-rock; (4) uranium-source development; (5) transport of uranium; (6) primary uranium deposition; (7) post-deposition modification; and (8) preservation. To apply the genetic-geological model to evaluate favourability, a question is posed that determines the presence or absence of each attribute listed under the geologic-occurrence base. By building a logic circuit of the attributes according to either their essential or non-essential nature, the resultant match between a well-documented control area and the test area may be determined. The degree of match is a measure of favourability for uranium occurrence as hypothesized in the genetic model

Selected bibliography for the extraction of uranium from seawater: evaluation of uranium resources and plant siting

Energy Technology Data Exchange (ETDEWEB)

Chen, A.C.T.; Gordon, L.I.; Rodman, M.R.; Binney, S.E.

1979-02-06

This bibliography contains 471 references pertaining to the evaluation of U.S. territorial ocean waters as a potential uranium resource and to the selection of a site for a plant designed for the large scale extraction of uranium from seawater. This bibliography was prepared using machine literature retrieval, bibliographic, and work processing systems at Oregon State University. The literature cited is listed by author with indices to the author's countries, geographic areas of study, and to a set of keywords to the subject matter.

Selected bibliography for the extraction of uranium from seawater: evaluation of uranium resources and plant siting

International Nuclear Information System (INIS)

Chen, A.C.T.; Gordon, L.I.; Rodman, M.R.; Binney, S.E.

1979-01-01

This bibliography contains 471 references pertaining to the evaluation of U.S. territorial ocean waters as a potential uranium resource and to the selection of a site for a plant designed for the large scale extraction of uranium from seawater. This bibliography was prepared using machine literature retrieval, bibliographic, and work processing systems at Oregon State University. The literature cited is listed by author with indices to the author's countries, geographic areas of study, and to a set of keywords to the subject matter

Achievements of the French laser uranium enrichment program and final demonstrations

International Nuclear Information System (INIS)

Bordier, G.

2006-01-01

The research on Atomic Vapor Laser Isotope Separation (SILVA in French) started in France during the seventies at the Commissariat a l'Energie Atomique (CEA) through basic experiments on uranium spectroscopy and evaporation. The program gained momentum rapidly with the decision in 1985 to focus on SILVA while decreasing the research on chemical exchange process, centrifugation and laser molecular route. Similar orientations were taken during the same period in the US and in Japan. The French need in uranium enrichment service, around 5 MSWU (million Separation Work Units) for 45 electronuclear reactors in 1985, was fulfilled by gaseous diffusion in EURODIF (multinational consortium). But the expected increase in the international need, especially in Asia, and the high cost of the energy power supply necessary for gaseous diffusion were the main reasons to search for a very efficient and selective new generation enrichment process like SILVA. The scientific demonstration of the SILVA process was completed in the mid 1990's with grams of separated uranium at both the requested industrial enriched and tail assays simultaneously. However, in the late 90's, some technical difficulties appeared in the scaling up of the process to produce kilograms of enriched uranium. In 1998 a scientific peer review defined some general goals and improvements to be performed, partly reached on the Pelleas facility in Saclay, two years later. In parallel the centrifugation technology made important progress (in Europe, URENCO consortium and in Japan) related to the emergence of high performance carbon fibers. In September 2000, a French ministerial nuclear committee chose the centrifugation as the reference industrial technology to substitute for gaseous diffusion in 2010-2015: SILVA was not enough mature and competitive to be developed at an industrial scale within such a delay. In order to save properly the knowledge and to account for potential future uses, the committee settled on a

Comparative evaluation of liner materials for inactive uranium-mill-tailings piles

International Nuclear Information System (INIS)

Buelt, J.L.; Barnes, S.M.

1981-01-01

Under the funding of the Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Program, Pacific Northwest Laboratory (PNL) has completed the initial accelerated testing phase of eight candidate liner materials. The tests were designed to comparatively evaluate the long term effectiveness of liner materials as a radionuclide and hazardous chemical leachate barrier. The eight materials tested were selected from a technical review of published literature and industrial specialists. Conditions were then identified that would accelerate the aging processes expected in a uranium tailings environment for 1000 years. High calcium leachates were forced through thin layers of clay liners to accelerate the ion exchange rate of sodium and calcium. Asphalt and synthetic materials were accelerated by exposure to elevate temperatures, high concentrations of oxygen, and increased strengths of aqueous oxidizing agents. By comparing the changes of permeability with time of exposure, the most acceptable materials were then identified. These materials are a catalytically airblown asphalt membrane and natural soil amended with sodium bentonite. Both materials showed an increased resistance to leachate penetration throughout the exposure period with final permeabilities less than 10 -7 cm/s. In addition, the asphalt membrane and sodium bentonite are among the least expensive materials to install at a disposal site. Therefore based on their economic and technical merits, these two materials are being evaluated further in field tests at Grand Junction, Colorado

Monitoring program design recommendations for uranium mining communities

International Nuclear Information System (INIS)

1978-10-01

Environmental radiological monitoring requirements and their rationale have been developed for operating uranium mine/mill sites including the pre-operational phase, and for non-operating tailings areas, in order to assess the radiological impact on the environment and follow long-term trends. These recommendations have been based on a review of regulatory standards, sources and nature of releases from mines, mills and tailings, and environmental pathway analysis. Media and measurements considered in the routine on-going programs include airborne radon, airborne particulates, external radiation, terrestrial biota, surface water, drinking water, ground water, fish and sediment. Program implementation guides are provided. An overview of sampling and field technique and specific recommendations have been made. (auth)

Uranium recovery from low-level aqueous sources

International Nuclear Information System (INIS)

Kelmers, A.D.; Goeller, H.E.

1981-03-01

The aqueous sources of soluble uranium were surveyed and evaluated in terms of the uranium geochemical cycle in an effort to identify potential unexploited resources. Freshwater sources appeared to be too low in uranium content to merit consideration, while seawater, although very dilute (approx. 3.3 ppB), contains approx. 4 x 10 9 metric tons of uranium in all the world's oceans. A literature review of recent publications and patents concerning uranium recovery from seawater was conducted. Considerable experimental work is currently under way in Japan; less is being done in the European countries. An assessment of the current state of technology is presented in this report. Repeated screening programs have identified hydrous titanium oxide as the most promising candidate absorbent. However, some of its properties such as distribution coefficient, selectivity, loading, and possibly stability appear to render its use inadequate in a practical recovery system. Also, various assessments of the energy efficiency of pumped or tidal power schemes for contacting the sorbent and seawater are in major disagreement. Needed future research and development tasks are discussed. A fundamental sorbent development program to greatly improve sorbent properties would be required to permit practical recovery of uranium from seawater. Major unresolved engineering aspects of such recovery systems are also identified and discussed

National Uranium Resource Evaluation: Newcastle Quadrangle, Wyoming and South Dakota

International Nuclear Information System (INIS)

Santos, E.S.; Robinson, K.; Geer, K.A.; Blattspieler, J.G.

1982-09-01

Uranium resources of the Newcastle 1 0 x2 0 Quadrangle, Wyoming and South Dakota were evaluated to a depth of 1500 m (5000 ft) using available surface and subsurface geologic information. Many of the uranium occurrences reported in the literature and in reports of the US Atomic Energy Commission were located, sampled and described. Areas of anomalous radioactivity, interpreted from an aerial radiometric survey, were outlined. Areas favorable for uranium deposits in the subsurface were evaluated using gamma-ray logs. Based on surface and subsurface data, two areas have been delineated which are underlain by rocks deemed favorable as hosts for uranium deposits. One of these is underlain by rocks that contain fluvial arkosic facies in the Wasatch and Fort Union Formations of Tertiary age; the other is underlain by rocks containing fluvial quartzose sandstone facies of the Inyan Kara Group of Early Cretaceous age. Unfavorable environments characterize all rock units of Tertiary age above the Wasatch Formation, all rock units of Cretaceous age above the Inyan Kara Group, and most rock units of Mesozoic and Paleozoic age below the Inyan Kara Group. Unfavorable environments characterize all rock units of Cretaceous age above the Inyan Kara Group, and all rock units of Mesozoic and Paleozoic age below the Inyan Kara Group

National Uranium Resource Evaluation: Newcastle Quadrangle, Wyoming and South Dakota

Energy Technology Data Exchange (ETDEWEB)

Santos, E S; Robinson, K; Geer, K A; Blattspieler, J G

1982-09-01

Uranium resources of the Newcastle 1/sup 0/x2/sup 0/ Quadrangle, Wyoming and South Dakota were evaluated to a depth of 1500 m (5000 ft) using available surface and subsurface geologic information. Many of the uranium occurrences reported in the literature and in reports of the US Atomic Energy Commission were located, sampled and described. Areas of anomalous radioactivity, interpreted from an aerial radiometric survey, were outlined. Areas favorable for uranium deposits in the subsurface were evaluated using gamma-ray logs. Based on surface and subsurface data, two areas have been delineated which are underlain by rocks deemed favorable as hosts for uranium deposits. One of these is underlain by rocks that contain fluvial arkosic facies in the Wasatch and Fort Union Formations of Tertiary age; the other is underlain by rocks containing fluvial quartzose sandstone facies of the Inyan Kara Group of Early Cretaceous age. Unfavorable environments characterize all rock units of Tertiary age above the Wasatch Formation, all rock units of Cretaceous age above the Inyan Kara Group, and most rock units of Mesozoic and Paleozoic age below the Inyan Kara Group. Unfavorable environments characterize all rock units of Cretaceous age above the Inyan Kara Group, and all rock units of Mesozoic and Paleozoic age below the Inyan Kara Group.

Western states uranium resource survey

International Nuclear Information System (INIS)

Tinney, J.F.

1977-01-01

ERDA's National Uranium Resource Evaluation (NURE) program was established to provide a comprehensive description of uranium resources in the United States. To carry out this task, ERDA has contracted with various facilities, including universities, private companies, and state agencies, to undertake projects such as airborne radiometric surveys, geological and geochemical studies, and the development of advanced geophysical technology. LLL is one of four ERDA laboratories systematically studying uranium distribution in surface water, groundwater, and lake and stream sediments. We are specifically responsible for surveying seven western states. This past year we have designed and installed facilities for delayed-neutron counting and neutron-activation analysis, completed seven orientation surveys, and analyzed several thousand field samples. Full-scale reconnaissance surveys began last fall

Profile of World Uranium Enrichment Programs - 2007

International Nuclear Information System (INIS)

Laughter, Mark D.

2007-01-01

of the future, but has yet to be demonstrated commercially. In the early 1980s, six countries developing gas centrifuge technology (United States, United Kingdom, Germany, the Netherlands, Japan, and Australia) along with the International Atomic Energy Agency (IAEA) and the European Atomic Energy Community (EURATOM) began developing effective safeguards techniques for GCEPs. This effort was known as the Hexapartite Safeguards Project (HSP). The HSP had the goal of maximizing safeguards effectiveness while minimizing the cost to the operator and inspectorate, and adopted several recommendations, such as the acceptance of limited-frequency unannounced access (LFUA) inspections in cascade halls, and the use of nondestructive assay (NDA) measurements and tamper-indicating seals. While only the HSP participants initially committed to implementing all the measures of the approach, it has been used as a model for the safeguards applied to GCEPs in additional states. This report provides a snapshot overview of world enrichment capacity in 2007, including profiles of the uranium enrichment programs of individual states. It is based on open-source information, which is dependent on unclassified sources and may therefore not reflect the most recent developments. In addition, it briefly describes some of the safeguards techniques being used at various enrichment plants, including implementation of HSP recommendations

Underground geologic evaluation of the Grossschloppen vein-uranium deposit, West Germany

International Nuclear Information System (INIS)

Moore, S.C.; Erickson, A.J.; Kolb, S.G.; Maclean, C.J.

1983-01-01

The Grossschloppen vein-uranium deposit, Bavaria, West Germany, was examined utilizing underground workings during 1980-82 by Esso Er/ZETA/ GMbH, an affiliate of Exxon Minerals Company (EMC). Geologic evaluation entailed dense drilling of a portion of the deposit from workings constructed specifically for the program. Discovered in 1977, the deposit was initially explored by surface diamond drillholes which allowed definition of a 30-60 m wide vein system discontinuously mineralized along a 1000 m strike length and to at least a 450 m depth. The underground program was conceived as a cost effective procedure to answer questions on vein correlation, grade continuity and variability. A 1200 m decline allowed access for detailed sampling of approximately 10% of the known area of mineralization. Fanned drillholes, logged by gamma probe, were spaced to provide intersections of veins at 10 to 20 m intervals. Six cross cuts also penetrate the pitchblende and uranophane mineralization which occurs in 0.1 to 2.5 m thick quartz veins. Detailed cross-sections and level plans were constructed for resource estimates of the intensively studied portion of the vein system. The program resulted in the discovery of local, high grade areas and an average grade in the evaluated area nearly double that expected from surface drilling

National Uranium Resource Evaluation. Volume 1. Summary of the geology and uranium potential of Precambrian conglomerates in southeastern Wyoming

Energy Technology Data Exchange (ETDEWEB)

Karlstrom, K.E.; Houston, R.S.; Flurkey, A.J.; Coolidge, C.M.; Kratochvil, A.L.; Sever, C.K.

1981-02-01

A series of uranium-, thorium-, and gold-bearing conglomerates in Late Archean and Early Proterozoic metasedimentary rocks have been discovered in southern Wyoming. The mineral deposits were found by applying the time and strata bound model for the origin of uranium-bearing quartz-pebble conglomerates to favorable rock types within a geologic terrane known from prior regional mapping. No mineral deposits have been discovered that are of current (1981) economic interest, but preliminary resource estimates indicate that over 3418 tons of uranium and over 1996 tons of thorium are present in the Medicine Bow Mountains and that over 440 tons of uranium and 6350 tons of thorium are present in Sierra Madre. Sampling has been inadequate to determine gold resources. High grade uranium deposits have not been detected by work to date but local beds of uranium-bearing conglomerate contain as much as 1380 ppM uranium over a thickness of 0.65 meters. This project has involved geologic mapping at scales from 1/6000 to 1/50,000 detailed sampling, and the evaluation of 48 diamond drill holes, but the area is too large to fully establish the economic potential with the present information. This first volume summarizes the geologic setting and geologic and geochemical characteristics of the uranium-bearing conglomerates. Volume 2 contains supporting geochemical data, lithologic logs from 48 drill holes in Precambrian rocks, and drill site geologic maps and cross-sections from most of the holes. Volume 3 is a geostatistical resource estimate of uranium and thorium in quartz-pebble conglomerates.

National Uranium Resource Evaluation. Volume 1. Summary of the geology and uranium potential of Precambrian conglomerates in southeastern Wyoming

International Nuclear Information System (INIS)

Karlstrom, K.E.; Houston, R.S.; Flurkey, A.J.; Coolidge, C.M.; Kratochvil, A.L.; Sever, C.K.

1981-02-01

A series of uranium-, thorium-, and gold-bearing conglomerates in Late Archean and Early Proterozoic metasedimentary rocks have been discovered in southern Wyoming. The mineral deposits were found by applying the time and strata bound model for the origin of uranium-bearing quartz-pebble conglomerates to favorable rock types within a geologic terrane known from prior regional mapping. No mineral deposits have been discovered that are of current (1981) economic interest, but preliminary resource estimates indicate that over 3418 tons of uranium and over 1996 tons of thorium are present in the Medicine Bow Mountains and that over 440 tons of uranium and 6350 tons of thorium are present in Sierra Madre. Sampling has been inadequate to determine gold resources. High grade uranium deposits have not been detected by work to date but local beds of uranium-bearing conglomerate contain as much as 1380 ppM uranium over a thickness of 0.65 meters. This project has involved geologic mapping at scales from 1/6000 to 1/50,000 detailed sampling, and the evaluation of 48 diamond drill holes, but the area is too large to fully establish the economic potential with the present information. This first volume summarizes the geologic setting and geologic and geochemical characteristics of the uranium-bearing conglomerates. Volume 2 contains supporting geochemical data, lithologic logs from 48 drill holes in Precambrian rocks, and drill site geologic maps and cross-sections from most of the holes. Volume 3 is a geostatistical resource estimate of uranium and thorium in quartz-pebble conglomerates

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)

Gravimetric determination of uranium in SALE samples

International Nuclear Information System (INIS)

Anon.

1981-01-01

As a participant in the Safeguards Analytical Laboratory Evaluation (SALE) program, the Analytical Chemistry Laboratory at General Atomic routinely assays uranium dioxide and uranyl nitrate SALE samples for uranium content. Gravimetric methods are relatively easy and inexpensive to apply when the samples for uranium content. Gravimetric methods are relatively easy and inexpensive to apply when the samples are free from substantial amounts of metallic impurities. Clearly the gravimetric procedure alone is not specific for uranium and must be enhanced by the use of impurity corrections. Emission spectrography is used routinely as the technique of choice for making such corrections. In cases where it is essential to assay specifically for uranium, the modified Davies-Gray titration using a weighed titrant method is applied. In this paper some essential features of these gravimetric and titrimetric procedures are discussed

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, 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 determination in natural U O2 samples for the laboratory intercomparison program of Agencia Brasileiro-Argentina de Contabilidade e Controle de Materiais Nucleares (ABACC)

International Nuclear Information System (INIS)

Avelar, Marta M.; Palmieri, Helena E.L.; Reis Fagundes, Oliene dos

1997-01-01

The modified Davies and Gray method for uranium titration to analyse nuclear materials is the procedure used by the CDTN's chemical laboratory. Its analytical performance was evaluated through the participation in the intercomparison program with the Brazilian - Argentine Agency for Accountability and Control of Nuclear Materials (ABACC). One sample of natural uranium dioxide was analysed. The precision and accuracy of the measurements are reported and discussed in this paper. (author). 7 refs., 1 fig., 2 tabs

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

International Nuclear Information System (INIS)

1977-08-01

In 1953, the U.S. Atomic Energy Commission, on invitation of the government of Honduras, conducted uranium reconnaissance in parts of the country. The survey consisted of scintillometric examination of all formations, veins, dikes, sills and contacts along more than 1,500 km of road. Additionally, 17 mines and prospects were examined, but in no location were uranium occurrences found. The largest and most consistently radioactive deposit noted was a body of volcanic ash at Santa Rosa de Copan, a sample of which assayed 15 ppm U 3 O 8 . A uranium prospect has been described from the Yatnala area in northwest Honduras. Uraninite and oxidation products occur in association with copper and mercury minerals in veinlets as well as disseminations in a Lower Cretaceous limestone conglomerate, the llama Formation. The llama Formation is the conglomeratic facies of the Atima (limestone) Formation, both of which are in the Yojoa Group. At the time of the U. N. development program survey in May, 1970, no uranium deposits were known in Honduras. Information is not available on current exploration in Honduras. The state owns most mineral deposits but may grant rights for exploration and exploitation of the subsoil. Mineral and surface titles are separate. Deposits of uranium and its salts, thorium and similar atomic energy substances are reserved to the state. Foreign citizens and companies, with some exceptions, may acquire mineral rights. Several groups of sediments might be of interest for uranium exploration. The Todos Santos redbeds and the El Plan Formation are both shallow marine and hence may contain marginal marine facies favorable for uranium. In the southern and central Cordillera, the Valle de Angeles sediments, particularly the sandstones, may be of interest. The contacts between Permian granites and schists (Paleozoic) may also warrant attention. Lacking further information on which to base a more optimistic outlook, it is estimated that the uranium potential of

Risk evaluation of uranium mining: A geochemical inverse modelling approach

Science.gov (United States)

Rillard, J.; Zuddas, P.; Scislewski, A.

2011-12-01

It is well known that uranium extraction operations can increase risks linked to radiation exposure. The toxicity of uranium and associated heavy metals is the main environmental concern regarding exploitation and processing of U-ore. In areas where U mining is planned, a careful assessment of toxic and radioactive element concentrations is recommended before the start of mining activities. A background evaluation of harmful elements is important in order to prevent and/or quantify future water contamination resulting from possible migration of toxic metals coming from ore and waste water interaction. Controlled leaching experiments were carried out to investigate processes of ore and waste (leached ore) degradation, using samples from the uranium exploitation site located in Caetité-Bahia, Brazil. In experiments in which the reaction of waste with water was tested, we found that the water had low pH and high levels of sulphates and aluminium. On the other hand, in experiments in which ore was tested, the water had a chemical composition comparable to natural water found in the region of Caetité. On the basis of our experiments, we suggest that waste resulting from sulphuric acid treatment can induce acidification and salinization of surface and ground water. For this reason proper storage of waste is imperative. As a tool to evaluate the risks, a geochemical inverse modelling approach was developed to estimate the water-mineral interaction involving the presence of toxic elements. We used a method earlier described by Scislewski and Zuddas 2010 (Geochim. Cosmochim. Acta 74, 6996-7007) in which the reactive surface area of mineral dissolution can be estimated. We found that the reactive surface area of rock parent minerals is not constant during time but varies according to several orders of magnitude in only two months of interaction. We propose that parent mineral heterogeneity and particularly, neogenic phase formation may explain the observed variation of the

Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved

International Nuclear Information System (INIS)

Andriot, J.; Gaussens, J.

1958-01-01

A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author) [fr

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Cameroon

International Nuclear Information System (INIS)

1985-01-01

A report has recently been published which describes the findings of the International Uranium Resources Evaluation Project (IUREP) Mission to Cameroon. The IUREP Orientation Phase Mission to Cameroon estimates the Speculative Resources of that country to be in the order of 10 000 tonnes uranium for syenite-associated U-deposits in southern Cameroon, and in the order of 5 000 tonnes uranium for uranium deposits associated with albitized and desilicified late tectonic Panafrican granites (episyenite) and Paleozoic volcanics in northern Cameroon. No specific tonnage is given for Francevillian equivalents (DJA-Series) and for Mesozoic and Cenozoic sedimentary basins, which are thought to hold limited potential for sandstone hosted uranium. However the Douala basin, consisting of mixed marine and continental sequences merits some attention. No specific budget and programme for uranium exploration are proposed for Cameroon. Instead specific recommendations concerning specific potential environments and general recommendation concerning the methodology of exploration are made. (author)

Uranium energy dependence

International Nuclear Information System (INIS)

Erkes, P.

1981-06-01

Uranium supply and demand as projected by the Uranium Institute is discussed. It is concluded that for the industrialized countries, maximum energy independence is a necessity. Hence it is necessary to achieve assurance of supply for uranium used in thermal power reactors in current programs and eventually to move towards breeders

Uranium soils integrated demonstration: Soil characterization project report

International Nuclear Information System (INIS)

Cunnane, J.C.; Gill, V.R.; Lee, S.Y.; Morris, D.E.; Nickelson, M.D.; Perry, D.L.; Tidwell, V.C.

1993-08-01

An Integrated Demonstration Program, hosted by the Fernald Environmental Management Project (FEMP), has been established for investigating technologies applicable to the characterization and remediation of soils contaminated with uranium. Critical to the design of relevant treatment technologies is detailed information on the chemical and physical characteristics of the uranium waste-form. To address this need a soil sampling and characterization program was initiated which makes use of a variety of standard analytical techniques coupled with state-of-the-art microscopy and spectroscopy techniques. Sample representativeness is evaluated through the development of conceptual models in an effort to identify and understand those geochemical processes governing the behavior of uranium in FEMP soils. Many of the initial results have significant implications for the design of soil treatment technologies for application at the FEMP

Uranium soils integrated demonstration: Soil characterization project report

Energy Technology Data Exchange (ETDEWEB)

Cunnane, J.C. [Argonne National Lab., IL (United States); Gill, V.R. [Fernald Environmental Restoration Management Corp., Cincinnati, OH (United States); Lee, S.Y. [Oak Ridge National Lab., TN (United States); Morris, D.E. [Los Alamos National Lab., NM (United States); Nickelson, M.D. [HAZWRAP, Oak Ridge, TN (United States); Perry, D.L. [Lawrence Berkeley Lab., CA (United States); Tidwell, V.C. [Sandia National Labs., Albuquerque, NM (United States)

1993-08-01

An Integrated Demonstration Program, hosted by the Fernald Environmental Management Project (FEMP), has been established for investigating technologies applicable to the characterization and remediation of soils contaminated with uranium. Critical to the design of relevant treatment technologies is detailed information on the chemical and physical characteristics of the uranium waste-form. To address this need a soil sampling and characterization program was initiated which makes use of a variety of standard analytical techniques coupled with state-of-the-art microscopy and spectroscopy techniques. Sample representativeness is evaluated through the development of conceptual models in an effort to identify and understand those geochemical processes governing the behavior of uranium in FEMP soils. Many of the initial results have significant implications for the design of soil treatment technologies for application at the FEMP.

Undiscovered resource evaluation: Towards applying a systematic approach to uranium

International Nuclear Information System (INIS)

Fairclough, M.; Katona, L.

2014-01-01

Evaluations of potential mineral resource supply range from spatial to aspatial, and everything in between across a range of scales. They also range from qualitative to quantitative with similar hybrid examples across the spectrum. These can compromise detailed deposit-specific reserve and resource calculations, target generative processes and estimates of potential endowments in a broad geographic or geological area. All are estimates until the ore has been discovered and extracted. Contemporary national or provincial scale evaluations of mineral potential are relatively advanced and some include uranium, such as those for South Australia undertaken by the State Geological Survey. These play an important role in land-use planning as well as attracting exploration investment and range from datato knowledge-driven approaches. Studies have been undertaken for the Mt Painter region, as well as for adjacent basins. The process of estimating large-scale potential mineral endowments is critical for national and international planning purposes but is a relatively recent and less common undertaking. In many cases, except at a general level, the data and knowledge for a relatively immature terrain is lacking, requiring assessment by analogy with other areas. Commencing in the 1980s, the United States Geological Survey, and subsequently the Geological Survey of Canada evaluated a range of commodities ranging from copper to hydrocarbons with a view to security of supply. They developed innovative approaches to, as far as practical, reduce the uncertainty and maximise the reproducibility of the calculations in information-poor regions. Yet the approach to uranium was relatively ad hoc and incomplete (such as the US Department of Energy NURE project). Other historic attempts, such as the IAEA-NEA International Uranium Resource Evaluation Project (IUREP) in the 1970s, were mainly qualitative. While there is still no systematic global evaluation of undiscovered uranium resources

User's guide for the Uranium Ore Reserve Calculation System (URAD)

International Nuclear Information System (INIS)

1988-12-01

The URAD (Uranium Reserves and Data) system consists of four computer programs designed to facilitate the evaluation of uranium ore reserves analysis and the handling of basic uranium assay data. URAD is designed specifically as a training tool for anyone unfamiliar with the methodology, data requirements, and/or general computer applications in the field of uranium ore reserves analysis. However, it can effectively be used in a 'production' environment involving considerable amounts of data. The resulting programs are written in Microsoft FORTRAN (Version 3.1) and may be run on any IBM-compatible microcomputer under DOS 2.1 (or later). Only a basic working knowledge of DOS 2.1 is needed to maintain the system and run the programs. This guide includes the overview of the URAD system, the review of sample data and a complete description of the file structure and sample type formats of the basic sample data files. Program URDAT explains the initial processing of the primary UDAT files to obtain standard output listings and gamma-log interpretations of radiometric data, and to create intermediate UDAT files which are used by the ore reserves programs - RESUV, ORSAC, and SCOR. Figs and tabs

Occupational exposures to uranium: processes, hazards, and regulations

International Nuclear Information System (INIS)

Stoetzel, G.A.; Fisher, D.R.; McCormack, W.D.; Hoenes, G.R.; Marks, S.; Moore, R.H.; Quilici, D.G.; Breitenstein, B.D.

1981-04-01

The United States Uranium Registry (USUR) was formed in 1978 to investigate potential hazards from occupational exposure to uranium and to assess the need for special health-related studies of uranium workers. This report provides a summary of Registry work done to date. The history of the uranium industry is outlined first, and the current commercial uranium industry (mining, milling, conversion, enrichment, and fuel fabrication) is described. This description includes information on basic processes and areas of greatest potential radiological exposure. In addition, inactive commercial facilities and other uranium operations are discussed. Regulation of the commercial production industry for uranium fuel is reported, including the historic development of regulations and the current regulatory agencies and procedures for each phase of the industry. A review of radiological health practices in the industry - facility monitoring, exposure control, exposure evaluation, and record-keeping - is presented. A discussion of the nonradiological hazards of the industry is provided, and the final section describes the tissue program developed as part of the Registry

The significance of zircon characteristic and its uranium concentration in evaluation of uranium metallogenetic prospect

International Nuclear Information System (INIS)

Li Yaosong; Zhu Jiechen; Xia Yuliang

1992-02-01

Zircon characteristic and its relation to uranium metallogenetic process have been studied on the basis of physics properties and chemical compositions. It is indicated that the colour of zircon crystal is related to uranium concentration; on the basis of method of zircon population type of Pupin J.P., the sectional plan of zircon population type has been designed, from which result that zircon population type of uranium-producing rock body is distributed mainly in second section, secondly in fourth section; U in zircon presents synchronous increase trend with Th, Hf and Ta; the uranium concentration in zircon from uranium-producing geologic body increases obviously and its rate of increase is more than that of the uranium concentration in rock; the period, in which uranium concentration in zircon is increased, is often related to better uranium-producing condition in that period of this area. 1785 data of the average uranium concentration in zircon have been counted and clear regularity has been obtained, namely the average uranium concentrations in zircon in rich uranium-producing area, rock, geologic body and metallogenetic zone are all higher than that in poor or no uranium-producing area, rock, geologic body and metallogenetic zone. This shows that the average uranium concentration in zircon within the region in fact reflects the primary uranium-bearing background in region and restricts directly follow-up possibility of uranium mineralization. On the basis of this, the uranium source conditions of known uranium metallogenetic zones and prospective provinces have been discussed, and the average uranium concentrations in zircon from magmatic rocks for 81 districts have been contrasted and graded, and some districts in which exploration will be worth doing further are put forward

Process evaluations for uranium recovery from scrap material

International Nuclear Information System (INIS)

Westphal, B.R.; Benedict, R.W.

1992-01-01

The integral Fast Reactor (IFR) concept being developed by Argonne National Laboratory is based on pyrometallurgical processing of spent nuclear metallic fuel with subsequent fabrication into new reactor fuel by an injection casting sequence. During fabrication, a dilute scrap stream containing uranium alloy fines and broken quartz (Vycor) molds in produced. Waste characterization of this stream, developed by using present operating data and chemical analysis was used to evaluate different uranium recovery methods and possible process variations for the return of the recovered metal. Two methods, comminution with size separation and electrostatic separation, have been tested and can recover over 95% of the metal. Recycling the metal to either the electrochemical process or the injection casting was evaluated for the different economic and process impacts. The physical waste parameters and the important separation process variables are discussed with their effects on the viability of recycling the material. In this paper criteria used to establish the acceptable operating limits is discussed

Conversion of research and test reactors to low enriched uranium fuel: technical overview and program status

International Nuclear Information System (INIS)

Roglans-Ribas, J.

2008-01-01

Many of the nuclear research and test reactors worldwide operate with high enriched uranium fuel. In response to worries over the potential use of HEU from research reactors in nuclear weapons, the U.S Department of Energy (DOE) initiated a program - the Reduced Enrichment for Research and Test Reactors (RERTR) - in 1978 to develop the technology necessary to reduce the use of HEU fuel by converting research reactors to low enriched uranium (LEU) fuel. The Reactor Conversion program is currently under the DOE's National Nuclear Security Administration's Global Threat Reduction Initiative (GTRI). 55 of the 129 reactors included in the scope have been already converted to LEU fuel or have shutdown prior to conversion. The major technical activities of the Conversion Program include: (1) the development of advanced LEU fuels; (2) conversion analysis and conversion support; and (3) technology development for the production of Molybdenum-99 (Mo 99 ) with LEU targets. The paper provides an overview of the status of the program, the technical challenges and accomplishments, and the role of international collaborations in the accomplishment of the Conversion Program objectives. Nuclear research and test reactors worldwide have been in operation for over 60 years. Many of these facilities operate with high enriched uranium fuel. In response to increased worries over the potential use of HEU from research reactors in the manufacturing of nuclear weapons, the U.S Department of Energy (DOE) initiated a program - the Reduced Enrichment for Research and Test Reactors (RERTR) - in 1978 to develop the technology necessary to reduce the use of HEU fuel in research reactors by converting them to low enriched uranium (LEU) fuel. The reactor conversion program was initially focused on U.S.-supplied reactors, but in the early 1990s it expanded and began to collaborate with Russian institutes with the objective of converting Russian supplied reactors to the use of LEU fuel.

Evaluation of the LASL automated spectrophotometer for uranium determination at submilligram levels

International Nuclear Information System (INIS)

Hollen, R.M.; Jackson, D.D.; Rein, J.E.

1977-07-01

The LASL automated spectrophotometer, designed for determination of 1 to 14 mg of uranium and 0.5 to 14 mg of plutonium, has been evaluated for determination of lower levels of uranium to 0.12 mg. The essentially linear response of absorbance is maintained and the standard deviation for a single measurement is constant at about 0.013 mg of uranium, corresponding to a maximum uncertainty of about 10 percent at the 0.12-mg limit. The instrument was applied to the analysis of a series of low-level-concentration, 0.07- to 0.8-mg/ml uranium samples. The results were not statistically different from those obtained by a manual spectrophotometric method

Adsorbent Alkali Conditioning for Uranium Adsorption from Seawater. Adsorbent Performance and Technology Cost Evaluation

International Nuclear Information System (INIS)

Tsouris, Costas; Mayes, Richard T.; Janke, Christopher James; Dai, Sheng; Das, S.; Liao, W.P.; Kuo, Li-Jung; Wood, Jordana; Gill, Gary; Byers, Maggie Flicker; Schneider, Eric

2015-01-01

The Fuel Resources program of the Fuel Cycle Research and Development program of the Office of Nuclear Energy (NE) is focused on identifying and implementing actions to assure that nuclear fuel resources are available in the United States. An immense source of uranium is seawater, which contains an estimated amount of 4.5 billion tonnes of dissolved uranium. This unconventional resource can provide a price cap and ensure centuries of uranium supply for future nuclear energy production. NE initiated a multidisciplinary program with participants from national laboratories, universities, and research institutes to enable technical breakthroughs related to uranium recovery from seawater. The goal is to develop advanced adsorbents to reduce the seawater uranium recovery technology cost and uncertainties. Under this program, Oak Ridge National Laboratory (ORNL) has developed a new amidoxime-based adsorbent of high surface area, which tripled the uranium capacity of leading Japanese adsorbents. Parallel efforts have been focused on the optimization of the physicochemical and operating parameters used during the preparation of the adsorbent for deployment. A set of parameters that need to be optimized are related to the conditioning of the adsorbent with alkali solution, which is necessary prior to adsorbent deployment. Previous work indicated that alkali-conditioning parameters significantly affect the adsorbent performance. Initiated in 2014, this study had as a goal to determine optimal parameters such as base type and concentration, temperature, and duration of conditioning that maximize the uranium adsorption performance of amidoxime functionalized adsorbent, while keeping the cost of uranium production low. After base-treatment at various conditions, samples of adsorbent developed at ORNL were tested in this study with batch simulated seawater solution of 8-ppm uranium concentration, batch seawater spiked with uranium nitrate at 75-100 ppb uranium, and continuous

Adsorbent Alkali Conditioning for Uranium Adsorption from Seawater. Adsorbent Performance and Technology Cost Evaluation

Energy Technology Data Exchange (ETDEWEB)

Tsouris, Costas [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mayes, Richard T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Janke, Christopher James [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dai, Sheng [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Das, S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Liao, W. -P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Kuo, Li-Jung [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wood, Jordana [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gill, Gary [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Byers, Maggie Flicker [Univ. of Texas, Austin, TX (United States); Schneider, Eric [Univ. of Texas, Austin, TX (United States)

2015-09-30

The Fuel Resources program of the Fuel Cycle Research and Development program of the Office of Nuclear Energy (NE) is focused on identifying and implementing actions to assure that nuclear fuel resources are available in the United States. An immense source of uranium is seawater, which contains an estimated amount of 4.5 billion tonnes of dissolved uranium. This unconventional resource can provide a price cap and ensure centuries of uranium supply for future nuclear energy production. NE initiated a multidisciplinary program with participants from national laboratories, universities, and research institutes to enable technical breakthroughs related to uranium recovery from seawater. The goal is to develop advanced adsorbents to reduce the seawater uranium recovery technology cost and uncertainties. Under this program, Oak Ridge National Laboratory (ORNL) has developed a new amidoxime-based adsorbent of high surface area, which tripled the uranium capacity of leading Japanese adsorbents. Parallel efforts have been focused on the optimization of the physicochemical and operating parameters used during the preparation of the adsorbent for deployment. A set of parameters that need to be optimized are related to the conditioning of the adsorbent with alkali solution, which is necessary prior to adsorbent deployment. Previous work indicated that alkali-conditioning parameters significantly affect the adsorbent performance. Initiated in 2014, this study had as a goal to determine optimal parameters such as base type and concentration, temperature, and duration of conditioning that maximize the uranium adsorption performance of amidoxime functionalized adsorbent, while keeping the cost of uranium production low. After base-treatment at various conditions, samples of adsorbent developed at ORNL were tested in this study with batch simulated seawater solution of 8-ppm uranium concentration, batch seawater spiked with uranium nitrate at 75-100 ppb uranium, and continuous

Experimental evaluation of the detection threshold of uranium in urine samples

International Nuclear Information System (INIS)

Ferreyra, M. D.; Suarez Mendez, Sebastian; Tossi, Mirta H.

1999-01-01

The routine internal dosimetric tests for nuclear installations workers includes the determination of uranium in urine. The analysis is carried out, after chemical treatment, by UV fluorometry, comparing the results with urine blank samples from workers not exposed professionally to contamination. The fluctuation of the results of the uranium content in the blank samples greatly affects the determinations. In 30 blank samples the uranium content was determined and the results were evaluated by three calculation methods: 1) The procedure recommended by IUPAC; 2) The graphical method; 3) and The error propagation method. The last one has been adopted for the calculation of the detection threshold. (authors)

Testing and evaluation of existing techniques for identifying uptakes and measuring retention of uranium in mill workers

International Nuclear Information System (INIS)

1983-03-01

Preliminary tests and evaluations of existing bio-analytical techniques for identifying uptakes and measuring retention of uranium in mill workers were made at two uranium mills. Urinalysis tests were found to be more reliable indicators of uranium uptakes than personal air sampling. Static air samples were not found to be good indicators of personal uptakes. In vivo measurements of uranium in lung were successfully carried out in the presence of high and fluctuating background radiation. Interference from external contamination was common during end of shift measurements. A full scale study to evaluate model parameters for the uptake, retention and elimination of uranium should include, in addition to the above techniques, particle size determination of airborne uranium, solubility in simulated lung fluid, uranium analysis in faeces and bone and minute volume measurements for each subject

Uranium exploration and evaluation techniques

International Nuclear Information System (INIS)

Bowie, S.H.U.

1977-01-01

Ground, carborne and airborne surveys for uranium commenced with GM-counters and developed to total-count scintillation counters which have subsequently been replaced to some extent by gamma spectrometers. Stabilisation of the last mentioned is important and has only been achieved recently. Hydrogeochemistry has been revitalised by the introduction of neutron activation analysis and has considerable promise of success in the discovery of surface and near-surface uranium deposits. Soil, stream sediment and lake sediment analyses also have potential particularly in follow-up surveys. One of the most encouraging methods of detecting relatively deeply buried uranium ore bodies is by measuring the radon content of air retained in soil or sub-soil; also that dissolved in stream or lake water. Helium, particularly 4 He, which is also a decay product of uranium but which has an infinite half-life could be measured along with radon. Theoretically this could not only give additional information on buried ore bodies, but on the depth of burial. Another possible technique for use in the detection of buried ore bodies is that of measuring the increased heat flow at surface which, in favourable circumstatnces, should be associated with significant uranium occurrences. Measurement of heat flow could either be by surface thermal sensors or by thermal infra-red scanning techniques from aircraft. For the purposes of preliminary surveys of large areas, airborne geochemical techniques offer considerable scope. Possibilities include the measurement of 222 Rn in the atmosphere. Alternatively, one or more of the decay products of radon could be measured. These are 210 Pb, 210 Bi and 210 Po. It is concluded that there is ample evidence to suggest that the more widespread application of known exploration methods, together with new techniques that can already be envisaged, will result in important new discoveries of uranium reserves

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)

California-Nevada uranium logging. Final report

International Nuclear Information System (INIS)

1981-04-01

The purpose of this project was to obtain geophysical logs of industry drill holes to assess the uranium resource potential of geologic formations of interest. The work was part of the US Department of Energy's National Uranium Resource Evaluation (NURE) Program. The principal objective of the logging program was to determine radioelement grade of formations through natural gamma ray detectors. Supplementary information was obtained from resistivity (R), self-potential (SP), point resistance (RE), and neutron density (NN) logs for formation interpretation. Additional data for log interpretation was obtained from caliper logs, casing schedules, and downhole temperature. This data was obtained from well operators when available, with new logs obtained where not formerly available. This report contains a summary of the project and data obtained to date

An evaluation of the uranium mine radiation safety course

International Nuclear Information System (INIS)

1984-07-01

The report evaluates the Uranium Mine Radiation Safety Course focussing on the following areas: effectivenss of the course; course content; instructional quality; course administration. It notes strengths and weaknesses in these areas and offers preliminary recommendations for future action

Realization of economic evaluation expert system for uranium mine project

International Nuclear Information System (INIS)

Wang Haifeng

1993-01-01

By studying the EVALUATOR, economic evaluation expert system of uranium mine project, the theoretical fundamentals of expert system, principle of inference mechanism, implementation of knowledge base, realization of explanation mechanism, acquisition of domain knowledge and representation of knowledge were described, especially the subjective Bayes approach for inexact reasoning problem used in EVALUATOR was discussed in detail

The uncertainty evaluation of measurement for uranium in UF_6 hydrolysate by potentiometric titration

International Nuclear Information System (INIS)

Jiang Haiying; Cheng Ruoyu; Meng Xiujun

2014-01-01

Based on the building of mathematical model, this paper analyzed the origin of component of indeterminacy of which the measurement result for uranium in uranium hexafluoride hydrolysate by potentiometric titration, also each uncertainty was calculated and the expanded uncertainty was given. By evaluation the result of the uranium concentration is that: (158.88 + 1.22) mgU/mL, K = 2, P = 95%. (authors)

Evaluation of kinetic phosphorescence analysis for the determination of uranium

International Nuclear Information System (INIS)

Croatto, P.V.; Frank, I.W.; Johnson, K.D.; Mason, P.B.; Smith, M.M.

1997-12-01

In the past, New Brunswick Laboratory (NBL) has used a fluorometric method for the determination of sub-microgram quantities of uranium. In its continuing effort to upgrade and improve measurement technology, NBL has evaluated the commercially-available KPA-11 kinetic phosphorescence analyzer (Chemchek, Richland, WA). The Chemchek KPA-11 is a bench-top instrument which performs single-measurement, quench-corrected analyses for trace uranium. It incorporates patented kinetic phosphorimetry techniques to measure and analyze sample phosphorescence as a function of time. With laser excitation and time-corrected photon counting, the KPA-11 has a lower detection limit than conventional fluorometric methods. Operated with a personal computer, the state-of-the-art KPA-11 offers extensive time resolution and phosphorescence lifetime capabilities for additional specificity. Interferences are thereby avoided while obtaining precise measurements. Routine analyses can be easily and effectively accomplished, with the accuracy and precision equivalent to the pulsed-laser fluorometric method presently performed at NBL, without the need for internal standards. Applications of kinetic phosphorimetry at NBL include the measurement of trace level uranium in retention tank, waste samples, and low-level samples. It has also been used to support other experimental activities at NBL by the measuring of nanogram amounts of uranium contamination (in blanks) in isotopic sample preparations, and the determining of elution curves of different ion exchange resins used for uranium purification. In many cases, no pretreatment of samples was necessary except to fume them with nitric acid, and then to redissolve and dilute them to an appropriate concentration with 1 M HNO 3 before measurement. Concentrations were determined on a mass basis (microg U/g of solution), but no density corrections were needed since all the samples (including the samples used for calibration) were in the same density

International Uranium Resources Evaluation Project (IUREP) orientation phase mission report: Republic of Burundi. Draft

International Nuclear Information System (INIS)

Gehrisch, W.; Chaigne, M.

1983-06-01

The basic objective of the International Uranium Resources Evaluation project lUREP is to 'Review the present body of knowledge pertinent to the existence of uranium resources, to review and evaluate the potential for the discovery of additional uranium resources and to suggest new exploration efforts which might be carried out in promising areas in collaboration with the countries concerned'. Therefore, the scope of the IUREP orientation phase Mission to Burundi was to review all data on past exploration in Burundi, to develop a better understanding of the uranium potential of the country, to make an estimate of the speculative resources of the country, to make recommendation as appropriate on the best methods or techniques for evaluating the resources in the favourable areas and for estimating possible costs as well, to compile a report which could be immediately available to the Burundian authorities. This mission gives a general introduction, a geological review of Burundi, information on non-uranium mining in Burundi, the history of uranium exploration, occurrences of uranium IUREP mission field reconnaissance, favourable areas for speculative potential, the uranium resources position and recommendations for future exploration. Conclusions are the following. The IUREP Orientation -phase mission to Burundi believes that the Speculative Resources of that country fall b etween 300 and 4100 tons uranium oxide but a less speculative appraisal is more likely between 0 and 1000 tons. There has been no uranium production and no official estimates of Uranium Resources in Burundi. Past exploration mainly dating from 1969 onwards and led the UNDP Mineral project has indicated a limited number of uranium occurrences and anomalies. The speculative uranium resources are thought to be possibly associated with potential unconformity related vein-like deposits of the Lower Burundian. Other speculative uranium resources could be associated with granitic or peribatholitic

Study of a bacterial leaching program for uranium ores by Thiobacillus ferroxidans

International Nuclear Information System (INIS)

Garcia Junior, O.

1989-01-01

The development of a bacterial leaching program for uranium ores is studied. Three basic points are presented: isolation and purification of Thiobacillus ferroxidans, as well Thiobacillus thio oxidans; physiological studies of growth and respiratory metabolism of T. ferroxidans; uranium leaching from two types of ore by T. ferroxidans action, on laboratory, semi pilot and pilot scales. The bacterial leaching studies were carried out in shake flasks, percolation columns (laboratory and semi pilot) and in heap leaching (pilot). The potential of the ores studied in relation to bacterial action, was first showed in shake flask experiments. The production of H 2 S O 4 and Fe 3+ was a result of the bacterial activity on both ore samples containing pyrite (Fe S 2 ). These two bacterial products resulted in a high uranium and molybdenum extraction and a lower sulfuric acid consumption compared to the sterilized treatments. Similar results were obtained in percolation column at the same scale (lab). (author)

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Uganda

International Nuclear Information System (INIS)

1985-01-01

A full report has been compiled describing the findings of the International Uranium Resources Evaluation Project (IUREP) Orientation Phase Mission to Uganda. The Mission suggest that the speculative uranium resources of the country could be within the very wide range of 0 to 105 000 tonnes of uranium metal. The Mission finds that most of these speculative resources are related to Proterozoic unconformities and to Cenozoic sandstones of the Western Rift Valley. Some potential is also associated with Post-tectonic granites. The Mission recommends to rehabilitate the Geological Survey of Uganda in order to enable it to conduct and support a uranium exploration programme for unconformity related and for standstone hosted uranium deposits. Recommended exploration methods encompass geological mapping and compilation, an airborne gamma-ray spectrometer survey north of 1 deg. North latitude, stream sediment sampling, and ground scintillometric surveys in favourable areas. Follow up work should include VLF-EM surveys, emanometry and drilling. (author)

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Somalia

International Nuclear Information System (INIS)

1985-01-01

A full report has been compiled describing the findings of the International Uranium Resources Evaluation Project (IUREP) Orientation Phase Mission to Somalia. The Mission suggests that in addition to the reasonably assured resources (RAR) of 5 000 t uranium and estimated additional resources (EAR) of 11 000 t uranium in calcrete deposits, the speculative resources (SR) could be within the wide range of 0 - 150 000 t uranium. The majority of these speculative resources are related to sandstone and calcrete deposits. The potential for magmatic hydrothermal deposits is relatively small. The Mission recommends an exploration programme of about US$ 22 000 000 to test the uranium potential of the country which is thought to be excellent. The Mission also suggests a reorganization of the Somalia Geological Survey in order to improve its efficiency. Recommended methods include geological mapping, Landsat imagery interpretation, airborne and ground scintillometer surveys, and geochemistry. Follow-up radiometric surveys, exploration geophysics, mineralogical studies, trenching and drilling are proposed in favourable areas. (author)

Aeromagnetic data processing and application in the evaluation of uranium resource potential in China

International Nuclear Information System (INIS)

Wang Yuanzhi; Zhang Junwei; Feng Chunyuan

2012-01-01

The article introduces the main methods to deduce geological structures with aeromagnetic data, and summarizes the prediction elements of aeromagnetic characteristics for granite, volcanic, carbonaceous-siliceous-argillaceous rock and sandstone type uranium deposits. By analysing the relationship of aeromagnetic deduced geological structures and uranium mineralization, the prediction model of combined factors was summarized for each type uranium deposit. A case study in Taoshan-Zhuguang mineralization belt shows that the fault, plutons and volcanic structures deduced from areomagnetic information can judge the favorable mineralization environment and ore control structure. Therefore, the process and application of aeromagnetic data can play an important role in the evaluation of uranium resource potential and uranium exploration. (authors)

Recent developments and evaluation of selected geochemical techniques applied to uranium exploration

International Nuclear Information System (INIS)

Wenrich-Verbeek, K.J.; Cadigan, R.A.; Felmlee, J.K.; Reimer, G.M.; Spirakis, C.S.

1976-01-01

Various geochemical techniques for uranium exploration are currently under study by the geochemical techniques team of the Branch of Uranium and Thorium Resources, US Geological Survey. Radium-226 and its parent uranium-238 occur in mineral spring water largely independently of the geochemistry of the solutions and thus are potential indicators of uranium in source rocks. Many radioactive springs, hot or cold, are believed to be related to hydrothermal systems which contain uranium at depth. Radium, when present in the water, is co-precipitated in iron and/or manganese oxides and hydroxides or in barium sulphate associated with calcium carbonate spring deposits. Studies of surface water samples have resulted in improved standardized sample treatment and collection procedures. Stream discharge has been shown to have a significant effect on uranium concentration, while conductivity shows promise as a ''pathfinder'' for uranium. Turbid samples behave differently and consequently must be treated with more caution than samples from clear streams. Both water and stream sediments should be sampled concurrently, as anomalous uranium concentrations may occur in only one of these media and would be overlooked if only one, the wrong one, were analysed. The fission-track technique has been applied to uranium determinations in the above water studies. The advantages of the designed sample collecting system are that only a small quantity, typically one drop, of water is required and sample manipulation is minimized, thereby reducing contamination risks. The fission-track analytical technique is effective at the uranium concentration levels commonly found in natural waters (5.0-0.01 μg/litre). Landsat data were used to detect alteration associated with uranium deposits. Altered areas were detected but were not uniquely defined. Nevertheless, computer processing of Landsat data did suggest a smaller size target for further evaluation and thus is useful as an exploration tool

International Uranium Resources Evaluation Project (IUREP) orientation phase mission report: Venezuela. Draft

International Nuclear Information System (INIS)

Hetland, Donald L.; Obellianne, Jean-marie

1981-04-01

required later to substantiate or invalidate the estimated Speculative Resources and to acquire sufficient evidence on which to base an estimate of the Reasonable Assured Resources or Estimated Additional Resources in Venezuela. However the Mission is unwilling to make an estimate of the required additional drilling or the cost until such time as the surface reconnaissance work proposed above is complete, particularly in the Guaysna Shield area, and the favorable areas are better defined. The comparison between the Mission's proposal (detailed in text) and the present recommendations of the national organization, CONADIN, shows that, in effect, the Mission endorses the proposed national surface survey program both in scope and objective, but suggests some modification in regards to techniques and methods employed. The Mission also suggests that the proposed drilling be increased by nearly four times. The Mission therefore believes that there is a difference of approximately 1.3 million U.S. dollars between the recommended five year plan and the Mission's estimate of what is required to conduct an adequate five year exploration program to evaluate Venezuela's Speculative Resources

Highly enriched uranium (HEU) storage and disposition program plan

International Nuclear Information System (INIS)

Arms, W.M.; Everitt, D.A.; O'Dell, C.L.

1995-01-01

Recent changes in international relations and other changes in national priorities have profoundly affected the management of weapons-usable fissile materials within the United States (US). The nuclear weapon stockpile reductions agreed to by the US and Russia have reduced the national security requirements for these fissile materials. National policies outlined by the US President seek to prevent the accumulation of nuclear weapon stockpiles of plutonium (Pu) and HEU, and to ensure that these materials are subjected to the highest standards of safety, security and international accountability. The purpose of the Highly Enriched Uranium (HEU) Storage and Disposition Program Plan is to define and establish a planned approach for storage of all HEU and disposition of surplus HEU in support of the US Department of Energy (DOE) Fissile Material Disposition Program. Elements Of this Plan, which are specific to HEU storage and disposition, include program requirements, roles and responsibilities, program activities (action plans), milestone schedules, and deliverables

National Uranium Resource Evaluation: Greensboro Quadrangle, North Carolina and Virginia

International Nuclear Information System (INIS)

Dribus, J.R.; Hurley, B.W.; Lawton, D.E.; Lee, C.H.

1982-07-01

The Greensboro Quadrangle, North Carolina and Virginia, was evaluated to identify and delineate areas favorable for the occurrence of uranium deposits. General surface reconnaissance and geochemical sampling were carried out in all geologic environments within the quadrangle. Aerial radiometric and hydrogeochemical and stream-sediment reconnaissance data were analyzed, and ground-truth followup studies of anomalies were conducted. Detailed surface investigations, log and core studies, and a radon emanometry survey were conducted in selected environments. The results of this investigation suggest environments favorable for allogenic uranium deposits in metamorphic rocks adjacent to the intrusive margins of the Rolesville, Castalia, Redoak, and Shelton granite plutons, and sandstone-type deposits in the sediments of the Durham and Dan River Triassic basin systems. Environments in the quadrangle considered unfavorable for uranium deposits are pegmatites and metamorphic rocks and their included veins associated with fault and shear zones

HIGHLY ENRICHED URANIUM BLEND DOWN PROGRAM AT THE SAVANNAH RIVER SITE PRESENT AND FUTURE

International Nuclear Information System (INIS)

Magoulas, V; Charles Goergen, C; Ronald Oprea, R

2008-01-01

The Department of Energy (DOE) and Tennessee Valley Authority (TVA) entered into an Interagency Agreement to transfer approximately 40 metric tons of highly enriched uranium (HEU) to TVA for conversion to fuel for the Browns Ferry Nuclear Power Plant. Savannah River Site (SRS) inventories included a significant amount of this material, which resulted from processing spent fuel and surplus materials. The HEU is blended with natural uranium (NU) to low enriched uranium (LEU) with a 4.95% 235U isotopic content and shipped as solution to the TVA vendor. The HEU Blend Down Project provided the upgrades needed to achieve the product throughput and purity required and provided loading facilities. The first blending to low enriched uranium (LEU) took place in March 2003 with the initial shipment to the TVA vendor in July 2003. The SRS Shipments have continued on a regular schedule without any major issues for the past 5 years and are due to complete in September 2008. The HEU Blend program is now looking to continue its success by dispositioning an additional approximately 21 MTU of HEU material as part of the SRS Enriched Uranium Disposition Project

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

Multi-coupling dynamic model and 3d simulation program for in-situ leaching of uranium mining

International Nuclear Information System (INIS)

Tan Kaixuan; Zeng Sheng; Sang Xiao; Sun Bing

2010-01-01

The in-situ leaching of uranium mining is a very complicated non-linear dynamic system, which involves couplings and positive/negative feedback among many factors and processes. A comprehensive, coupled multi-factors and processes dynamic model and simulation method was established to study the in-situ leaching of uranium mining. The model accounts for most coupling among various processes as following: (1) rock texture mechanics and its evolution, (2)the incremental stress rheology of rock deformation, (3) 3-D viscoelastic/ plastic multi-deformation processes, (4) hydrofracturing, (5) tensorial (anisotropic) fracture and rock permeability, (6) water-rock interactions and mass-transport (both advective and diffusive), (7) dissolution-induced chemical compaction, (8) multi-phase fluid flow. A 3-D simulation program was compiled based on Fortran and C++. An example illustrating the application of this model to simulating acidification, production and terminal stage of in situ leaching of uranium mining is presented for the some mine in Xinjiang, China. This model and program can be used for theoretical study, mine design, production management, the study of contaminant transport and restoration in groundwater of in-situ leaching of uranium mining. (authors)

Guide to the bioassay of uranium at uranium mine-mill facilities

International Nuclear Information System (INIS)

1981-01-01

As a result of occupational exposure, uranium may be taken into the body by inhalation, ingestion or absorption through skin wounds. The organs at risk are the lung, kidney, and bones. Analysis of urine samples for uranium is recommended on a regular monthly basis, before and after a rest period, and it is suggested that a worker be removed from a working area if a level above 300 μg/l is found before a rest period, or 150 μg/l after a rest period. Background information on the development of a bioassay program is given, and a recommended program for uranium mine and mill facilities is included. (L.L.)

Pulmonary function evaluations of dogs exposed to uranium ore dust

International Nuclear Information System (INIS)

Loscutoff, S.M.; Buschbom, R.L.; Palmer, R.F.; Cross, F.T.

1980-01-01

Pulmonary function evaluations were conducted on dogs exposed to carnotite uranium ore dust. Significant changes were detected in the slope of the single-breath N 2 washout curve, suggesting an uneven distribution of ventilation

Method to evaluate covariance data for the thorium-uranium fuel cycle

International Nuclear Information System (INIS)

Kawano, T.; Chadwick, M.B.

2003-01-01

This power point presentation gives an overview about the evaluation strategy for the experimental data for the thorium-uranium fuel cycle. Uncertainties, error propagation and calculation methods are outlined. Covariance evaluation tools and computer codes have been developed and results are presented

Neutron study of fast neutron reactor systems by exponential experiments on Harmonie - Graphite program HUG-PHUG - Oxide program PHRIXOS - Uranium program UK

International Nuclear Information System (INIS)

Desprets, Alain.

1977-12-01

Exponential experiments allow to obtain the fundamental characteristics of a lattice (material buckling, reaction rate ratios) more economically than critical experiments. This report describes the experimental techniques and the methods of analysis used for this type of experiments. The results obtained with three programs performed with the source reactor HARMONIE are given: graphite-lattices program (3 U-fueled and 3 Pu-fueled lattices); oxide-fuel program (4 PuO 2 -UO 2 lattices); pure uranium program (one lattice). Some of these lattices were also studied in critical experiments. The coherence of the results obtained by the two types of experiments is established [fr

Evaluation of plutonium, uranium, and thorium use in power reactor fuel cycles

International Nuclear Information System (INIS)

Kasten, P.R.; Homan, F.J.

1977-01-01

The increased cost of uranium and separative work has increased the attractiveness of plutonium use in both uranium and thorium fuel cycles in thermal reactors. A technology, fuel utilization, and economic evaluation is given for uranium and thorium fuel cycles in various reactor types, along with the use of plutonium and 238 U. Reactors considered are LWRs, HWRs, LWBRs, HTGRs, and FBRs. Key technology factors are fuel irradiation performance and associated physical property values. Key economic factors are unit costs for fuel fabrication and reprocessing, and for refabrication of recycle fuels; consistent cost estimates are utilized. In thermal reactors, the irradiation performance of ceramic fuels appears to be satisfactory. At present costs for uranium ore and separative work, recycle of plutonium with thorium rather than uranium is preferable from fuel utilization and economic viewpoints. Further, the unit recovery cost of plutonium is lower from LWR fuels than from natural-uranium HWR fuels; use of LWR product permits plutonium/thorium fueling to compete with uranium cycles. Converting uranium cycles to thorium cycles increases the energy which can be extracted from a given uranium resource. Thus, additional fuel utilization improvement can be obtained by fueling all thermal reactors with thorium, but this requires use of highly enriched uranium; use of 235 U with thorium is most economic in HTGRs followed by HWRs and then LWRs. Marked improvement in long-term fuel utilization can be obtained through high thorium loadings and short fuel cycle irradiations as in the LWBR, but this imposes significant economic penalties. Similar operating modes are possible in HWRs and HTGRs. In fast reactors, use of the plutonium-uranium cycle gives advantageous fuel resource utilization in both LMFBRs and GCFRs; use of the thorium cycle provides more negative core reactivity coefficients and more flexibility relative to use of recycle fuels containing uranium of less than 20

Geological and geochemical aspects of uranium deposits. A selected, annotated bibliography

Energy Technology Data Exchange (ETDEWEB)

Garland, P.A.; Thomas, J.M.; Brock, M.L.; Daniel, E.W. (comps.)

1980-06-01

A bibliography of 479 references encompassing the fields of uranium and thorium geochemistry and mineralogy, geology of uranium deposits, uranium mining, and uranium exploration techniques has been compiled by the Ecological Sciences Information Center of Oak Ridge National Laboratory. The bibliography was produced for the National Uranium Resource Evaluation Program, which is funded by the Grand Junction Office of the Department of Energy. The references contained in the bibliography have been divided into the following eight subject categories: (1) geology of deposits, (2) geochemistry, (3) genesis O deposits, (4) exploration, (5) mineralogy, (6) uranium industry, (7) reserves and resources, and (8) geology of potential uranium-bearing areas. All categories specifically refer to uranium and thorium; the last category contains basic geologic information concerning areas which the Grand Junction Office feels are particularly favorable for uranium deposition. The references are indexed by author, geographic location, quadrangle name, geoformational feature, taxonomic name, and keyword.

Geological and geochemical aspects of uranium deposits. A selected, annotated bibliography

International Nuclear Information System (INIS)

Garland, P.A.; Thomas, J.M.; Brock, M.L.; Daniel, E.W.

1980-06-01

A bibliography of 479 references encompassing the fields of uranium and thorium geochemistry and mineralogy, geology of uranium deposits, uranium mining, and uranium exploration techniques has been compiled by the Ecological Sciences Information Center of Oak Ridge National Laboratory. The bibliography was produced for the National Uranium Resource Evaluation Program, which is funded by the Grand Junction Office of the Department of Energy. The references contained in the bibliography have been divided into the following eight subject categories: (1) geology of deposits, (2) geochemistry, (3) genesis O deposits, (4) exploration, (5) mineralogy, (6) uranium industry, (7) reserves and resources, and (8) geology of potential uranium-bearing areas. All categories specifically refer to uranium and thorium; the last category contains basic geologic information concerning areas which the Grand Junction Office feels are particularly favorable for uranium deposition. The references are indexed by author, geographic location, quadrangle name, geoformational feature, taxonomic name, and keyword

Evaluation and control of radon daughter hazards in uranium mines

International Nuclear Information System (INIS)

Holaday, D.A.

1974-11-01

This monograph discusses primarily those health hazards to uranium miners which are produced by exposure to ionizing radiation. Emphasis is placed on the areas of evaluation of exposures to the radioactive gas radon-222 and its short-lived transformation products, and methods of controlling such exposures. A limited discussion of the biological effects of radon and radon daughters is undertaken, and some procedures are given for evaluating hazards created by other common contaminants of mine atmospheres. A large amount of information exists on these topics, some of which is unpublished or is not readily available. While efforts were made to obtain data from all sources, undoubtedly some valuable work was overlooked. The monograph is an endeavor to assemble pertinent information and make it available to those who are concerned with producing uranium at minimal risks. Where they were available, a variety of procedures for evaluating hazards are given, and examples of systems for controlling hazards are included. 154 references

Based on matlab 3d visualization programming in the application of the uranium exploration

International Nuclear Information System (INIS)

Qi Jianquan

2012-01-01

Combined geological theory, geophysical curve and Matlab programming three dimensional visualization applied to the production of uranium exploration. With a simple Matlab programming, numerical processing and graphical visualization of convenient features, and effective in identifying ore bodies, recourse to ore, ore body delineation of the scope of analysis has played the role of sedimentary environment. (author)

Training manual for uranium mill workers on health protection from uranium

International Nuclear Information System (INIS)

McElroy, N.; Brodsky, A.

1986-01-01

This report provides information for uranium mill workers to help them understand the radiation safety aspects of working with uranium as it is processed from ore to yellowcake at the mills. The report is designed to supplement the radiation safety training provided by uranium mills to their workers. It is written in an easily readable style so that new employees with no previous experience working with uranium or radiation can obtain a basic understanding of the nature of radiation and the particular safety requirements of working with uranium. The report should be helpful to mill operators by providing training material to support their radiation safety training programs

Some results of NURE uranium geochemical studies

International Nuclear Information System (INIS)

Price, V. Jr.

1979-01-01

Some technical developments of the National Uranium Resource Evaluation Program which are of general application in geochemical exploration are being studied. Results of stream water and suspended and bottom sediment analyses are compared for an area near Williamsport, Pennsylvania. Variations of uranium content of water samples with time in the North Carolina Piedmont are seen to correlate with rainfall. Ground water samples from coastal and piedmont areas were analyzed for helium. All media sampled provide useful information when properly analyzed and interpreted as part of a total geological analysis of an area

National uranium resource evaluation. Raton Quadrangle New Mexico and Colorado. Final report

International Nuclear Information System (INIS)

Reid, B.E.; Griswold, G.B.; Jacobsen, L.C.; Lessard, R.H.

1980-12-01

Using National Uranium Resource Evaluation criteria, the Raton Quadrangle (New Mexico and Colorado) contains one environment favorable for uranium deposits, the permeable arkosic sandstone members of the Pennsylvanian-Permian Sangre de Cristo Formation for either peneconcordant or roll-type deposits. The favorable parts of the Sangre de Cristo lie mostly in the subsurface in the Raton and Las Vegas Basins in the eastern part of the quadrangle. An area in the Costilla Peak Massif was investigated for uranium by determining geochemical anomalies in stream sediments and spring waters. Further work will be required to determine plutonic environment type. Environments unfavorable for uranium deposits include the Ogallala, Raton, and Vermejo Formations, the Trinidad Sandstone, the Pierre Shale, the Colorado Group, the Dakota Sandstone, the Morrison Formation, the Entrada and Glorieta Sandstones, Mississippian and Pennsylvanian rocks, quartz-pebble conglomerates, pegmatities, and Tertiary granitic stocks

Department of Energy depleted uranium recycle

International Nuclear Information System (INIS)

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

1994-01-01

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

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.

Evaluating the effectiveness of dilution of the recovered uranium with depleted uranium and low-enriched uranium to obtain fuel for VVER reactors

International Nuclear Information System (INIS)

Smirnov, A Yu; Sulaberidze, G A; Dudnikov, A A; Nevinitsa, V A

2016-01-01

The possibility of the recovered uranium enrichment in a cascade of gas centrifuges with three feed flows (depleted uranium, low-enriched uranium, recovered uranium) with simultaneous dilution of U-232,234,236 isotopes was shown. A series of numerical experiments were performed for different content of U-235 in low-enriched uranium. It has been demonstrated that the selected combination of diluents can simultaneously reduce the cost of separative work and the consumption of natural uranium, not only with respect to the previously used multi-flow cascade schemes, but also in comparison to the standard cascade for uranium enrichment. (paper)

Gravity data processing and research in potential evaluation of uranium resource in China

International Nuclear Information System (INIS)

Liu Hu; Zhao Dan; Ke Dan; Li Bihong; Han Shaoyang

2012-01-01

Through data processing, anomaly extraction, geologic structure deduction from gravity in 39 uranium metallogenic zones and 29 prediction areas, the predicting factors such as tectonic units, faults, scope and depth of rocks, scope of basins and strata structure were provided for the evaluation of uranium resources potential. Gravity field features of uranium metallogenic environment were summarized for hydrothermal type uranium deposits (granite, volcanic and carbonate-siliceous-argillaceous type) as regional gravity transition from high to the low field or the region near the low field, and the key metallogenic factors as granite rocks and volcanic basins in the low gravity field. It was found that Large-scale sandstone type uranium mineralization basins are located in the high regional gravity field, provenance areas are in the low field, and the edge and inner uplift areas usually located in the high field of the residual gravity. Faults related to different type uranium mineralization occur as the gradient zones, boundaries, a string of bead anomalies and striped gravity anomalies in the gravity field. (authors)

Hydrogeochemical and stream sediment reconnaissance of the National Uranium Resource Evaluation Program. Progress report, July--September 1976

International Nuclear Information System (INIS)

Morris, W.A.

1977-01-01

Water and/or sediment samples have been collected from some 47,000 sample locations covering about 504,000 km 2 which represents 19% of the area assigned to the LASL for the HSSR program. Slightly over half of this sampling work was done this quarter and included the first commercial, helicopter-borne sampling contract in Alaska where 4468 locations were sampled over an area of 94,000 km 2 . Thus far, uranium determinations have been made for some 12,000 water samples by fluorometry and for over 15,000 sediment samples by delayed-neutron counting. The main effort of this quarter has been directed toward completing all outstanding commercial sampling contracts and analyzing the backlog of water and sediment samples

A new approach for geochemical surveys of large areas for uranium resource potential

International Nuclear Information System (INIS)

Arendt, J.W.; Butz, T.R.; Cagle, G.W.; Kane, V.E.; Nichols, C.E.

1977-01-01

The Grand Junction, Colorado office of the United States Energy Research and Development Administration (ERDA) is conducting the National Uranium Resource Evaluation Program to evaluate the uranium resources in the United States and Alaska. The program is designed to identify favorable areas for uranium exploration, to assess the supply of domestic resources, and to improve exploration technology. The Nuclear Division of the Union Carbide Corporation has been assigned the responsibility of conducting a hydrogeochemical and stream sediment survey of the mid-continental states in the United States. This survey covers approximately 2,500,000 km 2 (1,000,000 mi 2 ) and includes the states of Texas, Oklahoma, Kansas, Nebraska, South Dakota, North Dakota, Minnesota, Wisconsin, Michigan, Indiana, Illinois, and Iowa. The uranium potential of sandstones, Precambrian conglomerates, veins, granites, and phosphorites is being assessed utliizing a three-part program consisting of pilot surveys in each geological province and two phases of reconnaissance sampling of drainage basins. Samples of stream sediment, stream water, groundwater, algae, and vegetation are analyzed for uranium and some 20 additional elements. Data resulting from this program is released to private industry by ERDA as it becomes available. Analysis of results from a typical three-part survey are given. For distinctive geological regions, the pilot survey will: (1) define characteristic concentration background levels of the elements of interest, (2) identify potential uranium pathfinder elements, (3) determine relationship between stream, stream sediment and botanical samples, (4) identify any necessary modification to field sampling techniques, and (5) determine necessary sensitivities required for chemical analysis. The first reconnaissance phase average sample spacing of one station per 250 km 2 (100 mi 2 ) drainage basin is shown to delineate general boundaries of uranium provinces, and the second

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Bolivia

International Nuclear Information System (INIS)

1985-01-01

A report has recently been published which describes the findings of the International Uranium Resources Evaluation Project (IUREP) mission to Bolivia. The IUREP Orientation Phase mission to Bolivia estimates that the Speculative Uranium Resources of that country fall within the range of 100 to 107 500 tonnes uranium. The majority of this potential is expected to be located in the Precambrian crystalline and sedimentary rocks of the southwestern part of the Central Brazilian Shield. Other potentially favourable geologic environments include Palaeozoic two mica granites and their metasedimentary hosts, Mesozoic granites and granodiorites as well as the intruded formations and finally Tertiary acid to intermediate volcanics. The mission recommends that approximately US$ 13 million be spent on exploration in Bolivia over a five-year period. The majority of this expenditure would be for airborne and surface exploration utilising geologic, magnetometric, radiometric, and geochemical methods and some pitting, trenching, tunneling and drilling to further evaluate the discovered occurrences. (author)

Method of impact evaluation of storage sites for uranium ore tailings

International Nuclear Information System (INIS)

Servant, A.C.; Cessac, B.

2001-11-01

Mining and ore processing generate liquid effluents and solid waste ( tailings) in important quantities. On fifty years exploitation, 50 millions tons of tailings have been stored on twenty sites in France. From a radiological point of view, the uranium tailings contain only natural radioisotopes, daughters of 238 U and 235 U families and for a low part daughter's of 232 Th family. Their activity stay low to very low, under the ore activity. It decreases very slowly because of the long period of some radionuclides ( 230 Th, 75 000 years, 226 Ra, 1600 years). generally stored on the exploitation site, these tailings constitute a radiological source term of which it is necessary to evaluate the impact on man and environment. At close-down of an uranium ore exploitation site, the operator is required to give to the prefect of his region a file of rehabilitation with the dispositions to take to limit the radiological impact of the storage. It is in this frame that the direction of pollutions and risks prevention (D.P.P.R.) from the Minister of Territory landscaping and the Institute of protection and nuclear safety (I.R.S.N.) established a convention, reference 56/2000, relative to investigations in matter of radiological impact evaluation of uranium tailings storage sites, in order to supply a document allowing to judge the pertinence of the different files made by Cogema in the frame of tailings storage of uranium ore processing. The present document constitutes the report planned at the 3. article ( 3. paragraph) of the convention. It gives the information necessary to the evaluation of impact studies for the sites in question. (N.C.)

National Uranium Resource Evaluation: Crystal City Quadrangle, Texas

International Nuclear Information System (INIS)

Greimel, T.C.

1982-08-01

The uranium resources of the Crystal City Quadrangle, Texas, were evaluated to a depth of 1500 m using surface and subsurface geologic information. Uranium occurrences reported in the literature, in reports of the US Atomic Energy Commission and the US Geological Survey Computerized Resources Information Bank, were located, described, and sampled. Geochemical anomalies interpreted from hydrogeochemical and stream-sediment reconnaissance were also investigated and sampled in detail. Areas of uranium favorability in the subsurface were located through interpretation of lithofacies patterns and structure derived from electric-log data. Gamma-ray well logs and results of geochemical sample analyses were used as supportive data in locating these areas. Fifteen surface and subsurface favorable areas were delineated in the quadrangle. Eight are in fluvial and genetically associated facies of the Pliocene Goliad Sandstone, Miocene Oakville Sandstone, Miocene Catahoula Tuff, and Oligocene Frio Clay. One area encompasses strand plain-barrier bar, fluvial-deltaic, and lagoonal-margin facies of the Eocene Jackson Group. Two areas are in strand plain-barrier bar and probable fluvial facies of the Eocene Yegua Formation. Four areas are in fluvial-deltaic, barrier-bar, and lagoonal-margin facies of the Eocene Queen City Formation and stratigraphically equivalent units. Seventeen geologic units are considered unfavorable, and seven are unevaluated due to lack of data

Bioassay for uranium mill tailings

International Nuclear Information System (INIS)

Tschaeche, A.N.

1986-01-01

Uranium mill tailings are composed of fine sand that contains, among other things, some uranium (U/sup 238/ primarily), and all of the uranium daughters starting with /sup 230/Th that are left behind after the usable uranium is removed in the milling process. Millions of pounds of tailings are and continue to be generated at uranium mills around the United States. Discrete uranium mill tailings piles exist near the mills. In addition, the tailings materials were used in communities situated near mill sites for such purposes as building materials, foundations for buildings, pipe runs, sand boxes, gardens, etc. The Uranium Mill Tailings Remedial Action Project (UMTRAP) is a U.S. Department of Energy Program designed with the intention of removing or stabilizing the mill tailings piles and the tailings used to communities so that individuals are not exposed above the EPA limits established for such tailings materials. This paper discusses the bioassay programs that are established for workers who remove tailings from the communities in which they are placed

Nuclear material control and accounting system evaluation in uranium conversion operations

International Nuclear Information System (INIS)

Moreira, Jose Pontes

1994-01-01

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

Study on integrated evaluation of sandstone-hosted uranium metallogenic potential in southern Yili basin

International Nuclear Information System (INIS)

Han Shaoyang; Ke Dan; Xu Jianguo; Zheng Enjiu; Li Shengxiang

2008-01-01

Plenty of geological data have been accumulated during mineral resource survey in China; under the guidance of new metallogenic theories, it is an important task of how to use these data most effectively for the new cycle uranium survey. In this paper, the flow of establishing the integrated mineral deposits prospecting model for sandstone-hosted uranium deposits is put forward. Based on studying geologic, hydrogeologic and regional geophysical field characteristics of representative uranium deposits No. 512 in southern Yili basin, its multi-source information descriptive model has been established, from which 512-type integrated prospecting models of sandstone-hosted uranium orefield and deposits are summarized. According to the established integrated prospecting models, the metallogenic information extraction of sandstone-hosted uranium deposits has completed in the study area. Finally, the integrated quantitative evaluation of sandstone-hosted uranium metallogenic potential is performed by using the evidence weighing method to integrate middle scale multi-source metallogenic information in the southern Yili basin, and good prediction effect is obtained. (authors)

Applications of inductively coupled plasma spectroscopy to geochemical reconnaissance for uranium exploration

International Nuclear Information System (INIS)

Cagle, G.W.; Butz, T.R.

1980-01-01

The analysis of large numbers of natural groundwater and stream sediment samples by Inductively Coupled Plasma (ICP) Spectroscopy has been applied to a geochemical reconnaissance program as part of the National Uranium Resource Evaluation Program. Approximately 25 elements have been determined in over 60,000 samples by ICP analysis. These data are combined with additional measurements obtained by atomic absorption, colorimetry, neutron activation, and fluorescence spectroscopy. Results are presented and interpreted in terms of the uranium favorability of areas in Texas where this survey has been completed

Uranium accountability for ATR fuel fabrication. Part I. A description of the existing system

International Nuclear Information System (INIS)

Dolan, C.A.; Nieschmidt, E.B.; Vegors, S.H. Jr.; Wagner, E.P. Jr.

1977-06-01

An evaluation of the materials accountability program at the Atomics International fuel fabrication facility in Canoga Park, California, with regard to the fabrication of highly enriched uranium fuel for the Advanced Test Reactor is presented. An analysis is given of the existing standards program, the existing measurements program and the existing statistical analysis procedures. In addition a short discussion is given of our evaluation of the safeguards procedures at Atomics International together with suggestions for possible modifications and improvements. Appendices of this report contain a rather complete description of the Atomics International plant and the flow of highly enriched uranium through the plant as well as the principal documents used for material accountability records

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

International Nuclear Information System (INIS)

1978-01-01

With the exception of the exploration activities in relation with the Beach Sand Project along the eastern Bay of Bengal, no systematic exploration for uranium had been done before December 1976, when a radiometric survey was implemented by the IAEA. As a result of this survey high radioactivity up to 450 cps was detected in placer Tipam deposits, The background of the terrain made up by Tertiary sediments is 160 - 170 cps. An anomaly was found in Kalipur Chara area which coincides with concentration of heavy minerals derived from Tipam Sandstones. Another anomaly was found within a horizon of Tipam sandstone crossing Hari River. An isolated outcrop in the riverbed showed a count rate up to 4 times background. During the follow up work it was found that this steeply dipping mineralized band stretches (with interruptions) over a distance of at least 3km along a strike. Samples collected from three different spils showed concentration of uranium 50, 60 and 140 ppm. The mineralized bed varies in thickness from a few cm to 2 m. It consists of alternating altered and unaltered sandstone. Bangladesh and Australian experts have separated monazite, zircon, ilmenite, rutile and magnetite from local sands at Cox's Bazar, 96 km southeast of Dacca. Radioactive mineral content is around 3,1% and exploitation may be feasible. Concerning the present status of exploration the technical assistance mission of the IAEA in the field of uranium exploration in Bangladesh is continuing with the objective to evaluate uranium potential in Chittongong and Sylhet district. Concerning areas favourable for uranium first priority should be given to areas of Hari River and Kalipur Chara where radioactive anomalies were detected. In general the area covered by Tipam Sandstone appears to be favourable for uranium mineralization. The potential for new discoveries in Bangladesh appears to be not too bad. Speculative potential could be in the order of 1-10,000 tons uranium

Practical issues in discriminating between environmental and occupational sources in a uranium urinalysis bioassay program

International Nuclear Information System (INIS)

Long, M.P.; Carbaugh, E.H.; Fairrow, N.L.

1994-11-01

Workers at two Department of Energy facilities, the Pantex Plant in Texas and the Hanford Site in Washington, are potentially exposed to class Y depleted or natural uranium. Since trace amounts of uranium are naturally present in urine excretion, site bioassay programs must be able to discern occupational exposure from naturally occurring uranium exposure. In 1985 Hanford established a 0.2-μg/d environmental screening level for elemental uranium in urine; the protocol was based on log-normal probability analysis of unexposed workers. A second study of background uranium levels commenced in 1990, and experiences in the field indicated that there seemed to be an excessive number of urine samples with uranium above the screening level and that the environmental screening level should be reviewed. Due to unforeseen problems, that second study was terminated before the complete data could be obtained. Natural uranium in rock (by weight, 99.27% 288 U, 0.72% 235 U, and 0.006% 234 U) has approximately equal activity concentrations of 238 U and 234 U. Earlier studies, summarized by the U.S. Environmental Protection Agency in 51 FR 32068, have indicated that 234 U (via 234 Th) has a greater environmental mobility than 238 U and may well have a higher concentration in ground water. By assuming that the 238 U-to 234 U ratio in the urine of nonoccupationally exposed persons should reflect the ratio of environmental levels, significant occupational exposure to depleted uranium would shift that ratio in favor of 238 U, allowing use of the ratio as a co-indicator of occupational exposure in addition to the isotope-specific screening levels. This approach has been adopted by Pantex. The Pacific Northwest Laboratory is studying the feasibility of applying this method to the natural and recycled uranium mixtures encountered at Hanford. The Hanford data included in this report represent work-in-progress

Geology and evaluation of the uranium mineral occurrence at Igdlorssuit, South Greenland

International Nuclear Information System (INIS)

Armour-Brown, A.

1986-05-01

Geological and radiometric mapping, and petrological and mineralogical investigations were made of a uranium mineral occurrence at Igdlorssuit, South Greenland during 1984 and 1985. The results have been evaluated in terms of the uranium potential and genesis the showing. The work was part of the South Greenland Exploration Programme (Sydex) carried out by the Geological Survey of Greenland (GGU) in cooperation with Risoe National Laboratory (Risoe). It was financed by the Danish Ministry of Energy. Igdlorssuit is located at the northerly limit of the fjord system about 60 km north of Kap Farvel (60 deg. 23 min.; 46 deg. 06 min.). The main uranium mineral showing is on a small alp on the eastern side, 500 m vertically above the fjord. Detailed plane table mapping (1:1000), and radiometric measurements with a lead collimated scintillometer calibrated for uranium delineated this occurrence: Regional mapping (1:10 000), however, showed that it was only one of many similar uranium occurrences in the area albeit the largest and richest. Over 35 uranium mineral occurences have been found scattered over the hillside. Textural and paragenetic relationships, and isotopic data show that the uranium was present in the supracrustal units before the folding, metamorphism and intrusion of the granite. The largest, highest grade uranium mineralised zone is about 50m long and up to 5m wide with an average grade of 0.31% with highs up to 7%. The results of the mapping and sampling has established that this type of mineral occurence can reach economic grades, and its surface expression suggests a size which could approach economic proportions. 3 maps, 30 refs. (EG)

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Ghana

International Nuclear Information System (INIS)

1985-01-01

A report has recently been published which describes the findings of the International Uranium Resources Evaluation Project (IUREP) Mission to Ghana. The IUREP Orientation Phase Mission to Ghana estimates that the Speculative Resources of that country fall within the range of 15 000 to 40 000 tonnes of uranium. The majority of this potential is expected to be located in the Proterozoic Panafrican Mobile Belt (up to 17 000 tonnes uranium) and the Paleozoic Obosum Beds of the Voltaian basin (up to 15 000 tonnes uranium), the remainder being associated with various other geological environments. The mission recommends that over a period of three (3) years approximately U.S. $5 million) would be spent on exploration in Ghana. A major part of this (U.S $2 million) would be spent on an airborne spectrometer survey over the Voltaian basin (Obosum beds), much of the remainder being spent on ground surveys, trenching and percussion drilling. (author)

Uranium Mill Tailings remedial action project waste minimization and pollution prevention awareness program plan

International Nuclear Information System (INIS)

1994-07-01

The purpose of this plan is to establish a waste minimization and pollution prevention awareness (WM/PPA) program for the U.S. Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The program satisfies DOE requirements mandated by DOE Order 5400.1. This plan establishes planning objectives and strategies for conserving resources and reducing the quantity and toxicity of wastes and other environmental releases

International Uranium Resources Evaluation Project (IUREP) orientation phase mission report: Cameroon. Draft

International Nuclear Information System (INIS)

Trey, Michel de; Leney, George W.

1983-05-01

The purpose of the International Uranium Resource Evaluation Project (IUREP) missions to host nations is to: R eview the present body of knowledge pertinent to the existence of uranium resources, to review and evaluate the potential for the discovery of additional resources, and to suggest new exploration efforts which might be carried out in promising areas in collaboration with the countries concerned. Guidance in the achievement of these goals is provided through a check list of desired relevant information on: general background, the potential role of nuclear energy, and organizations involved, information on the mining industry, technical manpower employed or available, available maps, aerial photographs, and publications, national geological survey and organizations involved in uranium, private organizations involved in uranium exploration and mining, results of previous exploration, known uranium occurrences, plans for further work, legal and administrative requirements for exploration and logistical information on facilities available. The economy of CAMEROON is sound and continues to expand with an annual growth rates of 5-6%. Emphasis is placed on private investment with government participation in major development projects. The overall investment climate is good. Minerals exploration is carried out under nonexclusive Prospecting License and exclusive Exploration License that may later be converted to a Mining Lease or Mining Concession. Many of the conditions must be negotiated. Uranium is classified as a strategic mineral, and may be subject to special review. There is no defined policy on uranium development. Two government organizations are concerned with geology and mining. The INSTITUT DE RECHERCHES GEOLOGIQUES ET MINIERES (IRGM) conducts programs of geologic mapping and research, mineralogy, hydrology, and alternate energy sources. The DEPARTMENT OF MINES AND GEOLOGY (DMG) is responsible for all minerals exploration and mining. It includes a

77 FR 14837 - Bioassay at Uranium Mills

Science.gov (United States)

2012-03-13

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0057] Bioassay at Uranium Mills AGENCY: Nuclear Regulatory..., ``Bioassay at Uranium Mills.'' This guide describes a bioassay program acceptable to the NRC staff for uranium mills and applicable portions of uranium conversion facilities where the possibility of exposure...

Radiological aspects of in situ uranium recovery

International Nuclear Information System (INIS)

BROWN, STEVEN H.

2007-01-01

In the last few years, there has been a significant increase in the demand for Uranium as historical inventories have been consumed and new reactor orders are being placed. Numerous mineralized properties around the world are being evaluated for Uranium recovery and new mining / milling projects are being evaluated and developed. Ore bodies which are considered uneconomical to mine by conventional methods such as tunneling or open pits, can be candidates for non-conventional recovery techniques, involving considerably less capital expenditure. Technologies such as Uranium in situ leaching in situ recovery (ISL / ISR), have enabled commercial scale mining and milling of relatively small ore pockets of lower grade, and may make a significant contribution to overall world wide uranium supplies over the next ten years. Commercial size solution mining production facilities have operated in the US since 1975. Solution mining involves the pumping of groundwater, fortified with oxidizing and complexing agents into an ore body, solubilizing the uranium in situ, and then pumping the solutions to the surface where they are fed to a processing plant. Processing involves ion exchange and may also include precipitation, drying or calcining and packaging operations depending on facility specifics. This paper presents an overview of the ISR process and the health physics monitoring programs developed at a number of commercial scale ISL / ISR Uranium recovery and production facilities as a result of the radiological character of these processes. Although many radiological aspects of the process are similar to that of conventional mills, conventional-type tailings as such are not generated. However, liquid and solid byproduct materials may be generated and impounded. The quantity and radiological character of these by products are related to facility specifics. Some special monitoring considerations are presented which are required due to the manner in which Radon gas is evolved in

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)

Evaluation of chemical stabilizers and windscreens for wind erosion control of uranium mill tailings

International Nuclear Information System (INIS)

Elmore, M.R.; Hartley, J.N.

1984-08-01

Potential wind erosion of uranium mill tailings is a concern for the surface disposal of tailings at uranium mills. Wind-blown tailings may subsequently be redeposited on areas outside the impoundment. Pacific Northwest Laboratory (PNL) is investigating techniques for fugitive dust control at uranium mill tailings piles. Laboratory tests, including wind tunnel studies, were conducted to evaluate the relative effectiveness of 43 chemical stabilizers. Seventeen of the more promising stabilizers were applied to test plots on a uranium tailings pile at the American Nuclear Corporation-Gas Hills Project mill site in central Wyoming. The durabilities of these materials under actual site conditions were evaluated over time. In addition, field testing of commercially available windscreens was conducted. Test panels were constructed of eight different materials at the Wyoming test site to compare their durability. A second test site was established near PNL to evaluate the effectiveness of windscreens at reducing wind velocity, and thereby reduce the potential for wind erosion of mill tailings. Results of the laboratory land field tests of the chemical stabilizers and windscreens are presented, along with costs versus effectiveness of these techniques for control of wind erosion at mill tailings piles. 12 references, 4 figures, 6 tables

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Madagascar

International Nuclear Information System (INIS)

1985-01-01

A report has recently been made public which describes the findings of the International Uranium Resources Evaluation Project (IUREP) Mission to Madagascar. The IUREP Orientation Phase Mission to Madagascar estimates the Speculative Resources of that country to be within the wide range of 4 000 to 38 000 tonnes uranium. Such resources could lie in areas with known occurrences (uranothorianite, Ft. Dauphin up to 5 000 t U, i.e. 'pegmatoids'; uranocircite, Antsirabe up to 3 000 t U in Neogene sediments; carnotiteautonite, Karoo area up to 30 000 t U in sandstones and in areas with as yet untested environments (e.g. related to unconformities and calcretes). Modifications to existing uranium exploration programmes are suggested and policy alternatives reviewed. No specific budget is proposed. (author)

Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

Energy Technology Data Exchange (ETDEWEB)

1994-02-01

In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE`s overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program.

Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

International Nuclear Information System (INIS)

1994-02-01

In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE's overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program

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

The technical feasibility of uranium enrichment for nuclear bomb construction at the parallel nuclear program plant

International Nuclear Information System (INIS)

Rosa, L.P.

1990-01-01

It is discussed the hole of the Parallel Nuclear Program is Brazil and the feasibility of uranium enrichment for nuclear bomb construction. This program involves two research centers, one belonging to the brazilian navy and another to the aeronautics. Some other brazilian institutes like CTA, IPEN, COPESP and CETEX and also taking part in the program. (A.C.A.S.)

Preparation of uranium targets and application of analytical techniques for its evaluation

International Nuclear Information System (INIS)

Luna Z, D.

1994-01-01

The objective of this work is to establish a method to produce uranium targets. The method selected for this purpose was the molecular plating. The first part of this work is devoted to the proper selection of an analytical technique to evaluate the different steps of the molecular plating method. Neutron Activation Analysis was chosen, because its high sensitivity and can be adapted easily to follow the whole procedure. The second part presents the experimental procedure and the study of the different parameters involved in the molecular plating and the evaluation of its uniformity was made using plastic track detectors. The results obtained are presented and a procedure is suggested to produce uranium targets. (Author)

Mechanical properties of depleted uranium-2 w/o molybdenum alloy

International Nuclear Information System (INIS)

Deel, O.L.; Burian, R.J.

1979-01-01

The primary objective of this program is to develop data and techniques for determining the dynamic impact response of radioactive-material shipping-container systems for environmental control and safety overview and assessment. One phase of this program is the dynamic testing of 1/8-, 1/4-, and 1/2-scale models of uranium-shielded truck casks. These linearly scaled models are fabricated from the same materials typically used in full-size prototype casks. In order to analytically evaluate the results of dynamic tests, it is necessary to know the mechanical properties of the materials of construction. Since the properties of cast uranium--molybdenum alloys vary significantly with casting and heat-treating techniques, it is necessary to fully characterize the mechanical properties of the uranium used in the model tests. This report presents the results of these studies. The uranium alloy exhibited a tensile strength equal to or greater than that reported by others. As indicated by the percentage of elongation and reduction in area, the ductility was lower. Comparative data for the other mechanical properties measured were not found in the literature

Toxicity of Uranium Adsorbent Materials using the Microtox Toxicity Test

Energy Technology Data Exchange (ETDEWEB)

Park, Jiyeon [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jeters, Robert T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gill, Gary A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kuo, Li-Jung [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bonheyo, George T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-10-01

The Marine Sciences Laboratory at the Pacific Northwest National Laboratory evaluated the toxicity of a diverse range of natural and synthetic materials used to extract uranium from seawater. The uranium adsorbent materials are being developed as part of the U. S. Department of Energy, Office of Nuclear Energy, Fuel Resources Program. The goal of this effort was to identify whether deployment of a farm of these materials into the marine environment would have any toxic effects on marine organisms.

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

International Nuclear Information System (INIS)

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

2007-01-01

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

Innovative industry alignment at RMIT to develop skills for uranium industries

International Nuclear Information System (INIS)

Bhargava, S.K.

2010-01-01

'Full text:' RMIT University has recently introduced new teaching and research training programs on uranium processing technology at both undergraduate and postgraduate level. These programs have been implemented to improve young scientists and engineers' awareness of Australia's uranium processing industry, and to help provide future employees with improved background knowledge to the industry. The teaching program involves joint course development and lectures delivered by the leading scientists from ANSTO (Dr Suzanne Burling and Dr Chris Griffith) and Rio Tinto (Dr Stephen Grocott). This lecture series, which is offered to final year applied science and chemical engineering students, covers a range of topics and issues related to uranium processing including uranium mining, methods for chracterising uranium ores, extraction of uranium, the nuclear fuel cycle, waste and safety. The research training program involves honours and PhD students undertaking research projects on uranium mineralogy and uranium extraction. Research students are also provided with extensive training on how to conduct research safely using radioactive materials. The research programs are undertaken in RMIT's new EPA approved, low level radiation laboratory which has been dedicated to research projects on uranium processing. An extended overview of both of these new programs will be presented. This program is unique in Australia and is designed to address the issue of skill shortage in the ever growing Uranium industry world wide. International collaborators in this program will be most welcomed. (author)

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

Radiometric method for the determination of uranium in soil and air: single-laboratory evaluation and interlaboratory collaborative study

International Nuclear Information System (INIS)

Casella, V.R.; Bishop, C.T.; Glosby, A.A.

1980-02-01

Results of a single-laboratory evaluation and an interlaboratory collaborative study of a method for determining uranium isotopes in soil and air samples are presented. The method is applicable to 10-gram soil samples and to both glass fiber and polystyrene (Microsorban) air filter samples. Sample decomposition is accomplished with a nitric-hydrofluoric acid dissolution. After a solvent extraction step to remove most of the iron present, the uranium is isolated by anion exchange chromatography and electrodeposition. Alpha spectrometry is used to measure the uranium isotopes. Two soil samples, a glass fiber air filter sample, and a polystyrene air filter sample were used to evaluate the method for uranium concentrations ranging from a few tenths to about one hundred disintegrations per minute per sample. Tracer recoveries for the single-laboratory evaluation averaged 78%, while the tracer recoveries for the collaborative study averaged 66%. Although the precision of the collaborative study results did not approach counting statistics errors, the measured uranium concentrations for these samples agreed to within 5% of the reference concentrations when the uranium concentration was greater than one disintegration per minute per gram of soil or one disintegration per minute per air filter

Investigation of Alaska's uranium potential. Part 1. Reconnaissance program, West-Central Alaska and Copper River basin. Part 2. Uranium and thorium in granitic and alkaline rocks in Western Alaska

International Nuclear Information System (INIS)

Eakins, G.R.; Jones, B.K.; Forbes, R.B.

1977-02-01

A 6-week reconnaissance program was conducted in west-central Alaska and in the Copper River basin--Chitina River valley area to aid in determining the uranium potential of the state. Division personnel also submitted samples from the Healy, Eagle, and Charley River quadrangles. Collected were 916 stream-sediment samples and 427 bedrock samples for uranium, thorium, and potassium oxide determinations, and 565 water samples for uranium analyses. A statistical analysis of the determinations was made using a computer at the University of Alaska. Thresholds, anomalies, and U:Th ratios were calculated for eight separate regions. Anomalous values of the U, Th, and K 2 O, and radiometric measurements are discussed. A combination of all uranium exploration techniques is needed to locate potential uranium deposits in Alaska. Correlations between aerial and ground radiometric surveys and geochemical surveys were often lacking, indicating that each method may or may not be effective, depending on local conditions. One hundred and eight rock samples were selected from traverses across five plutons in western Alaska and analyzed for uranium, thorium, and potassium. The highest uranium concentrations detected were 86 and 92 ppM from a mineralized dike intrusion zone in the Selawik Lake Complex. Analysis of individual plutons yields strong correlations between mineralogy and radioactivity. The mineralogical variable that correlates with uranium or thorium varies from one pluton to the next. Based on these correlations, mineralogical guidelines are offered for the selection of uranium enriched variants in four of the five plutons

International Uranium Resources Evaluation Project (IUREP) national favourability studies: United States of America

International Nuclear Information System (INIS)

1977-08-01

In the first years of the uranium program, starting in 1948, drilling was primarily undertaken by the government. The AEC and the U.S. Geological Survey continued a modest program until the mid-1950's. The government drilled about 5-6 million feet (1.7 million meters), and a number of significant ore deposits were defined, primarily in the Uravan Mineral Belt, Colorado. Except for the early years, private drilling exceeded the government program. Drilling reached a peak of 2.8 million meters in 1957, but dropped back to 0.6 million meters in 1965 when the government purchase program had been phased out. Later, with resurgence of uranium demand it rose again to nearly 9.1 million meters in 1969. After a decline in the early 1970's, activity rose dramatically to 10.3 million meters in 1976. Total drilling through 1976 has been about 88.3 million meters. Exploration costs from 1966 through 1976 are estimated to be $679 million. During 1976, 32 percent of the drilling or 3.3 million meters was in the Wyoming Basins, with 4.5 million meters or 43 percent in the Colorado Plateau, and 0.9 million meters or 8 percent in the Gulf Coastal Plain. Total 1976 drilling was 0.9 million meters and average depth of hole 155 meters; this contrasts with 1.7 million meters and 53 meters average depth in 1960. Reserves of uranium are located in the western portion of the country with over 85 percent in the Colorado Plateau and Wyoming Basins. The Basin and Range province of Oregon, California, Nevada, Arizona, New Mexico, and Texas is receiving considerable exploration emphasis. Other areas of increasing activity include sedimentary rocks of the Great Plains and the crystalline rocks of the Rocky Mountains, Appalachian Mountains, and the Precambrian shield of Michigan and Wisconsin. Work in the new areas emphasizes geologic and geophysical assessment, so relatively little drilling has been done. When programs have matured, it is assumed that drilling effort will be accelerated

Computer programs for data reduction and interpretation in plutonium and uranium analysis by gamma ray spectrometry

International Nuclear Information System (INIS)

Singh, R.K.; Moorthy, A.D.; Babbar, R.K.; Udagatti, S.V.

1989-01-01

Non destructive gamma ray have been developed for analysis of isotopic abundances and concentrations of plutonium and uranium in the respective product solutions of a reprocessing plant. The method involves analysis of gamma rays emitted from the sample and uses a multichannel analyser system. Data reduction and interpretation of these techniques are tedious and time consuming. In order to make it possible to use them in routine analysis, computer programs have been developed in HP-BASIC language which can be used in HP-9845B desktop computer. A set of programs, for plutonium estimation by high resolution gamma ray spectrometry and for on-line measurement of uranium by gamma ray spectrometry are described in this report. (author) 4 refs., 3 tabs., 6 figs

The computerized semi-quantitative comprehensive identification-evaluation model for the large-sized in-situ leachable sandstone type uranium deposits in Northern Xinjiang, China

Energy Technology Data Exchange (ETDEWEB)

Zhengbang, Wang; Mingkuan, Qin; Ruiquan, Zhao; Shenghuang, Tang [Beijing Research Inst. of Uranium Geology, CNNC (China); Baoqun, Wang; Shuangxing, Lin [Geo-prospecting Team No. 216, CNNC (China)

2001-08-01

The process of establishment of the model includes following steps: (1) Systematically studying a known typical in-situ leachable sandstone type uranium deposit--Deposit No. 512 in Yili basin, analyzing its controlling factors and establishing its metallogenetic model; (2) Establishing the metallogenetic models of this type of uranium deposit and uranium-bearing area on the basis of comparison study on the deposit No. 512 with the same type uranium deposits in the world; (3) Creating the computerized semi-quantitative comprehensive identification-evaluation model for the large-sized in-situ leachable sandstone type uranium deposits in northern Xinjiang; (4) Determining the standards of giving a evaluation-mark for each controlling factor of in-situ leachable sandstone type uranium deposit and uranium-bearing area; (5) Evaluating uranium potential and prospect of the unknown objective target.

The computerized semi-quantitative comprehensive identification-evaluation model for the large-sized in-situ leachable sandstone type uranium deposits in Northern Xinjiang, China

International Nuclear Information System (INIS)

Wang Zhengbang; Qin Mingkuan; Zhao Ruiquan; Tang Shenghuang; Wang Baoqun; Lin Shuangxing

2001-01-01

The process of establishment of the model includes following steps: (1) Systematically studying a known typical in-situ leachable sandstone type uranium deposit--Deposit No. 512 in Yili basin, analyzing its controlling factors and establishing its metallogenetic model; (2) Establishing the metallogenetic models of this type of uranium deposit and uranium-bearing area on the basis of comparison study on the deposit No. 512 with the same type uranium deposits in the world; (3) Creating the computerized semi-quantitative comprehensive identification-evaluation model for the large-sized in-situ leachable sandstone type uranium deposits in northern Xinjiang; (4) Determining the standards of giving a evaluation-mark for each controlling factor of in-situ leachable sandstone type uranium deposit and uranium-bearing area; (5) Evaluating uranium potential and prospect of the unknown objective target

Neutron activation analysis for uranium and associated elements

International Nuclear Information System (INIS)

Bowman, W.W.

1977-01-01

The samples obtained by the Savannah River Laboratory as part of the National Uranium Resource Evaluation program are activated in the intense neutron flux from a Savannah River Plant production reactor. A pilot-scale facility was installed at the reactor site to provide analyses of samples through the initial phase of the program and to develop design data for a full-scale facility. Sediments are analyzed by direct activation of 0.5-g samples. However, to analyze ground or surface water samples, mineral elements from 1-liter samples are concentrated on ion exchange resin and then approximately 5-g samples of resin are activated. Uranium concentration is determined by counting neutrons emitted from specific short-lived products of fission induced in 235 U by the primary neutron flux. Repetitive short cycles of irradiation and counting permit detection and determination of <0.1 μg of uranium. Elements associated with uranium are determined by spectral analysis of the gamma ray activities induced by the cyclic and subsequent longer irradiations. The pilot facility consists of four irradiation positions (plus 2 spare positions), a sample loader and unloader, and counting stations with neutron and gamma ray detectors, all interconnected with a pneumatic sample transport system. A computer controls both the transport system and the data acquisition devices. Gamma ray counting data are stored on magnetic tape for further processing by a large central computer. Facility hardware and software are described. Repetitive analyses of standards have shown an accuracy within +-10% for uranium values and within +-25% for associated elements. A quality assurance program has been developed to maintain these levels of reliability

Development of methods to evaluate uranium distribution coefficients in unsaturated media

International Nuclear Information System (INIS)

Sautman, M.T.; Simonson, S.A.

1993-01-01

To date, batch sorption and dynamic column experiments have been performed for many elements as part of site characterization programs. These experiments were often conducted with samples having relatively high liquid/solid ratios (in some cases the solid volume was much smaller than the solution volume). The development of methods for measuring sorption parameters at low liquid/solid ratios was undertaken to attempt to judge whether or not results of saturated experiments are valid for use in performance assessments of sites located in unsaturated rocks. The amount of hydrologic saturation can affect the ionic strength, pH, and redox potential which can in turn affect sorption. In addition, the presence of the gas phase may affect the amount of wetting occurring on the solid's surface. This paper describes experimental procedures which were developed to evaluate the sorption of uranium by silica sand at predetermined levels of unsaturation

Statistical evaluation of an interlaboratory comparison for the determination of uranium by potentiometric titration

International Nuclear Information System (INIS)

Ketema, D.J.; Harry, R.J.S.; Zijp, W.L.

1990-09-01

Upon request of the ESARDA working group 'Low enriched uranium conversion - and fuel fabrication plants' an interlaboratory comparison was organized, to assess the precision and accuracy concerning the determination of uranium by the potentiometric titration method. This report presents the results of a statistical evaluation on the data of the first phase of this exercise. (author). 9 refs.; 5 figs.; 24 tabs

Performance evaluation of indigenous controlled potential coulometer for the determination of uranium and plutonium

International Nuclear Information System (INIS)

Sharma, H.S.; Jisha, V.; Noronha, D.M.; Sharma, M.K.; Aggarwal, S.K.

2007-09-01

We have carried out performance evaluation of indigenously manufactured controlled potential coulometer for the determination of uranium and plutonium respectively in Rb 2 U(SO 4 ) 3 and K 4 Pu(SO 4 ) 4 chemical assay standards. The coulometric results obtained on uranium determination showed an insignificant difference as compared with the biamperometric results at 95% and 99.9% confidence levels while for plutonium determination showed a difference of -0.4% at 95% with respect to expected value. The results obtained show that indigenous coulometer is suitable for uranium and plutonium determination in chemical assay standards. (author)

Natural uranium toxicology - evaluation of internal contamination in man; Toxicologie de l'uranium naturel - essai d'evaluation de la contamination interne chez l'homme

Energy Technology Data Exchange (ETDEWEB)

Chalabreysse, J [Commissariat a l' Energie Atomique, Pierrelatte (France). Centre d' Etudes Nucleaires

1968-07-01

After reminding the physical and chemical properties of natural uranium which might affect its toxicology, a comprehensive investigation upon natural uranium metabolism and toxicity and after applying occupational exposure standards to this particular poison, it has been determined, from accident reports and human experience reported in the related literature, a series of formulae obtained by theoretical mathematical development giving principles for internal contamination monitoring and disclosure by determining uranium in the urine of occupationally exposed individuals. An assay is performed to determine individual internal contamination according to the various contamination cases. The outlined purposes, mainly practical, required some options and extrapolations. The proposed formula allows a preliminary approach and also to determine shortly a contamination extent or to discuss the systematical urinalysis results as compared with individual radio-toxicology monitoring professional standards. (author) [French] Apres le rappel des caracteristiques physiques et des proprietes chimiques de l'uranium naturel pouvant avoir une influence sur sa toxicologie, l'etude detaillee de son metabolisme et de sa toxicite, puis l'application des normes professionnelles d'exposition au cas particulier de ce toxique, il est etabli, a partir des comptes rendus d'accidents et de l'experimentation humaine rapportes dans la litterature, une serie de formules obtenues par developpement mathematique theorique qui posent les principes de la surveillance et de la mise en evidence de la contamination interne par la recherche et le dosage de l'uranium dans les urines d'individus professionnellement exposes. Un essai d'evaluation de la contamination interne individuelle suivant les differents cas de contamination est effectue. Le formulaire propose permet de faire une premiere approximation et d'apprecier rapidement l'importance d'une contamination ou bien d'interpreter les resultats d

Natural phenomena hazards evaluation of equipment and piping of Gaseous Diffusion Plant Uranium Enrichment Facility

International Nuclear Information System (INIS)

Singhal, M.K.; Kincaid, J.H.; Hammond, C.R.; Stockdale, B.I.; Walls, J.C.

1995-01-01

In support of the Gaseous Diffusion Plant Safety Analysis Report Upgrade program (GDP SARUP), a natural phenomena hazards evaluation was performed for the main process equipment and piping in the uranium enrichment buildings at Paducah and Portsmouth gaseous diffusion plants. In order to reduce the cost of rigorous analyses, the evaluation methodology utilized a graded approach based on an experience data base collected by SQUG/EPRI that contains information on the performance of industrial equipment and piping during past earthquakes. This method consisted of a screening walkthrough of the facility in combination with the use of engineering judgment and simple calculations. By using these screenings combined with evaluations that contain decreasing conservatism, reductions in the time and cost of the analyses were significant. A team of experienced seismic engineers who were trained in the use of the DOE SQUG/EPRI Walkdown Screening Material was essential to the success of this natural phenomena hazards evaluation

Natural phenomena hazards evaluation of equipment and piping of Gaseous Diffusion Plant Uranium Enrichment Facility

Energy Technology Data Exchange (ETDEWEB)

Singhal, M.K.; Kincaid, J.H.; Hammond, C.R.; Stockdale, B.I.; Walls, J.C. [Oak Ridge National Lab., TN (United States). Technical Programs and Services; Brock, W.R.; Denton, D.R. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States)

1995-12-31

In support of the Gaseous Diffusion Plant Safety Analysis Report Upgrade program (GDP SARUP), a natural phenomena hazards evaluation was performed for the main process equipment and piping in the uranium enrichment buildings at Paducah and Portsmouth gaseous diffusion plants. In order to reduce the cost of rigorous analyses, the evaluation methodology utilized a graded approach based on an experience data base collected by SQUG/EPRI that contains information on the performance of industrial equipment and piping during past earthquakes. This method consisted of a screening walkthrough of the facility in combination with the use of engineering judgment and simple calculations. By using these screenings combined with evaluations that contain decreasing conservatism, reductions in the time and cost of the analyses were significant. A team of experienced seismic engineers who were trained in the use of the DOE SQUG/EPRI Walkdown Screening Material was essential to the success of this natural phenomena hazards evaluation.

Prospects of Using Reprocessed Uranium in CANDU Reactors, in the U.S. GNEP Program

International Nuclear Information System (INIS)

Ellis, Ronald James

2007-01-01

Current Global Nuclear Energy Partnership (GNEP) plans envision reprocessing spent fuel (SF) with view to minimizing high-level waste (HLW) repository use and recovering actinides (U, Np, Pu, Am, and Cm) for transmutation in reactors as fuel and targets. The reprocessed uranium (RU), however, is to be disposed of. This paper presents a limited-scope analysis of possible reuse of RU in CANDU (Canada Deuterium Uranium) Reactors, within the context of the US GNEP program. Other papers on this topic submitted to this conference discuss the possibility of RU reuse in light-water reactors (LWRs) (with enrichment) and offer an independent economic analysis of RU reuse. A representative RU uranium 'vector', from reprocessed spent LWR fuel, comprises 98.538 wt% 238U, 0.46 wt% 236 U, 0.986 wt% 235 U, and 0.006 wt% 234 U. After multiple recyclings, the concentration of 234 U can approach 0.02 wt%. The presence of 234 U and 236 U in RU reduces the reactivity and fuel lifetime (exit burnup), which is particularly an issue in LWRs. While in PWR analyses, the burnup penalty caused by the concentration of 236 U in RU needs to be offset by additional 235 U enrichment in the amount of ∼25% to 30% of the weight percentage of the 236 U; however, the effect in CANDU is much smaller. Furthermore, since the 235 U content in RU exceeds that of natural uranium, CANDU offers the advantageous option of uranium recycling without reenrichment. The exit burnup of CANDU RU-derived fuel is considerably larger than that for natural uranium-fueled scenario, despite the presence of 234 U and 236 U.

Corrosion resistant coatings for uranium and uranium alloys

International Nuclear Information System (INIS)

Weirick, L.J.; Lynch, C.T.

1977-01-01

Coatings to prevent the corrosion of uranium and uranium alloys are considered in two military applications: kinetic energy penetrators and aircraft counterweights. This study, which evaluated organic films and metallic coatings, demonstrated that the two most promising coatings are based on an electrodeposited nickel system and a galvanized zinc system

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

Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved; Cycles de combustibles. Production d'uranium, programme de centrales electriques et effort financier correspondant

Energy Technology Data Exchange (ETDEWEB)

Andriot, J; Gaussens, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author)Fren. [French] L'etude presentee comporte l'examen d'un certain nombre d'hypotheses de programmes de centrales nucleaires de types differents. Ces programmes correspondent a l'utilisation de tonnages d'uranium et de thorium de l'ordre de grandeur de ceux qui seront probablement produits par la France dans les quinze prochaines annees. Comme il est possible de batir un programme de centrales nucleaires, comportant a la fois plusieurs filieres suivant des variantes en nombre infini, on s'est contente d'examiner successivement les resultats ous si on utilisait exclusivement l'une des trois filieres suivantes: - filiere uranium

National Uranium Resource Evaluation: Moab Quadrangle, Colorado and Utah

International Nuclear Information System (INIS)

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

1982-09-01

Portions of the Salt Wash Member of the Morrison, the Chinle, the Rico, the Cutler, and the Entrada Formations are favorable for uranium deposits that meet the minimum size and grade requirements of the US Department of Energy within the Moab 1' x 2' Quadrangle, Utah and Colorado. Nine areas are judged favorable for the Late Jurassic Salt Wash Member. The criteria used to evaluate these areas as favorable include 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. Three favorable areas have been outlined for the Late Triassic Chinle Formation. The criteria used to evaluate these areas are the sandstone-to-shale ratios for the Chinle Formation and the distribution of the Petrified Forest Member of the Chinle, which is considered the source for the uranium. Two favorable areas have been delineated for the Permian Cutler Formation, and one for the Permian Rico Formation. The criteria used to outline favorable areas are the distribution of favorable facies within each formation. Favorable facies are those that are a result of deposition in environments that are transitional between fluvial and marine. One favorable area is outlined in the Jurassic Entrada Sandstone in the southeastern corner of the quadrangle in the Placerville district. Boundaries for this area were established by geologic mapping

Issues in uranium availability

International Nuclear Information System (INIS)

Schanz, J.J. Jr.; Adams, S.S.; Gordon, R.L.

1982-01-01

The purpose of this publication is to show the process by which information about uranium reserves and resources is developed, evaluated and used. The following three papers in this volume have been abstracted and indexed for the Energy Data Base: (1) uranium reserve and resource assessment; (2) exploration for uranium in the United States; (3) nuclear power, the uranium industry, and resource development

Extraction of uranium low-grade ores from Great Divide Basin, Wyoming. National Uranium Resource Evaluation

International Nuclear Information System (INIS)

Judd, J.C.; Nichols, I.L.; Huiatt, J.L.

1983-04-01

The US Bureau of Mines is investigating the leachability of carbonaceous uranium ore samples submitted by the DOE under an Interagency Agreement. Studies on eight samples from the Great Divide Basin, Wyoming, are the basis of this report. The uranium content of the eight ore samples ranged from 0.003 to 0.03% U 3 O 8 and contained 0.7 to 45% organic carbon. Experiments were performed to determine the feasibility of extracting uranium using acid leaching, roast-acid leaching and pressure leaching techniques. Acid leaching with 600 lb/ton H 2 SO 4 plus 10 lb/ton NaClO 3 for 18 h at 70 0 C extracted 65 to 83% of the uranium. One sample responded best to a roast-leach treatment. When roasting for 4 h at 500 0 C followed by acid leaching of the calcine using 600 lb/ton H 2 SO 4 , the uranium extraction was 82%. Two of the samples responded best to an oxidative pressure leach for 3 h at 200 0 C under a total pressure of 260 psig; uranium extractions were 78 and 82%

Evaluation of selected neutralizing agents for the treatment of uranium tailings leachates. Laboratory progress report

International Nuclear Information System (INIS)

Sherwood, D.R.; Serne, R.J.

1983-02-01

Laboratory experiments were conducted to evaluate the performance of selected neutralizing agents for the treatment of uranium tailings solutions. Highly acidic tailings solutions (pH 3 ) reagent grade; Calcium hydroxide [Ca(OH) 2 ] reagent grade; Magnesium oxide (MgO) reagent grade; Sodium carbonate (Na 2 CO 3 ) reagent grade; and Sodium hydroxide (NaOH) reagent grade. Evaluation of the effectiveness for the treatment of uranium tailings solutions for the selected neutralizing agents under controlled laboratory conditions was based on three criteria. The criteria are: (1) treated effluent water quality, (2) neutralized sludge handling and hydraulic properties, and (3) reagent costs and acid neutralizing efficiency. On the basis of these limited laboratory results calcium hydroxide or its dehydrated form CaO (lime) appears to be the most effective option for treatment of uranium tailings solutions

The future of the uranium mining industry

International Nuclear Information System (INIS)

Capus, G.; Galaud, G.

1993-01-01

This paper presents the state of natural Uranium market today. In a first part, the author gives a brief history about nuclear programs history in Usa and Europe and describes natural Uranium demand and supply (Uranium mines, recycling, excessive civil stocks, military stocks using). In a second part, evolutions and futures of Uranium industry is studied: using of excessive stocks in Western Europe, using of military stocks, recycling of Uranium from spent fuels reprocessing, uranium deposits, future natural uranium market. 6 refs., 4 figs., 3 tabs., 3 photos

Safety evaluation for packaging (onsite) depleted uranium waste boxes

Energy Technology Data Exchange (ETDEWEB)

McCormick, W.A.

1997-08-27

This safety evaluation for packaging (SEP) allows the one-time shipment of ten metal boxes and one wooden box containing depleted uranium material from the Fast Flux Test Facility to the burial grounds in the 200 West Area for disposal. This SEP provides the analyses and operational controls necessary to demonstrate that the shipment will be safe for the onsite worker and the public.

Safety evaluation for packaging (onsite) depleted uranium waste boxes

International Nuclear Information System (INIS)

McCormick, W.A.

1997-01-01

This safety evaluation for packaging (SEP) allows the one-time shipment of ten metal boxes and one wooden box containing depleted uranium material from the Fast Flux Test Facility to the burial grounds in the 200 West Area for disposal. This SEP provides the analyses and operational controls necessary to demonstrate that the shipment will be safe for the onsite worker and the public

Uranium internal exposure evaluation based on urine assay data

International Nuclear Information System (INIS)

Lawrence, J.N.P.

1984-09-01

The difficulties in assessing internal exposures to uranium from urine assay data are described. A simplified application of the ICRP-30 and ICRP Lung Model concepts to the estimation of uranium intake is presented. A discussion follows on the development of a computer code utilizing the ICRP-30-based uranium elimination model with the existing urine assay information. The calculated uranium exposures from 1949 through 1983 are discussed. 13 references, 1 table

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

International Nuclear Information System (INIS)

1977-08-01

Bolivia has an area of 1,098,580 square kilometers. Its capital is La Paz. The western part of the country is dominated by two ranges of the Andes Mountains, the Cordillera Occidental on the vest flank of the high plateau (Altiplano) and the Cordillera Real (or Oriental) on the east flank. The northern Andes average 5,486 meters in elevation; the southern Andes are not as lofty. The Altiplano is 3,658 to A,267 meters high and 129 km. in average width; it is the largest basin of inland drainage in South America and contains the renowned Lake Titicaca on the Peruvian-Bolivian border. The eastern tropical lowlands or pampas (Oriente) comprise about two-thirds of the country, with rain forest in the northern portion. An intermediate zone of valleys and basins lies between the eastern Andes and Oriente. Bolivia differs from other Andean countries, like Chile, Peru and Ecuador, in having large areas of Preeambrian schists, gneisses, migmatites and granites. These crop out in the eastern part of the country. Parts of these rocks contain banded iron formations (i.e., in the Muttin region) and are probably early Precambrian in age. Little systematic exploration for uranium was undertaken in Bolivia until the late 1960's. In 1967, 1968 and 1969 technical assistance was requested from, and provided by, the IAEA. This work led to evaluation of radioactive anomalies in veins of northeast Bolivia and in sandstones in the extreme southern part of the country. Although no uranium reserves are now credited to Bolivia, the geologic possibilities for several kinds of uranium deposits coupled with the relatively limited work done to date suggest that uranium orebodies will be discovered. It is estimated that the potential resources of Bolivia are in the range of 10,000 to 100,000 tonnes uranium

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

Preliminary Evaluation of Alternate Designs for HFIR Low-Enriched Uranium Fuel

Energy Technology Data Exchange (ETDEWEB)

Renfro, David [ORNL; Chandler, David [ORNL; Cook, David [ORNL; Ilas, Germina [ORNL; Jain, Prashant [ORNL; Valentine, Jennifer [ORNL

2014-10-30

Engineering design studies of the feasibility of conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel are ongoing at Oak Ridge National Laboratory (ORNL) as part of an effort sponsored by the U.S. Department of Energy’s Global Threat Reduction Initiative (GTRI)/Reduced Enrichment for Research and Test Reactors (RERTR) program. The fuel type selected by the program for the conversion of the five high-power research reactors in the U.S. that still use HEU fuel is a new U-Mo monolithic fuel. Studies by ORNL have previously indicated that HFIR can be successfully converted using the new fuel provided (1) the reactor power can be increased from 85 MW to 100 MW and (2) the fuel can be fabricated to a specific reference design. Fabrication techniques for the new fuel are under development by the program but are still immature, especially for the “complex” aspects of the HFIR fuel design. In FY 2012, the program underwent a major shift in focus to emphasize developing and qualifying processes for the fabrication of reliable and affordable LEU fuel. In support of this new focus and in an effort to ensure that the HFIR fuel design is as suitable for reliable fabrication as possible, ORNL undertook the present study to propose and evaluate several alternative design features. These features include (1) eliminating the fuel zone axial contouring in the previous reference design by substituting a permanent neutron absorber in the lower unfueled region of all of the fuel plates, (2) relocating the burnable neutron absorber from the fuel plates of the inner fuel element to the side plates of the inner fuel element (the fuel plates of the outer fuel element do not contain a burnable absorber), (3) relocating the fuel zone inside the fuel plate to be centered on the centerline of the depth of the plate, and (4) reshaping the radial contour of the relocated fuel zone to be symmetric about this centerline. The

Preliminary Evaluation of Alternate Designs for HFIR Low-Enriched Uranium Fuel

Energy Technology Data Exchange (ETDEWEB)

Renfro, David G [ORNL; Chandler, David [ORNL; Cook, David Howard [ORNL; Ilas, Germina [ORNL; Jain, Prashant K [ORNL; Valentine, Jennifer R [ORNL

2014-11-01

Engineering design studies of the feasibility of conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel are ongoing at Oak Ridge National Laboratory (ORNL) as part of an effort sponsored by the U.S. Department of Energy s Global Threat Reduction Initiative (GTRI)/Reduced Enrichment for Research and Test Reactors (RERTR) program. The fuel type selected by the program for the conversion of the five high-power research reactors in the U.S. that still use HEU fuel is a new U-Mo monolithic fuel. Studies by ORNL have previously indicated that HFIR can be successfully converted using the new fuel provided (1) the reactor power can be increased from 85 MW to 100 MW and (2) the fuel can be fabricated to a specific reference design. Fabrication techniques for the new fuel are under development by the program but are still immature, especially for the complex aspects of the HFIR fuel design. In FY 2012, the program underwent a major shift in focus to emphasize developing and qualifying processes for the fabrication of reliable and affordable LEU fuel. In support of this new focus and in an effort to ensure that the HFIR fuel design is as suitable for reliable fabrication as possible, ORNL undertook the present study to propose and evaluate several alternative design features. These features include (1) eliminating the fuel zone axial contouring in the previous reference design by substituting a permanent neutron absorber in the lower unfueled region of all of the fuel plates, (2) relocating the burnable neutron absorber from the fuel plates of the inner fuel element to the side plates of the inner fuel element (the fuel plates of the outer fuel element do not contain a burnable absorber), (3) relocating the fuel zone inside the fuel plate to be centered on the centerline of the depth of the plate, and (4) reshaping the radial contour of the relocated fuel zone to be symmetric about this centerline. The present

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Morocco

International Nuclear Information System (INIS)

1985-01-01

A report has recently been published on the findings of the mission to Morocco under the International Uranium Resources Evaluation Project (IUREP) Orientation Phase. The IUREP Orientation Phase Mission estimates that the speculative resources of Morocco range from 70 000 to 180 000 tonnes of uranium, half of which could be expected to occur in the Northern Provinces, which are relatively well explored, and the other half in the little explored Southern Provinces. In the north, speculative resources are fairly evenly distributed among the various types of deposit, in particular vein deposits (intragranitic and contact) linked with Hercynian and Precambrian blocks, the sandstone type deposits linked with Mesozoic strata and the volcanogenic deposits, especially of Precambrian age. The potential for large high-grade deposits, especially for those linked with unconformities and linear albitites, has been little investigated in Morocco and is chiefly thought to lie in the Precambrian in the Anti-Atlas and Southern Provinces. Here, the presence of acid volcanic rock reinforces the uranium potential, and there is also some potential for calcrete-related deposits. Phosphate-related uranium, to be recovered shortly, constitutes by far the largest reserves in Morocco, estimated at about 7 million tonnes of recoverable uranium. Recommendations have been made for further study of known occurrences and identification of new ones, such as unconformity and albitite-related deposits. (author) [fr

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Morocco

International Nuclear Information System (INIS)

1985-01-01

A report has recently been published on the findings of the mission to Morocco under the International Uranium Resources Evaluation Project (IUREP) Orientation Phase. The IUREP Orientation Phase Mission estimates that the speculative resources of Morocco range from 70 000 to 180 000 tonnes of uranium, half of which could be expected to occur in the Northern Provinces, which are relatively well explored, and the other half in the little explored Southern Provinces. In the north, speculative resources are fairly evenly distributed among the various types of deposit, in particular vein deposits (intragranitic and contact) linked with Hercynian and Precambrian blocks, the sandstone type deposits linked with Mesozoic strata and the volcanogenic deposits, especially of Precambrian age. The potential for large high-grade deposits, especially for those linked with unconformities and linear albitites, has been little investigated in Morocco and is chiefly thought to lie in the Precambrian in the Anti-Atlas and Southern Provinces. Here, the presence of acid volcanic rock reinforces the uranium potential, and there is also some potential for calcrete-related deposits. Phosphate-related uranium, to be recovered shortly, constitutes by far the largest reserves in Morocco, estimated at about 7 million tonnes of recoverable uranium. Recommendations have been made for further study of known occurrences and identification of new ones, such as unconformity and albitite-related deposits. (author)

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

International Nuclear Information System (INIS)

1977-12-01

The geology of Israel is relatively simple. Most of the country is underlain by sedimentary rocks of Secondary and Tertiary age. As far as the IAEA is aware no systematic exploration has been done for conventional type uranium deposits. Israel has no uranium deposits, and no high or low-grade uranium ores. However, there are uranium 'sources' which are mainly phosphate rock.Proven phosphate reserves in Israel are estimated at about 220 million tons in five different locations. The average uranium concentration is between 100 and 170 ppm. This makes the uranium content in the proven phosphate reserves of Israel to be about 25,000 tons. Together with the possibility of additional discoveries and on the assumption that the economic conditions for the production of both phosphate and uranium become favourable the Speculative Potential is placed in the 10,000 to 50,000 tonnes uranium category. (author)

National Uranium Resource Evaluation: Lewistown Quadrangle, Montana

International Nuclear Information System (INIS)

Culver, J.C.

1982-09-01

Uranium resources in the Lewistown Quadrangle, Montana, were evaluated to a depth of 1500 m (5000 ft). All existing geologic data were considered, including geologic surveys, literature, theses, radiometric surveys, oil- and water-well logs. Additional data were generated during the course of two field seasons, including the collection of more than 350 water, rock, crude oil and panned concentrate samples for analyses, sedimentary facies maps, structural geology and isopach maps, and field examination of reported areas of anomalous radioactivity. Three environments with potential for the occurrence of a minimum of 100 t of 0.01% U 3 O 8 were delineated. The most favorable environment is located in the southeastern portion of the quadrangle; here, Tertiary felsic dikes intrude four potential sandstone host rocks in the Kootenai Formation and the Colorado Shale. Structural-chemical traps for allogenic uranium are provided by the juxtaposition of oil-bearing domes. A second potential environment is located in the Eagle Sandstone in the northwestern and western portions of the quadrangle; here, anomalous water samples were obtained downtip from oxidized outcrops that are structurally related to Tertiary intrusive rocks of the Bearpaw and Highwood Mountains. Lignitic lenses and carbonaceous sandstones deposited in a near-shore lagoonal and deltaic environment provide potential reductants for hexavalent uranium in this environment. A third environment, in the Judith River Formation, was selected as favorable on the basis of water-well and gamma-ray log anomalies and their structural relationship with the Bearpaw Mountains. Organic materials are present in the Judith River Formation as potential reductants. They were deposited in a near-shore fluvial and lagoonal system similar to the depositional environment of the Jackson Group of the Texas Gulf Coast

Quality assurance program plan for the radiological survey activities program: Uranium Mill Tailings Remedial Action Project

International Nuclear Information System (INIS)

Ramos, S.J.; Berven, B.A.; Little, C.A.

1986-08-01

The Radiological Survey Activities (RASA) program at Oak Ridge National Laboratory (ORNL) is responsible for surveying designated sites in the vicinity of 24 inactive mill sites involved in the Department of Energy's (DOE) Uranium Mill Tailings Remedial Action Project (UMTRAP). The purpose of these surveys is to provide a recommendation to DOE whether to include or exclude the site from UMTRAP based on whether the onsite residual radioactive material (if any) originated from the former mill sites, and radiation levels onsite are in excess of appropriate Environmental Protection Agency (EPA) criteria. This report describes the quality assurance program plan for the RASA program in conducting all activities related to the UMTRA project. All quality assurance provisions given by the DOE, DOE/UMTRA, and ORNL organizations are integrated into this plan. Specifically, this report identifies the policies and procedures followed in accomplishing the RASA/UMTRAP QA program, identifies those organizational units involved in the implementation of these procedures, and outlines the respective responsibilities of those groups

Quality assurance program plan for the Radiological Survey Activities Program - Uranium Mill Tailings Remedial Action Project

International Nuclear Information System (INIS)

Ramos, S.J.; Berven, B.A.; Little, C.A.

1986-01-01

The Radiological Survey Activities (RASA) program at Oak Ridge National Laboratory (ORNL) is responsible for surveying designated sites in the vicinity of 24 inactive mill sites involved in the Department of Energy's (DOE) Uranium Mill Tailings Remedial Action Project (UMTRAP). The purpose of these surveys is to provide a recommendation to DOE whether to include or exclude the site from UMTRAP based on whether the onsite residual radioactive material (if any) originated from the former mill sites, and radiation levels onsite are in excess of appropriate Environmental Protection Agency (EPA) criteria. This report describes the quality assurance program plan for the RASA program in conducting all activities related to the UMTRA project. All quality assurance provisions given by the DOE, DOE/UMTRA, and ORNL organizations are integrated into this plan. Specifically, this report identifies the policies and procedures followed in accomplishing the RASA/UMTRAP QA program, identifies those organizational units involved in the implementation of these procedures, and outlines the respective responsibilities of those groups

Evaluation of uranium geochemical anomalies in the Charlotte 10 x 20 NTMS quadrangle

International Nuclear Information System (INIS)

Carpenter, R.H.

1981-11-01

This report contains a synthesis of published geological, geophysical, and geochemical information for portions of Cabarrus and Rowan Counties, NC, where uranium geochemical anomalies have been described by Heffner and Ferguson (1978). The results of a ground radiation survey in selected areas are also described. Based on an evaluation of published information and the data obtained in the field study, conclusions are made regarding the possible occurrence of uranium concentration. Recommendations for detailed surveys in certain areas are also presented

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Zambia

International Nuclear Information System (INIS)

1985-01-01

A report has recently been published which describes the findings of the International Uranium Resources Evaluation Project (IUREP) mission to Zambia. The IUREP Orientation Phase mission to Zambia estimates that the Speculative Resources of that country fall within the range of 33 000 and 100 000 tonnes uranium. The majority of these resources are believed to exist in the Karoo sediments. Other potentially favourable geological environments are the Precambrian Katanga sediments, as well as intrusive rocks of different chemical compositions and surficial duricrusts. Previous unofficial estimates of Zambia's Reasonably Assured Resources (RAR) and Estimated Additional Resources (EAR) are considered to be still valid: the total RAR amount to 6 000 tonnes uranium, located in Karoo (4 000 tonnes) and Katanga (2 000 tonnes) sediments, while the EAR are believed to total 4 000 tonnes being found only in Karoo sediments. The mission recommends that approximately US$ 40 million be spent on uranium exploration in Zambia over 10 years. The largest part of this expenditure would be for drilling, while the remainder should be spent on airborne and ground surveys, as well as on interpretative work on previous airborne data, Landsat imageries, etc. (author)

Geological and geochemical aspects of uranium deposits. A selected, annotated bibliography. Vol. 1

International Nuclear Information System (INIS)

White, M.B.; Garland, P.A.

1977-10-01

This bibliography was compiled by selecting 580 references from the Bibliographic Information Data Base of the Department of Energy's (DOE) National Uranium Resource Evaluation (NURE) Program. This data base and five others have been created by the Ecological Sciences Information Center to provide technical computer-retrievable data on various aspects of the nation's uranium resources. All fields of uranium geology are within the defined scope of the project, as are aerial surveying procedures, uranium reserves and resources, and universally applied uranium research. References used by DOE-NURE contractors in completing their aerial reconnaissance survey reports have been included at the request of the Grand Junction Office, DOE. The following indexes are provided to aid the user in locating reference of interest: author, keyword, geographic location, quadrangle name, geoformational index, and taxonomic name

System for the hydrogeologic analysis of uranium mill waste disposal sites

International Nuclear Information System (INIS)

Osiensky, J.L.

1983-01-01

Most of the uranium mill wastes generated before 1977 are stored in unlined tailings ponds. Seepage from some of these ponds has been of sufficient severity that the US Nuclear Regulatory Commission (NRC) has required the installation of withdrawal wells to remove the contaminated groundwater. Uranium mill waste disposal facilities typically are located in complex hydrogeologic environments. This research was initiated in 1980 to analyze hydrogeologic data collected at seven disposal sites in the US that have experienced problems with groundwater contamination. The characteristics of seepage migration are site specific and are controlled by the hydrogeologic environment in the vicinity of each tailings pond. Careful monitoring of most seepage plumes was not initiated until approximately 1977. These efforts were accelerated as a consequence of the uranium Mill Tailings Act of 1979. Some of the data collected at uranium mill waste disposal sites in the past are incomplete and some were collected by methods that are outdated. Data frequently were collected in sequences which disrupted the continuity of the hydrogeologic analysis and decreased the effectiveness of the data collection programs. Evaluation of data collection programs for seven uranium mill waste disposal sites in the US has led to the development and presentation herein of a system for the hydrogeologic analysis of disposal sites

Uranium mining

International Nuclear Information System (INIS)

Lange, G.

1975-01-01

The winning of uranium ore is the first stage of the fuel cycle. The whole complex of questions to be considered when evaluating the profitability of an ore mine is shortly outlined, and the possible mining techniques are described. Some data on uranium mining in the western world are also given. (RB) [de

Research Establishment progress report 1978 - uranium fuel cycle

International Nuclear Information System (INIS)

1978-12-01

A report of research programs continuing in the following areas is presented: mining and treatment of uranium ores, uranium enrichment, waste treatment, reprocessing and the uranium fuel cycle. Staff responsible for each project are indicated

Overview of toxicity data and risk assessment methods for evaluating the chemical effects of depleted uranium compounds

International Nuclear Information System (INIS)

Hartmann, H.M.; Monette, F.A.; Avci, H.I.

2000-01-01

In the United States, depleted uranium is handled or used in several chemical forms by both governmental agencies and private industry (primarily companies producing and machining depleted uranium metal for military applications). Human exposure can occur as a result of handling these compounds, routine low-level effluent releases to the environment from processing facilities, or materials being accidentally released from storage locations or during processing or transportation. Exposure to uranium can result in both chemical and radiological toxicity, but in most instances chemical toxicity is of greater concern. This article discusses the chemical toxic effects from human exposure to depleted uranium compounds that are likely to be handled during the long-term management and use of depleted uranium hexafluoride (UF 6 ) inventories in the United States. It also reviews representative publications in the toxicological literature to establish appropriate reference values for risk assessments. Methods are described for evaluating chemical toxicity caused by chronic low-level exposure and acute exposure. Example risk evaluations are provided for illustration. Preliminary results indicate that chemical effects of chronic exposure to uranium compounds under normal operating conditions would be negligibly small. Results also show that acute exposures under certain accident conditions could cause adverse chemical effects among the populations exposed.

Evaluation of methods for cleaning low carbon uranium metal and alloy samples

International Nuclear Information System (INIS)

Kirchner, K.; Dixon, M.

1979-01-01

Several methods for cleaning uranium samples prior to carbon analysis, using a Leco Carbon Analyzer, were evaluated. Use of Oakite Aluminum NST Cleaner followed by water and acetone rinse was found to be the best overall technique

Hydrogeological analysis applied to regional evaluation of sandstone-type uranium ore-formation in sedimentary basins

International Nuclear Information System (INIS)

Xu Laisheng

2005-01-01

The main purpose of regional evaluation of uranium ore-formation is to preliminarily divide environmental zones and to delineate favourable areas for uranium ore-formation in order to provide basis for further detailed prospecting work. Of the various kinds of prospecting work, the hydrogeologic work should be mainly carried out in following aspects: division of hydrogeological units, the determination of artesian water-bearing system and the identification of prospecting target horizon; the analysis on hydrodynamic regime, the analysis on hydrogeochemical environments, the paleo-hydrogeologic analysis and the delineation of redox front and favourable area for uranium ore-formation. (author)

Hypertension and hematologic parameters in a community near a uranium processing facility

International Nuclear Information System (INIS)

Wagner, Sara E.; Burch, James B.; Bottai, Matteo; Pinney, Susan M.; Puett, Robin; Porter, Dwayne; Vena, John E.; Hebert, James R.

2010-01-01

Background: Environmental uranium exposure originating as a byproduct of uranium processing can impact human health. The Fernald Feed Materials Production Center functioned as a uranium processing facility from 1951 to 1989, and potential health effects among residents living near this plant were investigated via the Fernald Medical Monitoring Program (FMMP). Methods: Data from 8216 adult FMMP participants were used to test the hypothesis that elevated uranium exposure was associated with indicators of hypertension or changes in hematologic parameters at entry into the program. A cumulative uranium exposure estimate, developed by FMMP investigators, was used to classify exposure. Systolic and diastolic blood pressure and physician diagnoses were used to assess hypertension; and red blood cells, platelets, and white blood cell differential counts were used to characterize hematology. The relationship between uranium exposure and hypertension or hematologic parameters was evaluated using generalized linear models and quantile regression for continuous outcomes, and logistic regression or ordinal logistic regression for categorical outcomes, after adjustment for potential confounding factors. Results: Of 8216 adult FMMP participants 4187 (51%) had low cumulative uranium exposure, 1273 (15%) had moderate exposure, and 2756 (34%) were in the high (>0.50 Sievert) cumulative lifetime uranium exposure category. Participants with elevated uranium exposure had decreased white blood cell and lymphocyte counts and increased eosinophil counts. Female participants with higher uranium exposures had elevated systolic blood pressure compared to women with lower exposures. However, no exposure-related changes were observed in diastolic blood pressure or hypertension diagnoses among female or male participants. Conclusions: Results from this investigation suggest that residents in the vicinity of the Fernald plant with elevated exposure to uranium primarily via inhalation exhibited

Hypertension and hematologic parameters in a community near a uranium processing facility

Energy Technology Data Exchange (ETDEWEB)

Wagner, Sara E., E-mail: swagner@uga.edu [College of Public Health, Department of Epidemiology and Biostatistics, Paul D. Coverdell Center for Biomedical and Health Sciences, University of Georgia, 500 D.W. Brooks Drive, Athens, GA 30602-7396 (United States); Burch, James B. [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States); South Carolina Statewide Cancer Prevention and Control Program, Columbia, SC (United States); WJB Dorn Veteran' s Affairs Medical Center, Columbia, SC (United States); Bottai, Matteo [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States); Pinney, Susan M. [College of Medicine, Department of Environmental Health, University of Cincinnati, Cincinnati, OH (United States); Puett, Robin [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States); South Carolina Statewide Cancer Prevention and Control Program, Columbia, SC (United States); Arnold School of Public Health, Department of Environmental Health Sciences, University of South Carolina, Columbia, SC (United States); Porter, Dwayne [Arnold School of Public Health, Department of Environmental Health Sciences, University of South Carolina, Columbia, SC (United States); Vena, John E. [College of Public Health, Department of Epidemiology and Biostatistics, Paul D. Coverdell Center for Biomedical and Health Sciences, University of Georgia, 500 D.W. Brooks Drive, Athens, GA 30602-7396 (United States); Hebert, James R. [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States); South Carolina Statewide Cancer Prevention and Control Program, Columbia, SC (United States)

2010-11-15

Background: Environmental uranium exposure originating as a byproduct of uranium processing can impact human health. The Fernald Feed Materials Production Center functioned as a uranium processing facility from 1951 to 1989, and potential health effects among residents living near this plant were investigated via the Fernald Medical Monitoring Program (FMMP). Methods: Data from 8216 adult FMMP participants were used to test the hypothesis that elevated uranium exposure was associated with indicators of hypertension or changes in hematologic parameters at entry into the program. A cumulative uranium exposure estimate, developed by FMMP investigators, was used to classify exposure. Systolic and diastolic blood pressure and physician diagnoses were used to assess hypertension; and red blood cells, platelets, and white blood cell differential counts were used to characterize hematology. The relationship between uranium exposure and hypertension or hematologic parameters was evaluated using generalized linear models and quantile regression for continuous outcomes, and logistic regression or ordinal logistic regression for categorical outcomes, after adjustment for potential confounding factors. Results: Of 8216 adult FMMP participants 4187 (51%) had low cumulative uranium exposure, 1273 (15%) had moderate exposure, and 2756 (34%) were in the high (>0.50 Sievert) cumulative lifetime uranium exposure category. Participants with elevated uranium exposure had decreased white blood cell and lymphocyte counts and increased eosinophil counts. Female participants with higher uranium exposures had elevated systolic blood pressure compared to women with lower exposures. However, no exposure-related changes were observed in diastolic blood pressure or hypertension diagnoses among female or male participants. Conclusions: Results from this investigation suggest that residents in the vicinity of the Fernald plant with elevated exposure to uranium primarily via inhalation exhibited

Uranium-236 as an indicator of fuel-cycle uranium in ground water

International Nuclear Information System (INIS)

Jaquish, R.E.

1989-08-01

Environmental monitoring on and around the Hanford Site includes regular sampling of onsite monitoring wells and offsite farm wells. Uranium has been identified in the ground water onsite and also in water from farm wells located on the east side of the Columbia River, across from the Hanford Site. Information on the hydrology of the area indicates that the source of the offsite uranium is not the Hanford Site. This study evaluated the isotopic composition of the uranium in water from the various wells to differentiate the onsite uranium contamination from natural uranium offsite. 5 refs., 2 figs., 2 tabs

Application of multiple correlation analysis method to the prognosis and evaluation of uranium metallogenisys in Jiangzha region

International Nuclear Information System (INIS)

Zhu Hongxun; Pan Hongping; Jian Xingxiang

2008-01-01

Prognosis and evaluation of uranium resources in Jiangzha region, Sichuan province are carried out through the multiple correlation analysis method. Through combining the characteristics of the methods and geology circumstance of areas to be predict, the uranium source, rock types, structure, terrain, hot springs and red basin are selected as estimation variable (factor). The original data of reference and predict unit are listed first, then correlation degree is calculated and uranium mineralization prospect areas are discriminated finally. The result shows that the method is credible, and should be applied to the whole Ruoergai uranium metallogenic area. (authors)

Uranium purchasers reassert their influence

International Nuclear Information System (INIS)

Braatz, U.

1976-01-01

The growing uranium requirement in the Western world in the long run can be met only by a participation of the electricity generating industry and the governments of the participating countries in the development costs of new deposits, according to statements by leading representatives of the uranium producers and consumers at a symposium organized by the Uranium Institute in the summer of 1976. On the other hand, the uranium market is likely to get under more and more pressure because of the delays in nuclear power programs worldwide. It is probable that the price of uranium will soon have reached its peak for a long time to come. Uranium producers also will have to bear in mind that a price policy which makes the use of uranium unattractive compared with other sources of energy could well result in a situation in which the largest uranium consumers would build more conventional thermal power stations to bridge the time to commercial introduction of fast breeder reactors. (orig.) [de

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

Analysis performed in cooperation with the SALE program, (1)

International Nuclear Information System (INIS)

Tuboya, Takao; Wada, Yukio; Suzuki, Takeshi

1978-01-01

One of the objects of the SALE (Safeguard Analytical Laboratory Evaluation) program is a development of technique in safeguard and accountability. The SALE program was established by the United States Atomic Energy Commission's New Brunswick Laboratory in 1970. Six years later, SALE program has grown into a worldwide quality control program, receiving analysis results from about 60 laboratories that includes 19 non-U.S. laboratories. All laboratories, participating at present or in the past in the SALE program are listed in Table 1. By 1973, the program was expanded to include six different materials; uranium dioxide (UO 2 ), uranyl nitrate (U-NO 3 ), plutonium dioxide (PuO 2 ), plutonium nitrate (Pu-NO 3 ), uranium-plutonium mixed oxides [(Pu,U)O 2 ], and uranium-plutonium mixed nitrates (Pu-U-NO 3 ). PNC has joined in this program in 1975 for the analysis of samples shown in Table 2. SALE program participants analyze, on a bimonthly basis, materials supplied by the New Brunswick Laboratory (NBL) and report measurement results to NBL for evaluation and inclusion in the bimonthly reports. Present paper describes analysis result and evaluations for these samples which were measured in 1975 -- 1976. (author)

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 enrichment

International Nuclear Information System (INIS)

1991-08-01

This paper reports that in 1990 the Department of Energy began a two-year project to illustrate the technical and economic feasibility of a new uranium enrichment technology-the atomic vapor laser isotope separation (AVLIS) process. GAO believes that completing the AVLIS demonstration project will provide valuable information about the technical viability and cost of building an AVLIS plant and will keep future plant construction options open. However, Congress should be aware that DOE still needs to adequately demonstrate AVLIS with full-scale equipment and develop convincing cost projects. Program activities, such as the plant-licensing process, that must be completed before a plant is built, could take many years. Further, an updated and expanded uranium enrichment analysis will be needed before any decision is made about building an AVLIS plant. GAO, which has long supported legislation that would restructure DOE's uranium enrichment program as a government corporation, encourages DOE's goal of transferring AVLIS to the corporation. This could reduce the government's financial risk and help ensure that the decision to build an AVLIS plant is based on commercial concerns. DOE, however, has no alternative plans should the government corporation not be formed. Further, by curtailing a planned public access program, which would have given private firms an opportunity to learn about the technology during the demonstration project, DOE may limit its ability to transfer AVLIS to the private sector

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

International Nuclear Information System (INIS)

1977-08-01

Thailand is a country with an area of 514?000 square kilometres situated in the centre of continental south-east Asia, The geology of Thailand is very varied with sedimentary formations ranging from Cambrian to Quaternary in age and including sandstones, shales, limestones of many varieties. Among the igneous rocks, granites are very important and rhyolites, tuffs diorites, basalts and ultrabasic rocks also exist. Tin is the most important mineral occurrence. Available information on the geology and mineral resources suggests that the country may contain significant resources of radioactive minerals. Favourable potential host types are; 1) uranium and thorium in monazite in beach sands and tin placer deposits; 2) uranium in sandstones, principally in Jurassic sandstones of the Khorat Plateau; 3) uranium in Tertiary lignite deposits; 4) uranium in veins in granites; 5) uranium related to fluorite deposits; 6) uranium in black shales and phosphates. Uranium mineralization in sedimentary rocks at Phu Wieng was discovered in 1970. The area has been radiometrically grid mapped and limited shallow drilling has shown continuity.of the narrow, carbonaceous, conglomeratic sandstone host bed. No uranium reserves or resources can be stated at the present time, but the favourable geology of the Khorat Plateau, the known uranium occurrence and the very small exploration coverage is possibly indicative of a good future potential. The Speculative Potential is estimated to be between 1000 and 10,000 tonnes uranium. (author)

Position paper Oak Ridge Y-12 Plant storage of uranium in plastics

International Nuclear Information System (INIS)

Duerksen, W.K.

1995-07-01

As a result of the end of the Cold War, the United States nuclear weapon stockpile is being reduced from approximately 20,000 warheads to fewer than 10,000 by the end of the century. The Oak Ridge Y-12 Plant is the Department of Energy (DOE) site charged with the responsibility of providing safe, secure storage for the uranium recovered from these weapons. In addition to weapons material, Y-12 has traditionally processed and stored uranium from nonweapon programs and presumably will continue to do so. The purpose of this document is to evaluate the suitability of plastics for use in the containment of uranium

Application of discriminant analysis and generalized distance measures to uranium exploration

International Nuclear Information System (INIS)

Beauchamp, J.J.; Begovich, C.L.; Kane, V.E.; Wolf, D.A.

1980-01-01

The National Uranium Resource Evaluation (NURE) Program has as its goal the estimation of the nation's uranium resources. It is possile to use discriminant analysis methods on hydrogeochemical data collected in the NURE Program to aid in fomulating geochemical models that can be used to identify the anomalous areas used in resource estimation. Discriminant' analysis methods have been applied to data from the Plainview, Texas Quadrangle which has approximately 850 groundwater samples with more than 40 quantitative measurements per sample. Discriminant analysis topics involving estimation of misclassification probabilities, variable selection, and robust discrimination are applied. A method using generalized distance measures is given which enables the assignment of samples to a background population or a mineralized population whose parameters were estimated from separate studies. Each topic is related to its relevance in identifying areas of possible interest to uranium exploration. However, the methodology presented here is applicable to the identification of regions associated with other types of resources. 8 figures, 3 tables

Evaluation of laser phosphorimetry for the analysis of uranium in biological samples from laboratory animal studies

International Nuclear Information System (INIS)

Gray, D.; Eidsom, A.F.

1985-01-01

Laser phosphorimetry has been used for uranium analyses in a variety of sample matrices, including environmental and human bioassay samples. The Scientrex-UA-3 Uranium Analyzer has been used at ITRI to acquire data on the applicability of laser phosphorimetry to analyses of uranium in the highly concentrated solutions resulting from chemical processing of biological comparisons of results with those obtained from conventional fluorometry. These comparisons have been very favorable for many sample types. Results of these comparisons and an evaluation of the data obtained with the Scintrex unit are presented

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Colombia

International Nuclear Information System (INIS)

1984-01-01

A full report has been released describing the findings of the International Uranium Resources Evaluation Project (IUREP) Orientation Phase Mission to Colombia. The Mission suggests that the speculative uranium resources of the country could be within the very wide range of 20 000 tonnes of 220 000 tonnes of uranium metal. The Mission finds that the area with the highest potential is the Llanos Orientales (Interior Zone), which has the potential of hosting quartz-pebble conglomerate deposits, Proterozoic unconformity-related deposits and sandstone deposits. The Mission recommends that approximately US$80 million should be expended in a phased ten-year exploration programme. It is likely that the majority of the funds will be needed for drilling, followed by ground surveys and airborne radiometry. It is the opinion of the Mission that the considerable funds required for the proposed programme could most suitably be raised by inviting national or foreign commercial organizations to participate under a shared production agreement. (author)

National low-level waste management program radionuclide report series, Volume 15: Uranium-238

International Nuclear Information System (INIS)

Adams, J.P.

1995-09-01

This report, Volume 15 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of uranium-238 ( 238 U). The purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to state representatives and developers of low-level radioactive waste disposal facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the waste disposal facility environment. This report also includes discussions about waste types and forms in which 238 U can be found, and 238 U behavior in the environment and in the human body

Copper Mountain, Wyoming, intermediate-grade uranium resource assessment project. Final report. National Uranium Resource Evaluation

International Nuclear Information System (INIS)

Madson, M.E.; Ludlam, J.R.; Fukui, L.M.

1982-11-01

Intermediate-grade uranium resources were delineated and estimated for Eocene and Precambrian host rock environments in the 39.64 mi 2 Copper Mountain, Wyoming, assessment area. Geologic reconnaissance and geochemical, geophysical, petrologic, borehole, and structural data were interpreted and used to develop a genetic model for uranium mineralization in these environments. Development of a structural scoring system and application of computer graphics in a high-confidence control area established the basis for estimations of uranium resources in the total assessment area. 8 figures, 5 tables

Evaluation of adsorption of uranium from aqueous solution using biochar materials

Energy Technology Data Exchange (ETDEWEB)

Correa, Wagner Clayton; Guilhen, Sabine Neusatz; Ortiz, Nilce; Fungaro, Denise Alves, E-mail: wcorrea@ipen.br, E-mail: snguilhen@ipen.br, E-mail: notriz@ipen.br, E-mail: dfungaro@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

Uranium is present in the environment as a result of leaching from natural deposits and activities associated with nuclear fuel, copper mining, uranium mining, milling industry, etc. For the purpose of protecting ecosystem stability and public health, it is crucial to eliminate uranium from aqueous solutions before they are discharged into the environment. Various technologies have been used for removing U(VI) ions from aqueous systems. Among these methods, adsorption has been applied in wastewater because of simple operation procedure and high removal efficiency. Brazil is the largest producer of charcoal in the world, with nearly half of the woody biomass harvested for energy in Brazil being transformed into charcoal. Biochar exhibits a great potential as an adsorbent because of favorable physical/chemical surface characteristics. The objective of this work was to evaluate the adsorption potential of biochar materials prepared from pyrolysis of Bamboo (CBM), Eucalyptus (CEM) and Macauba (CMA) nuts for the removal of uranium from solutions. Adsorption experiments were carried out by a batch technique. Equilibrium adsorption experiments were performed by shaking a known amount of biochar material with 100 mL of U(VI) solution in Erlenmeyer flasks in a shaker at 120 rpm and room temperature (25 deg C) for 24 h. The adsorbent was separated by centrifugation from the solution. The U(VI) concentration remaining in the supernatant solution was determined using inductively coupled plasma optical emission spectrometry (ICP-OES). The influences of different experimental parameters such as solution pH and bioadsorbent dose on adsorption were investigated. The highest uranium adsorption capacity were obtained at pH 3.0 and 16 g/L biomass dosage for CMA, pH 3.0 and 12 g/L biomass dosage for CBM and pH 2.0 and 10 g/L biomass dosage for CEM. The results demonstrated that the biomass derived char can be used as a low-cost adsorbent for removal of uranium from wastewater. (author)

Evaluation of adsorption of uranium from aqueous solution using biochar materials

International Nuclear Information System (INIS)

Correa, Wagner Clayton; Guilhen, Sabine Neusatz; Ortiz, Nilce; Fungaro, Denise Alves

2015-01-01

Uranium is present in the environment as a result of leaching from natural deposits and activities associated with nuclear fuel, copper mining, uranium mining, milling industry, etc. For the purpose of protecting ecosystem stability and public health, it is crucial to eliminate uranium from aqueous solutions before they are discharged into the environment. Various technologies have been used for removing U(VI) ions from aqueous systems. Among these methods, adsorption has been applied in wastewater because of simple operation procedure and high removal efficiency. Brazil is the largest producer of charcoal in the world, with nearly half of the woody biomass harvested for energy in Brazil being transformed into charcoal. Biochar exhibits a great potential as an adsorbent because of favorable physical/chemical surface characteristics. The objective of this work was to evaluate the adsorption potential of biochar materials prepared from pyrolysis of Bamboo (CBM), Eucalyptus (CEM) and Macauba (CMA) nuts for the removal of uranium from solutions. Adsorption experiments were carried out by a batch technique. Equilibrium adsorption experiments were performed by shaking a known amount of biochar material with 100 mL of U(VI) solution in Erlenmeyer flasks in a shaker at 120 rpm and room temperature (25 deg C) for 24 h. The adsorbent was separated by centrifugation from the solution. The U(VI) concentration remaining in the supernatant solution was determined using inductively coupled plasma optical emission spectrometry (ICP-OES). The influences of different experimental parameters such as solution pH and bioadsorbent dose on adsorption were investigated. The highest uranium adsorption capacity were obtained at pH 3.0 and 16 g/L biomass dosage for CMA, pH 3.0 and 12 g/L biomass dosage for CBM and pH 2.0 and 10 g/L biomass dosage for CEM. The results demonstrated that the biomass derived char can be used as a low-cost adsorbent for removal of uranium from wastewater. (author)

Disposition Options for Uranium-233

International Nuclear Information System (INIS)

Beahm, E.C.; Dole, L.R.; Forsberg, C.W.; Icenhour, A.S.; Storch, S.N.

1999-01-01

The U.S. Department of Energy (DOE) Fissile Materials Disposition Program (MD), in support of the U.S. arms-control and nonproliferation policies, has initiated a program to disposition surplus weapons-usable fissile material by making it inaccessible and unattractive for use in nuclear weapons. Weapons-usable fissile materials include plutonium, high-enriched uranium (HEU), and uranium-233 (sup 233)U. In support of this program, Oak Ridge National Laboratory led DOE's contractor efforts to identify and characterize options for the long-term storage and disposal of excess (sup 233)U. Five storage and 17 disposal options were identified and are described herein

Derivation of uranium residual radioactive material guidelines for the Shpack site

International Nuclear Information System (INIS)

Cheng, J.J.; Yu, C.; Monette, F.; Jones, L.

1991-08-01

Residual radioactive material guidelines for uranium were derived for the Shpack site in Norton, Massachusetts. This site has been identified for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy (DOE). The uranium guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the Shpack site should not exceed a dose of 100 mrem/yr following decontamination. The DOE residual radioactive material guideline computer code, RESRAD, which implements the methodology described in the DOE manual for implementing residual radioactive material guidelines, was used in this evaluation. Three potential scenarios were considered for the site; the scenarios vary with regard to time spent at the site, sources of water used, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded for uranium (including uranium-234, uranium-235, and uranium-238) within 1000 years, provided that the soil concentration of combined uranium (uranium-234 and uranium-238) at the Shpack site does not exceed the following levels: 2500 pCi/g for Scenario A (recreationist: the expected scenario); 1100 pCi/g for Scenario B (industrial worker: a plausible scenario); and 53 pCi/g for Scenario C (resident farmer using a well water as the only water source: a possible but unlikely scenario). The uranium guidelines derived in this report apply to the combined activity concentration of uranium-234 and uranium-238 and were calculated on the basis of a dose of 100 mrem/yr. In setting the actual uranium guidelines for the Shpack site, DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors, such as whether a particular scenario is reasonable and appropriate. 8 refs., 2 figs., 8 tabs

Geological and geochemical aspects of uranium deposits. A selected, annotated bibliography. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

White, M.B.; Garland, P.A. (comps.)

1977-10-01

This bibliography was compiled by selecting 580 references from the Bibliographic Information Data Base of the Department of Energy's (DOE) National Uranium Resource Evaluation (NURE) Program. This data base and five others have been created by the Ecological Sciences Information Center to provide technical computer-retrievable data on various aspects of the nation's uranium resources. All fields of uranium geology are within the defined scope of the project, as are aerial surveying procedures, uranium reserves and resources, and universally applied uranium research. References used by DOE-NURE contractors in completing their aerial reconnaissance survey reports have been included at the request of the Grand Junction Office, DOE. The following indexes are provided to aid the user in locating reference of interest: author, keyword, geographic location, quadrangle name, geoformational index, and taxonomic name.

Evaluation and design of the uranium project “Tigre I – La Terraza”, Sierra Pintada, Mendoza, Argentina

International Nuclear Information System (INIS)

Mansilla, M.; Dieguez, S.

2014-01-01

The Sierra Pintada uranium district in Mendoza Province, Argentina, was discovered by airborne survey. This deposit is associated with a volcanic caldera and occurs in the Lower Permian volcaniclastic sediments of the Cochico Group, in which aeolian and fluvial sandstones, inter-bedded with ignimbrites, were reworked by pyroclastic flows. The origin of the mineralization is interpreted as a product of the leaching of the inter-bedded rhyolitic tuff. The mineralization is lenticular and nearly concordant with the bedding. The deposit has been affected by a complex fault system, which is responsible for mineralization and disposition via spatial displacement. The primary uranium minerals are uraninite, brannerite and coffinite. Uranophane and low liebigite uranium are the products of the oxidative alteration of primary minerals. This study involves the technical and economical evaluation of the open pit uranium mining project Tigre I – La Terraza in Mendoza, Argentina, at prefeasibility level. Its development includes geological modeling through economic evaluation, and the incorporation of different mining-specific software.

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

International Nuclear Information System (INIS)

1977-08-01

Physiographically India has a total area of 3,268,010 km 2 in three distinct regions. 1. The Peninsular shield in the south with an area of 823,310 km 2 . 2. The Himalayan mountain system with an area of 1,797,200 km 2 . 3. The Indo-Gangetic alluvial plain with an area of 647,500 km 2 . The three presently recognised major uranium provinces in India are: 1. The Singhbhum uranium province; 2. The Rajasthan uranium province, 3. The Madhya Pradesh uranium province. The Atomic Minerals Division of the Department of Atomic Energy has carried out a vigorous exploration programme since 1949 but despite their efforts a great deal of ground has still to be explored. At present, structurally controlled deposits account for most of the uranium resources of India. Uranium occurrences and deposits have been outlined in (1) Vein type deposits (the Singhbhum belt), (2) Conglomerate (Karnataka and Udaipur area, Raiasthan), (3) Sandstones (Madhra Pradesh and Swaliks, Himachal Pradesh, (4) Others such as carbonatites, marine phosphates, etc, (Mussorrie - Sahasradhara In Uttar Pradesh and Chatterpur-Saucur in Madhya Pradesh), (5) By-product Uranium in copper tailings and beach sands. India's total resources are listed as 52,538 tonnes uranium (68,300 short tons U 3 O 8 ) with additional resources from monazite of 12700 tonnes uranium. In view of the wide geological favourability, the many types of occurrences already known and the vast areas of unexplored ground it is estimated that the Speculative Potential may be between 150,000 and 250,000 tonnes uranium which is Category 5. (author)

Report of the Uranium Enrichment Technology Evaluation Committee

International Nuclear Information System (INIS)

1977-01-01

The centrifuge method of uranium enrichment is being pushed forward in Japan as a national project. The results of the technology evaluation are described regarding the efforts heretofore, the plan for pilot plant construction, internationally competitive ability, and the schedule after the pilot plant. In conclusion, the basic technology for proceeding to a pilot plant is now mature, and the pilot plant planning by PNC (Power Reactor and Nuclear Fuel Development Corporation) is generally appropriate. The outlook for constructing and internationally competitive practical plant is reasonably good. (Mori, K.)

Santa Cruz 10 x 20 NTMS area, California: data report (abbreviated), National Uranium Resource Evaluation Program, hydrogeochemical and stream sediment reconnaissance

International Nuclear Information System (INIS)

Cook, J.R.

1981-07-01

This abbreviated data report presents results of ground water and stream/surface sediment reconnaissance in the National Topographic Map Series (NTMS) Santa Cruz 1 0 x 2 0 quadrangle. Surface sediment samples were collected at 1270 sites, at a target sampling density of one site per 13 square kilometers (five square miles). Ground water samples were collected at 636 sites. Neutron activation analysis (NAA) results are given for uranium and 16 other elements in sediments, and for uranium and 9 other elements in ground water. Mass spectrometry results are given for helium in ground water. Field measurements and observations are reported for each site. Analytical data and field measurements are presented in tables and maps. Uranium concentrations in the sediments which were above detection limits ranged from 0.10 t 51.2 ppM. The mean of the logarithms of the uranium concentrations was 0.53. A group of high uranium concentrations occurs near the junctions of quadrangles AB, AC, and BB

Uranium tailings reference materials

International Nuclear Information System (INIS)

Smith, C.W.; Steger, H.F.; Bowman, W.S.

1984-01-01

Samples of uranium tailings from Bancroft and Elliot Lake, Ontario, and from Beaverlodge and Rabbit Lake, Saskatchewan, have been prepared as compositional reference materials at the request of the National Uranium Tailings Research Program. The four samples, UTS-1 to UTS-4, were ground to minus 104 μm, each mixed in one lot and bottled in 200-g units for UTS-1 to UTS-3 and in 100-g units for UTS-4. The materials were tested for homogeneity with respect to uranium by neutron activation analysis and to iron by an acid-decomposition atomic absorption procedure. In a free choice analytical program, 18 laboratories contributed results for one or more of total iron, titanium, aluminum, calcium, barium, uranium, thorium, total sulphur, and sulphate for all four samples, and for nickel and arsenic in UTS-4 only. Based on a statistical analysis of the data, recommended values were assigned to all elements/constituents, except for sulphate in UTS-3 and nickel in UTS-4. The radioactivity of thorium-230, radium-226, lead-210, and polonium-210 in UTS-1 to UTS-4 and of thorium-232, radium-228, and thorium-228 in UTS-1 and UTS-2 was determined in a radioanalytical program composed of eight laboratories. Recommended values for the radioactivities and associated parameters were calculated by a statistical treatment of the results

ALPHA SPECTROMETRIC EVALUATION OF SRM-995 AS A POTENTIAL URANIUM/THORIUM DOUBLE TRACER SYSTEM FOR AGE-DATING URANIUM MATERIALS

Energy Technology Data Exchange (ETDEWEB)

Beals, D.

2011-12-06

Uranium-233 (t{sub 1/2} {approx} 1.59E5 years) is an artificial, fissile isotope of uranium that has significant importance in nuclear forensics. The isotope provides a unique signature in determining the origin and provenance of uranium-bearing materials and is valuable as a mass spectrometric tracer. Alpha spectrometry was employed in the critical evaluation of a {sup 233}U standard reference material (SRM-995) as a dual tracer system based on the in-growth of {sup 229}Th (t{sub 1/2} {approx} 7.34E3 years) for {approx}35 years following radiochemical purification. Preliminary investigations focused on the isotopic analysis of standards and unmodified fractions of SRM-995; all samples were separated and purified using a multi-column anion-exchange scheme. The {sup 229}Th/{sup 233}U atom ratio for SRM-995 was found to be 1.598E-4 ({+-} 4.50%) using recovery-corrected radiochemical methods. Using the Bateman equations and relevant half-lives, this ratio reflects a material that was purified {approx} 36.8 years prior to this analysis. The calculated age is discussed in contrast with both the date of certification and the recorded date of last purification.

Chattanooga shale: uranium recovery by in situ processing

International Nuclear Information System (INIS)

Jackson, D.D.

1977-01-01

The increasing demand for uranium as reactor fuel requires the addition of sizable new domestic reserves. One of the largest potential sources of low-grade uranium ore is the Chattanooga shale--a formation in Tennessee and neighboring states that has not been mined conventionally because it is expensive and environmentally disadvantageous to do so. An in situ process, on the other hand, might be used to extract uranium from this formation without the attendant problems of conventional mining. We have suggested developing such a process, in which fracturing, retorting, and pressure leaching might be used to extract the uranium. The potential advantages of such a process are that capital investment would be reduced, handling and disposing of the ore would be avoided, and leaching reagents would be self-generated from air and water. If successful, the cost reductions from these factors could make the uranium produced competitive with that from other sources, and substantially increase domestic reserves. A technical program to evaluate the processing problems has been outlined and a conceptual model of the extraction process has been developed. Preliminary cost estimates have been made, although it is recognized that their validity depends on how successfully the various processing steps are carried out. In view of the preliminary nature of this survey (and our growing need for uranium), we have urged a more detailed study on the feasibility of in situ methods for extracting uranium from the Chattanooga shale

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Turkey

International Nuclear Information System (INIS)

1985-01-01

A report has recently been published which describes the findings of the International Uranium Resources Evaluation Project (IUREP) mission to Turkey. The IUREP Orientation Phase mission to Turkey estimates that the Speculative Resources of that country fall within the range of 21 000 to 55 000 tonnes of uranium. This potential is expected to lie in areas of Neogene and possibly other Tertiary sediments, in particular in the areas of the Menderes Massif and Central Anatolia. The mission describes a proposed exploration programme with expenditures over a five year period of between $80 million and $110 million, with nearly half of the amount being spent on drilling. (author)

Economic evaluation of in situ extraction for copper, gold, and uranium

International Nuclear Information System (INIS)

Lewis, F.M.; Chase, C.K.; Bhappu, R.B.

1976-01-01

In situ extraction for copper, gold, and uranium, generally involves several common alternative processes and techniques. These include dump leaching, heap leaching, leaching of fractured ore in-place or bore hole mining and unit operations such as cementation, solvent extraction, ion-exchange, or carbon-in-pulp. Since the metallurgical effectiveness and economics of such processes and unit operations are well established, it would be possible to select the optimum alternative for extracting either copper, gold, or uranium from their ores using in situ extraction technology. Efforts made to provide metallurgical evaluation as well as capital and operating costs for the various processes and unit operations are reported. These costs are used in preparing feasibility studies for in situ extraction of these metals

Hydrogeochemical and stream sediment reconnaissance basic data for Emory Peak NTMS Quadrangle, Texas. Uranium Resource Evaluation Project

International Nuclear Information System (INIS)

1978-01-01

Results of a reconnaissance geochemical survey of the Emory Peak Quadrangle, Texas, are reported. Field and laboratory data are presented for 193 groundwater samples and 491 stream sediment samples. Statistical and areal distributions of uranium and other possible uranium-related variables are displayed. A generalized geologic map of the survey area is provided, and the pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed. In groundwater, uranium concentrations above the 85th percentile outline an area in the northwest portion of the quadrangle which is dominated by tertiary tuffaceous ash beds which disconformably overlie cretaceous units. The relationship between uranium and related variables indicates this area appears to have the best potential for uranium mineralization within the quadrangle. Stream sediment data indicate four areas that appear to be favorable for potential uranium mineralization: the Upper Green Valley-Paradise Valley region, the Terlingua Creek-Solitario region, an area in the vicinity of Big Bend National Park, and an area east of long. 102 0 15' W. In the first three of the preceding areas, soluble uranium is associated with tertiary igneous rocks. In the fourth area, soluble uranium is present in carbonate-dominant cretaceous strata

SRTC criticality technical review: Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility

International Nuclear Information System (INIS)

Rathbun, R.

1993-01-01

Separate review of NMP-NCS-930058, open-quotes Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility (U), August 17, 1993,close quotes was requested of SRTC Applied Physics Group. The NCSE is a criticality assessment to determine waste container uranium limits in the Uranium Solidification Facility's Waste Handling Facility. The NCSE under review concludes that the NDA room remains in a critically safe configuration for all normal and single credible abnormal conditions. The ability to make this conclusion is highly dependent on array limitation and inclusion of physical barriers between 2x2x1 arrays of boxes containing materials contaminated with uranium. After a thorough review of the NCSE and independent calculations, this reviewer agrees with that conclusion

Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved; Cycles de combustibles. Production d'uranium, programme de centrales electriques et effort financier correspondant

Energy Technology Data Exchange (ETDEWEB)

Andriot, J.; Gaussens, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author)Fren. [French] L'etude presentee comporte l'examen d'un certain nombre d'hypotheses de programmes de centrales nucleaires de types differents. Ces programmes correspondent a l'utilisation de tonnages d'uranium et de thorium de l'ordre de grandeur de ceux qui seront probablement produits par la France dans les quinze prochaines annees. Comme il est possible de batir un programme de centrales nucleaires, comportant a la fois plusieurs filieres suivant des variantes en nombre infini, on s'est contente d'examiner successivement les resultats ous si on utilisait exclusivement l

International Uranium Resources Evaluation Project (IUREP) orientation phase mission report: Colombia. February - March 1980

International Nuclear Information System (INIS)

Cameron, J.; Meunier, A.R.; Tauchid, M.

1980-01-01

The basic objective of IUREP is to 'review the present body of knowledge pertinent to the existence of uranium resources, to review and evaluate the potential for discovery of additional uranium resources, and to suggest new exploration efforts which might be carried out in promising new areas in collaboration with the countries concerned'. Following the initial bibliographic study, which formed Phase I of IUREP, it was envisaged that a further assessment in co-operation with the country in question would lead to a better delineation of areas of high potential and a more reliable estimate as to the degree of favourability for the discovery of additional uranium resources. It was planned that such work would be accomplished through field missions to the country and that these field missions and the resulting report would constitute the IUREP Orientation Phase. The purpose of the Orientation Mission to Colombia was (i) to develop a better understanding of the uranium potential of the country, (ii) to delineate areas favourable for the discovery of speculative uranium resources, (iii) to make recommendations, as appropriate, on the best methods for evaluating the favourable areas, operating procedures and estimated possible costs, (iv) to develop the logistical data required to carry out any possible further work, and (v) to compile a report that would be immediately available to the Colombian authorities. Uranium exploration in Colombia is of very recent date, with the majority of activities getting under way only after 1970. In spite of the limited work that has been done, however, over 1300 radioactive anomalies have been recorded. The total number of uranium mineral occurrences resulting from follow-up work is still very small, and some are unusual in world terms. Topographic and geographic conditions in Colombia make geological and exploration work very difficult and costly, especially in the Cordilleras and the Interior Zone (Llanos Orientales). There are, at

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

International Nuclear Information System (INIS)

1977-12-01

Uranium occurrences and resources - To date the uranium identified in Belgium is limited to a number of occurrences and none of these have as yet proved significant from a reserve or resource viewpoint. The main uranium occurrences ares (1) In the Upper Cambrian graphite schists corresponding to the culm of Sweden small zones are found (30 - 50 cm thick) with an average of 20 ppm uranium. (2) Near Vise at the base of the Carboniferous the Visean formation is discordantly superimposed on the Permian (Frasnian) and overlain by shales and phyllites. Solution pockets at the boundary contain phosphatic lenses that contain uranium values of up to 200 ppm. Autunite and Torbernite are the main uranium minerals associated with a number of complex phosphatic minerals. Within the Chalk (Maestrichtien) of the Mons basin, that is mainly in the Ciply - St. Symphorien and Baudow district. Here is found enrichment of uranium up to 140 ppm over large areas related to phosphatic chalk. The thickness of the zone varies from a few to 20 metres. However, as the P 2 O 5 content is not high enough for the deposits to be exploited at present for phosphate there is little possibility of the uranium being concentrated at high enough levels to be exploited for itself alone. (4) Near to Vielsalm (in the Stavelot Massif) are some thin quartz veins containing small amounts of copper and uranium minerals (Torbornite). Values of up to 70 ppm are recorded. (5) A number of low uranium values are recorded associated with phosphatic nodules and zones in the Lower Pleistocene and Tertiary

Seasonal effects on ground water chemistry of the Ouachita Mountains. National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

Steele, K.F.; Fay, W.M.; Cavendor, P.N.

1982-08-01

Samples from 13 ground water sites (10 springs and 3 wells) in the Ouachita Mountains were collected nine times during a 16-month period. Daily sampling of six sites was carried out over an 11-day period, with rain during this period. Finally, hourly sampling was conducted at a single site over a 7-hour period. The samples were analyzed for pH, conductivity, temperature, total alkalinity, nitrate, ammonia, sulfate, phosphate, chloride, silica, Na, K, Li, Ca, Mg, Sr, Ba, Fe, Mn, Zn, Cu, Co, Ni, Pb, Hg, Br, F, V, Al, Dy, and U. Despite the dry season during late summer, and wet seasons during late spring and late fall in the Ouachita Mountain region, there was no significant change in the ground water chemistry with season. Likewise, there was no significant change due to rain storm events (daily sampling) or hourly sampling. The report is issued in draft form, without detailed technical and copy editing. This was done to make the report available to the public before the end of the National Uranium Resource Evaluation. 9 figures, 19 tables

Nuclear criticality safety assessment of the Consolidated Edison Uranium-Solidification Program Facility

International Nuclear Information System (INIS)

Thomas, J.T.

1984-01-01

A nuclear criticality assessment of the Consolidated Edison Uranium-Solidification Program facility confirms that all operations involved in the process may be conducted with an acceptable margin of subcriticality. Normal operation presents no concern since subcriticality is maintained by design. Several recommendations are presented to prevent, or mitigate the consequences of, any abnormal events that might occur in the various portions of the process. These measures would also serve to reduce to a minimum the administrative controls required to prevent criticality

Reconnaissance geochemical survey for uranium and related industrial minerals in Cebu Island

International Nuclear Information System (INIS)

Reyes, R.Y.; Ramos, A.F.; Magsambol, W.N.; Hernandez, E.

1989-03-01

Consistent with the program of evaluating the nuclear mineral resource potential and related industrial minerals of the Philippines, a reconnaissance geochemical survey was conducted in Cebu with considerable success. The total area covered by the survey was about 5,088 sq. kms. The survey consisted of systematic collection of 857 geochemical stream and water and heavy mineral samples, and measurement of radioactivity in over 352 stations. The average sampling density was about one set of samples per 15 to 30 sq. kms. All solid samples were analyzed for U, Cu, Pb, Zn, Mn, Ag, Co and Ni. Uranium, radon and conductivity were measured on most water samples collected. A total of 4,518 elemental determinations were involved. All field and analytical data were treated by statistics, and the computed parameters data were correlated with the geology of the area to establish anomalous zones. Four areas were delineated for possible uranium mineralization. Of the areas, the Mandaue river area is the most interesting for uranium. The contact zone between the diorite and the sedimentary rocks in this area appears to be a favorable geological environment for uranium mineralization. The other anomalous uranium values were found to be related with the guano and phosphate deposits. Uranium was also shown to be independent of the other seven elements in the geologic environment of Cebu. No definite elemental association could be established at present. This study also marks the thorough utilization of Q'GAS, Cadplot and Autocad, all microcomputer-based programs/systems, in the evaluation and interpretation of exploration-oriented geochemical and geological data, and with more significance in the sense that computer generated quality geochemical maps were produced, a first in the country. (Author). Appendices (23); 23 figs; 13 refs.; 4 tabs

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

Discharge Burnup Evaluation of Natural Uranium Loaded CANFLEX-43 Fuel Bundle

International Nuclear Information System (INIS)

Roh, Gyu Hong; Kim, Yong Hee; Kim, Won Young; Park, Joo Hwan

2009-11-01

Using WIMS-AECL code, which is 2-dimensional lattice core used in CANDU physics calculation, the discharge burnup of the natural uranium loaded CANFLEX-43 fuel bundle was evaluated by comparing the discharge burnup of standard 37 element fuel bundle. When the discharge burnup of the standard 37 element fuel is 7,200 MWd/MTU, that of the CANFLEX 43 fuel bundle was evaluated as 7,077 MWd/MTU, by applying the same lattice conditions for both fuel bundles

Ailing uranium millworkers seek recognition, aid

International Nuclear Information System (INIS)

Ambler, M.

1980-01-01

Uranium millworkers who helped produce uranium for the U.S. nuclear defense program in the 1950's and 1960's are suing the federal government and uranium companies for compensation for illnesses that they believe are job-related. Symptoms of these illnesses include frequent blackouts, chronic bronchitis, asthma, constant fatigue, and susceptibility to colds. Research is being conducted to determine whether the millworkers' symptoms are due to excessive radiation exposure. Studies to date indicated that during the 1950's and early 1960's, radiation protection procedures at uranium milling facilities were extremely deficient

Natural uranium toxicology - evaluation of internal contamination in man; Toxicologie de l'uranium naturel - essai d'evaluation de la contamination interne chez l'homme

Energy Technology Data Exchange (ETDEWEB)

Chalabreysse, J. [Commissariat a l' Energie Atomique, Pierrelatte (France). Centre d' Etudes Nucleaires

1968-07-01

After reminding the physical and chemical properties of natural uranium which might affect its toxicology, a comprehensive investigation upon natural uranium metabolism and toxicity and after applying occupational exposure standards to this particular poison, it has been determined, from accident reports and human experience reported in the related literature, a series of formulae obtained by theoretical mathematical development giving principles for internal contamination monitoring and disclosure by determining uranium in the urine of occupationally exposed individuals. An assay is performed to determine individual internal contamination according to the various contamination cases. The outlined purposes, mainly practical, required some options and extrapolations. The proposed formula allows a preliminary approach and also to determine shortly a contamination extent or to discuss the systematical urinalysis results as compared with individual radio-toxicology monitoring professional standards. (author) [French] Apres le rappel des caracteristiques physiques et des proprietes chimiques de l'uranium naturel pouvant avoir une influence sur sa toxicologie, l'etude detaillee de son metabolisme et de sa toxicite, puis l'application des normes professionnelles d'exposition au cas particulier de ce toxique, il est etabli, a partir des comptes rendus d'accidents et de l'experimentation humaine rapportes dans la litterature, une serie de formules obtenues par developpement mathematique theorique qui posent les principes de la surveillance et de la mise en evidence de la contamination interne par la recherche et le dosage de l'uranium dans les urines d'individus professionnellement exposes. Un essai d'evaluation de la contamination interne individuelle suivant les differents cas de contamination est effectue. Le formulaire propose permet de faire une premiere approximation et d'apprecier rapidement l'importance d

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

International Nuclear Information System (INIS)

1977-11-01

The geology of Oman is unlikely to lie favourable for uranium occurrence being mainly of marine sedimentary origin. No exploration for uranium has been reported or is planned. The Speculative Potential is placed in the category of less than 1000 tonnes uranium. (author)

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

International Nuclear Information System (INIS)

Batbold, T.

2001-01-01

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

Validation of the WATEQ4 geochemical model for uranium

International Nuclear Information System (INIS)

Krupka, K.M.; Jenne, E.A.; Deutsch, W.J.

1983-09-01

As part of the Geochemical Modeling and Nuclide/Rock/Groundwater Interactions Studies Program, a study was conducted to partially validate the WATEQ4 aqueous speciation-solubility geochemical model for uranium. The solubility controls determined with the WATEQ4 geochemical model were in excellent agreement with those laboratory studies in which the solids schoepite [UO 2 (OH) 2 . H 2 O], UO 2 (OH) 2 , and rutherfordine ((UO 2 CO 3 ) were identified as actual solubility controls for uranium. The results of modeling solution analyses from laboratory studies of uranyl phosphate solids, however, identified possible errors in the characterization of solids in the original solubility experiments. As part of this study, significant deficiencies in the WATEQ4 thermodynamic data base for uranium solutes and solids were corrected. Revisions included recalculation of selected uranium reactions. Additionally, thermodynamic data for the hydroxyl complexes of U(VI), including anionic (VI) species, were evaluated (to the extent permitted by the available data). Vanadium reactions were also added to the thermodynamic data base because uranium-vanadium solids can exist in natural ground-water systems. This study is only a partial validation of the WATEQ4 geochemical model because the available laboratory solubility studies do not cover the range of solid phases, alkaline pH values, and concentrations of inorganic complexing ligands needed to evaluate the potential solubility of uranium in ground waters associated with various proposed nuclear waste repositories. Further validation of this or other geochemical models for uranium will require careful determinations of uraninite solubility over the pH range of 7 to 10 under highly reducing conditions and of uranyl hydroxide and phosphate solubilities over the pH range of 7 to 10 under oxygenated conditions

Feasibility studies on electrochemical separation and recovery of uranium by using domestic low grade uranium resources

International Nuclear Information System (INIS)

Oh, Won Zin; Jung, Chong Hun; Lee, Kune Woo; Won, Hui Jun; Choi, Wang Kyu; Kim, Gye Nam; Lee, Yu Ri; Lee, Joong Moung

2005-12-01

The up-to-date electrochemical uranium separation technology has been developed for uranium sludge waste treatment funded by a long term national nuclear technology development program. The objective of the studies is to examine applicability of the uranium separation technology to making use of the low grade uranium resources in the country. State of the arts of uranium separation and recovery from the low grade national uranium resources. - The amount of the high grade uranium resources(0.1 % U 3 O 8 contents) in the world is 1,750,000MTU and that of the low grade uranium resources(0.04 % U 3 O 8 contents) in the country is 340,000MTU. - The world uranium price will be increase to more than 30$/l0b in 10 years, so that the low grade uranium in the country become worth while to recover. - The conventional uranium recovery technologies are based on both acidic - The ACF electrochemical uranium separation technology is the state of the art technology in the world and the adsorption capability of 690 mgU/g is several ten times higher than that of a conventional zeolite and the uranium stripping efficiency by desorption is more than 99%. So, this technology is expected to replace the existing solvent extraction technology. Feasibility of the ACF electrochemical uranium separation technology as an uranium recovery method. Lab scale demonstration of uranium separation and recovery technologies have been carried out by using an ACF electrochemical method

NDA technology for uranium resource evaluation. Progress report July 1-December 31, 1979

International Nuclear Information System (INIS)

Evans, M.L.

1980-08-01

This report describes work performed during the time period from July 1, 1979 to December 31, 1979, on the contract for Nondestructive Nuclear Analysis (NDA) Technology for Uranium Resource Evaluation in Group Q-1. Calculational effort was focused on improving the accuracy with which detector response function maps can be generated for subsequent enfolding with ONETRAN angular flux data. Experimental effort was highlighted by a field test of the prototype photoneutron logging probe at the Grand Junction DOE calibration facility. The probe demonstrated adequate durability in the field and sufficient sensitivity to uranium to function at competitive logging speeds

Uranium - the nuclear fuel

International Nuclear Information System (INIS)

Smith, E.E.N.

1976-01-01

A brief history is presented of Canadian uranium exploration, production, and sales. Statistics show that Canada is a good customer for its own uranium due to a rapidly expanding nuclear power program. Due to an average 10 year lag between commencement of exploration and production, and with current producers sold out through 1985, it is imperative that exploration efforts be increased. (E.C.B.)

Uranium isotopic signatures measured in samples of dirt collected at two former uranium facilities

International Nuclear Information System (INIS)

Meyers, L.A.; Stalcup, A.M.; LaMont, S.P.; Spitz, H.B.

2014-01-01

Nuclear forensics is a multidisciplinary science that uses a variety of analytical methods and tools to explore the physical, chemical, and isotopic characteristics of nuclear and radiological materials. These characteristics, when evaluated alone or in combination, become signatures that may reveal how and when the material was fabricated. The signatures contained in samples of dirt collected at two different uranium metal processing facilities in the United States were evaluated to determine uranium isotopic composition and compare results with processes that were conducted at these sites. One site refined uranium and fabricated uranium metal ingots for fuel and targets and the other site rolled hot forged uranium and other metals into dimensional rods. Unique signatures were found that are consistent with the activities and processes conducted at each facility and establish confidence in using these characteristics to reveal the provenance of other materials that exhibit similar signatures. (author)

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

International Uranium Resources Evaluation Project (IUREP) orientation phase mission summary report: Burundi

International Nuclear Information System (INIS)

1985-01-01

A report has recently been published which describes the findings of the International Uranium Resources Evaluation Project (IUREP) Mission to Burundi. The IUREP Orientation Phase Mission to Burundi estimates that the Speculative Resources of that country fall within the range of 300 to more than 4 100 tonnes of uranium. The potential is rather evenly distributed throughout the Proterozoic of Burundi in various geological environments (unconformity, hydrothermal, fault controlled, etc.). The mission recommends that over a period of five years U.S. $ 3 to 4.5 million be spent on exploration in Burundi, with even spending on the various exploration techniques as e.g. prospecting, drilling trenching, geophysical surveys, analyses, etc. (author)

Detection and evaluation of uranium in different minerals by gamma spectrometry and laser induced breakdown spectroscopy

International Nuclear Information System (INIS)

Sergani, F.M.; Khedr, M.A.; Harith, M.A.; El Mongy, S.A.

2004-01-01

Analysis, detection and evaluation of source nuclear materials (e.g. uranium) in different minerals by sensitive techniques are a vital objective for uranium exploration, nuclear materials extraction, processing and verification. In this work, uranium in different geological formations was determined using gamma spectrometry and laser induced breakdown spectroscopy (LIBS). The investigated samples were collected from different regions distributed all over Egypt. The samples were then prepared for non-destructive analysis. A hyper pure germanium detector was used to measure the emitted gamma rays of uranium and its daughters in the samples. The concentrations of uranium in ppm (μg/g) in the investigated samples are given and discussed in this work. The highest uranium concentration (4354.9 ppm) was found in uranophane samples of Gattar rocks. In Laser induced breakdown spectroscopy (LIBS) technique, plasma was formed by irradiating the rock surface with focused Q-switched Nd:Yag laser pulses of 7 ns pulse duration at the fundamental wavelength (1064 nm). Atoms and ions originating from the rock surface are excited and ionized in the laser produced hot plasma (∝10 000 K). The plasma emission spectral line is characteristic of the elements present in the plasma and allows identification of the uranium in the uranophane mineral. The strong atomic line at 424.2 nm is used for the qualitative identification of uranium. It can be mentioned that the elevated levels of uranium in some of the investigated uranophane samples are of great economic feasibility to be extracted. (orig.)

Evaluation of parameters associated with monitoring in vivo of uranium isotopes in the lungs

International Nuclear Information System (INIS)

Juppa, Silvia P.; Lucena, Eder A.; Dantas, Bernardo M.; Dantas, Ana Leticia A.

2013-01-01

The objective of this study is to evaluate the parameters associated with the technique of monitoring individuals exposed to uranium isotopes, aiming to optimize the technique and reduced uncertainties associated

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

National Uranium Resource Evaluation Program. Hydrogeochemical and stream sediment pilot survey of Llano area, Texas

International Nuclear Information System (INIS)

Nichols, C.E.; Kane, V.E.; Minkin, S.C.; Cagle, G.W.

1976-01-01

A pilot geochemical survey of the Llano, Texas, area was conducted during February and March 1976. The purpose of this work was to prepare for a subsequent reconnaissance geochemical survey of uranium in Central Texas. Stream sediment, stream water, well water, and plant ash from five geologic areas were analyzed in the laboratory for approximately 25 parameters. Examples of anomalous values in stream sediment and stream water indicate the usefulness of both sample types in identifying anomalies at a regional reconnaissance-scale station spacing of approximately 5 km (3 mi). Groundwater samples, which generally best indicate the geochemistry of formations at depth in a survey of this type, represent another important tool in detecting uranium mineralization. Anomalies in San Saba County are associated with the Marble Falls-Smithwich Formations and the Strawn Series (Pennsylvanian), the Houy Formation (Devonian and lower Mississippian), and the Hickory Sandstone Member of the Riley Formation (Cambrian). In Burnet County anomalous values are due to the influence of the Valley Spring Formation (Precambrian); and in Blanco County anomalies are found associated with the Riley Formation

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

Sensitivity evaluation of the green alga Chlamydomonas reinhardtii to uranium by pulse amplitude modulated (PAM) fluorometry

International Nuclear Information System (INIS)

Herlory, Olivier; Bonzom, Jean-Marc; Gilbin, Rodolphe

2013-01-01

fluorescence induction kinetics are valuable indicators for evaluating the impact of uranium on PSII in green algae. PAM fluorometry provided a rapid and reasonably sensitive method for assessing stress response to uranium in microalgae

Computer-modeling codes to improve exploration nuclear-logging methods. National Uranium Resource Evaluation

International Nuclear Information System (INIS)

Wilson, R.D.; Price, R.K.; Kosanke, K.L.

1983-03-01

As part of the Department of Energy's National Uranium Resource Evaluation (NURE) project's Technology Development effort, a number of computer codes and accompanying data bases were assembled for use in modeling responses of nuclear borehole logging Sondes. The logging methods include fission neutron, active and passive gamma-ray, and gamma-gamma. These CDC-compatible computer codes and data bases are available on magnetic tape from the DOE Technical Library at its Grand Junction Area Office. Some of the computer codes are standard radiation-transport programs that have been available to the radiation shielding community for several years. Other codes were specifically written to model the response of borehole radiation detectors or are specialized borehole modeling versions of existing Monte Carlo transport programs. Results from several radiation modeling studies are available as two large data bases (neutron and gamma-ray). These data bases are accompanied by appropriate processing programs that permit the user to model a wide range of borehole and formation-parameter combinations for fission-neutron, neutron-, activation and gamma-gamma logs. The first part of this report consists of a brief abstract for each code or data base. The abstract gives the code name and title, short description, auxiliary requirements, typical running time (CDC 6600), and a list of references. The next section gives format specifications and/or directory for the tapes. The final section of the report presents listings for programs used to convert data bases between machine floating-point and EBCDIC

Standard guide for establishing a quality assurance program for uranium conversion facilities

CERN Document Server

American Society for Testing and Materials. Philadelphia

2004-01-01

1.1 This guide provides guidance and recommended practices for establishing a comprehensive quality assurance program for uranium conversion facilities. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate health and safety practices and determine the applicability of regulatory limitations prior to use. 1.3 The basic elements of a quality assurance program appear in the following order: FUNCTION SECTION Organization 5 Quality Assurance Program 6 Design Control 7 Instructions, Procedures & Drawings 8 Document Control 9 Procurement 10 Identification and Traceability 11 Processes 12 Inspection 13 Control of Measuring and Test Equipment 14 Handling, Storage and Shipping 15 Inspection, Test and Operating Status 16 Control of Nonconforming Items 17 Corrective Actions 18 Quality Assurance Records 19 Audits 20 TABLE 1 NQA-1 Basic Requirements Relat...

Application of NURE data to the study of crystalline rocks in the Wyoming uranium province

International Nuclear Information System (INIS)

Rush, S.M.; Anderson, J.R.; Bennett, J.E.

1983-03-01

The Wyoming uranium province study is a part of the National Uranium Resource Evaluation (NURE) program conducted by Bendix Field Engineering Corporation for the US Department of Energy. The ultimate objective of the entire project is the integration of NURE and other data sources to develop a model for a uranium province centered in Wyoming. This paper presents results of the first phase of the Wyoming uranium province study, which comprises characterization of the crystalline rocks of the study area using NURE hydrogeochemical and stream-sediment data, aerial radiometric and magnetic data, and new data generated for zircons from intrusive rocks in the study area. The results of this study indicate that the stream-sediment, aerial radiometric, aerial magnetic, and zircon data are useful in characterization of the crystalline rocks of the uranium province. The methods used in this project can be applied in two ways toward the recognition of a uranium province: (1) to locate major uranium deposits and occurrences, and (2) to generally identify different crystalline rock types, particularly those that could represent significant uranium source rocks. 14 figures, 8 tables

Uranium isotopic composition and uranium concentration in special reference material SRM A (uranium in KCl/LiCl salt matrix)

International Nuclear Information System (INIS)

Graczyk, D.G.; Essling, A.M.; Sabau, C.S.; Smith, F.P.; Bowers, D.L.; Ackerman, J.P.

1997-07-01

To help assure that analysis data of known quality will be produced in support of demonstration programs at the Fuel Conditioning Facility at Argonne National Laboratory-West (Idaho Falls, ID), a special reference material has been prepared and characterized. Designated SRM A, the material consists of individual units of LiCl/KCl eutectic salt containing a nominal concentration of 2.5 wt. % enriched uranium. Analyses were performed at Argonne National Laboratory-East (Argonne, IL) to determine the uniformity of the material and to establish reference values for the uranium concentration and uranium isotopic composition. Ten units from a batch of approximately 190 units were analyzed by the mass spectrometric isotope dilution technique to determine their uranium concentration. These measurements provided a mean value of 2.5058 ± 0.0052 wt. % U, where the uncertainty includes estimated limits to both random and systematic errors that might have affected the measurements. Evidence was found of a small, apparently random, non-uniformity in uranium content of the individual SRM A units, which exhibits a standard deviation of 0.078% of the mean uranium concentration. Isotopic analysis of the uranium from three units, by means of thermal ionization mass spectrometry with a special, internal-standard procedure, indicated that the uranium isotopy is uniform among the pellets with a composition corresponding to 0.1115 ± 0.0006 wt. % 234 U, 19.8336 ± 0.0059 wt. % 235 U, 0.1337 ± 0.0006 wt. % 236 U, and 79.9171 ± 0.0057 wt. % 238 U

Review of the NURE Assessment of the U.S. Gulf Coast Uranium Province

International Nuclear Information System (INIS)

Hall, Susan M.

2013-01-01

Historic exploration and development were used to evaluate the reliability of domestic uranium reserves and potential resources estimated by the U.S. Department of Energy national uranium resource evaluation (NURE) program in the U.S. Gulf Coast Uranium Province. NURE estimated 87 million pounds of reserves in the $30/lb U 3 O 8 cost category in the Coast Plain uranium resource region, most in the Gulf Coast Uranium Province. Since NURE, 40 million pounds of reserves have been mined, and 38 million pounds are estimated to remain in place as of 2012, accounting for all but 9 million pounds of U 3 O 8 in the reserve or production categories in the NURE estimate. Considering the complexities and uncertainties of the analysis, this study indicates that the NURE reserve estimates for the province were accurate. An unconditional potential resource of 1.4 billion pounds of U 3 O 8 , 600 million pounds of U 3 O 8 in the forward cost category of $30/lb U 3 O 8 (1980 prices), was estimated in 106 favorable areas by the NURE program in the province. Removing potential resources from the non-productive Houston embayment, and those reserves estimated below historic and current mining depths reduces the unconditional potential resource 33% to about 930 million pounds of U 3 O 8 , and that in the $30/lb cost category 34% to 399 million pounds of U 3 O 8 . Based on production records and reserve estimates tabulated for the region, most of the production since 1980 is likely from the reserves identified by NURE. The potential resource predicted by NURE has not been developed, likely due to a variety of factors related to the low uranium prices that have prevailed since 1980

Research and information needs for management of uranium development. Interim report Dec 82-Nov 83

International Nuclear Information System (INIS)

1983-11-01

The report reviews the research needed to support the regulatory and managerial role of BLM and other entities involved in uranium development of public Indian lands in the western United States, advising them to: (1) Identify and evaluate potential domestic and international research and development projects, (2) Assemble and distribute key information on new methodology for use by government managers and the uranium industry, and (3) Initiate a long-range program to evaluate existing uranium processing methods and systems, including mining, milling, and waste management, with the intent of developing more effective approaches. With uranium mining and milling on the wane, and with the increased emphasis in health and safety, there are urgent needs for innovative processes, greater economics in operations, and improved management and control criteria. There cannot be more effective handling of disposal of mine wastes and mill tailings, cleanup and control of air- and waterborne particulates, better reclamation procedures, or prevention of environmental degradation, without maintenance of a strong U.S. mining industry

Uranium soils integrated demonstration, 1993 status

International Nuclear Information System (INIS)

Nuhfer, K.

1994-01-01

The Fernald Environmental Management Project (FEMP), operated by the Fernald Environmental Restoration Management Corporation (FERMCO) for the DOE, was selected as the host site for the Uranium Soils Integrated Demonstration. The Uranium Soils ID was established to develop and demonstrate innovative remediation methods which address the cradle to grave elements involved in the remediation of soils contaminated with radionuclides, principally uranium. The participants in the ID are from FERMCO as well as over 15 other organizations from DOE, private industry and universities. Some of the organizations are technology providers while others are members of the technical support groups which were formed to provide technical reviews, recommendations and labor. The following six Technical Support Groups (TSGs) were formed to focus on the objective of the ID: Characterization, Excavation, Decontamination, Waste Treatment/Disposal, Regulatory, and Performance Assessment. This paper will discuss the technical achievements made to date in the program as well as the future program plans. The focus will be on the realtime analysis devices being developed and demonstrated, the approach used to characterize the physical/chemical properties of the uranium waste form in the soil and lab scale studies on methods to remove the uranium from the soil

Sensitivity evaluation of the green alga Chlamydomonas reinhardtii to uranium by pulse amplitude modulated (PAM) fluorometry.

Science.gov (United States)

Herlory, Olivier; Bonzom, Jean-Marc; Gilbin, Rodolphe

2013-09-15

Although ecotoxicological studies tend to address the toxicity thresholds of uranium in freshwaters, there is a lack of information on the effects of the metal on physiological processes, particularly in aquatic plants. Knowing that uranium alters photosynthesis via impairment of the water photo-oxidation process, we determined whether pulse amplitude modulated (PAM) fluorometry was a relevant tool for assessing the impact of uranium on the green alga Chlamydomonas reinhardtii and investigated how and to what extent uranium hampered photosynthetic performance. Photosynthetic activity and quenching were assessed from fluorescence induction curves generated by PAM fluorometry, after 1 and 5h of uranium exposure in controlled conditions. The oxygen-evolving complex (OEC) of PSII was identified as the primary action site of uranium, through alteration of the water photo-oxidation process as revealed by F0/Fv. Limiting re-oxidation of the plastoquinone pool, uranium impaired the electron flux between the photosystems until almost complete inhibition of the PSII quantum efficiency ( [Formula: see text] , EC50=303 ± 64 μg UL(-1) after 5h of exposure) was observed. Non-photochemical quenching (qN) was identified as the most sensitive fluorescence parameter (EC50=142 ± 98 μg UL(-1) after 5h of exposure), indicating that light energy not used in photochemistry was dissipated in non-radiative processes. It was shown that parameters which stemmed from fluorescence induction kinetics are valuable indicators for evaluating the impact of uranium on PSII in green algae. PAM fluorometry provided a rapid and reasonably sensitive method for assessing stress response to uranium in microalgae. Copyright © 2013 Elsevier B.V. All rights reserved.

The use of medium enriched uranium fuel for research reactors

International Nuclear Information System (INIS)

1979-01-01

The evaluation described in the present paper concerns the use of medium enriched uranium fuel for our research reactors. The underlying assumptions set up for the evaluation are as follows: (1) At first, the use of alternative fuel should not affect, even to a small extent, research and development programs in nuclear energy utilization, which were described in the previous paper. Hence the use of lower enrichment fuel should not cause any reduction in reactor performances. (2) The fuel cycle cost for operating research reactors with alternative fuel, excepting R and D cost for such fuel, should not increase beyond an acceptable limit. (3) The use of alternative fuel should be satisfactory with respect to non-proliferation purposes, to the almost same degree as the use of 20% enriched uranium fuel

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

International Nuclear Information System (INIS)

1977-11-01

Very little information is available to IAEA on the geology and uranium potential of Syria. In 1975 a contract was awarded to Huntings Geology and Geophysics Ltd by the Ministry of Petroleum and Mineral Resources to carry out a study of the country's mineral resources with particular reference to phosphate uranium, chrome and industrial materials. The results of this survey are not known. Apart from the assumption of some possibility of uranium recovery as a by-product from phosphate production it is assumed that the Speculative Potential is likely to be less than 1000 tonnes uranium. (author)

Technology for down-blending weapons grade uranium into commercial reactor-usable uranium

International Nuclear Information System (INIS)

Arbital, J.G.; Snider, J.D.

1996-01-01

The US Department of Energy (DOE) is evaluating options for rendering surplus inventories of highly enriched uranium (HEU) incapable of being used in nuclear weapons. Weapons-capable HEU was earlier produced by enriching the uranium isotope 235 U from its natural occurring 0.71 percent isotopic concentration to at least 20 percent isotopic concentration. Now, by permanently diluting the concentration of the 235 U isotope, the weapons capability of HEU can be eliminated in a manner that is reversible only through isotope re-enrichment, and therefore, highly resistant to proliferation. To the extent that can be economically and technically justified, the down-blended, low-enriched uranium product will be made suitable for use as commercial reactor fuel. Such down-blended uranium product can also be disposed of as waste if chemical or isotopic impurities preclude its use as reactor fuel. The DOE has evaluated three candidate processes for down blending surplus HEU. These candidate processes are: (1) uranium hexafluoride blending; (2) molten uranium metal blending; and (3) uranyl nitrate solution blending. This paper describes each of these candidate processes. It also compares the relative advantages and disadvantages of each process with respect to: (1) the various forms and compounds of HEU comprising the surplus inventory, (2) the use of down-blended product as commercial reactor fuel, or (3) its disposal as waste

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

Oak Ridge Geochemical Reconnaissance Program

International Nuclear Information System (INIS)

Arendt, J.W.

1977-03-01

The Oak Ridge reconnaissance program is responsible for the geochemical survey in a 12-state area covering Texas, Oklahoma, Kansas, Nebraska, South Dakota, North Dakota, Minnesota, Wisconsin, Michigan, Iowa, Indiana, and Illinois as part of the National Uranium Resource Evaluation Program. The program concept is outlined and the planning and organization of the program is discussed

Evaluation of the uranium potential of the Bushveld Complex

International Nuclear Information System (INIS)

Cheney, E.S.

1986-04-01

The poor quality of the airborne radiometric surveys and the lack of exploration geochemical data in the public domain prevent a satisfactory assessment of the uranium potential of the Bushveld area. Undue reliance must be placed upon fitting models of uranium ore deposits to the geology of the Bushveld area. Although the Bushveld granites have an unusually high background of uranium (20 to 40 ppm), they probably only host small vein-type deposits. The vein at the Albert Silver mine should be investigated as a type example to determine if it is only economic in the narrow interval of supergene enrichment. The Rooiberg Group has considerable potential for caldera-related deposits and for uranium-bearing sulphide deposits (including Olympic Dam-type deposits) in sedimentary interbeds. The Loskop Formation appears to be correlative with the Glentig and lower Swaershoek Formations of the Waterberg area. The Waterberg Group is the logical host to investigate for giant uncomformity/vein-type uranium deposits like those in Canada and Australia. Because the Waterberg consists of four uncomformity-bounded sequences, it is rarely more than 3 km thick; all of the sequences could be younger than 1770 Ma

Geophysical and geochemical regional evaluation and geophysical model for uranium exploration in the western part of Yanliao region

International Nuclear Information System (INIS)

Liu Tengyao; Cui Huanmin; Chen Guoliang; Zhai Yugui

1992-01-01

The western part of Yanliao region is an important uranium metallogenic region. This paper summarizes the regional geophysical model for uranium exploration composed of prediction model for favourable area of mineralization and evaluation model for anomalies on the basis of aeromagnetic and aeroradiometric data interpretation and analysis of the data from carborane and ground gamma spectrometric survey, high accurate magnetic survey, VLF survey and α-collected film survey in mult-displiary research work. The prospective prediction for uranium metallogenesis in this region was also conducted

A lattice-based Monte Carlo evaluation of Canada Deuterium Uranium-6 safety parameters

International Nuclear Information System (INIS)

Kim, Yong Hee; Hartanto, Donny; Kim, Woo Song

2016-01-01

Important safety parameters such as the fuel temperature coefficient (FTC) and the power coefficient of reactivity (PCR) of the CANada Deuterium Uranium (CANDU-6) reactor have been evaluated using the Monte Carlo method. For accurate analysis of the parameters, the Doppler broadening rejection correction scheme was implemented in the MCNPX code to account for the thermal motion of the heavy uranium-238 nucleus in the neutron-U scattering reactions. In this work, a standard fuel lattice has been modeled and the fuel is depleted using MCNPX. The FTC value is evaluated for several burnup points including the mid-burnup representing a near-equilibrium core. The Doppler effect has been evaluated using several cross-section libraries such as ENDF/B-VI.8, ENDF/B-VII.0, JEFF-3.1.1, and JENDL-4.0. The PCR value is also evaluated at mid-burnup conditions to characterize the safety features of an equilibrium CANDU-6 reactor. To improve the reliability of the Monte Carlo calculations, we considered a huge number of neutron histories in this work and the standard deviation of the k-infinity values is only 0.5-1 pcm

Program of Environmental monitoring in uranium and thorium mines; Programa de monitoreo ambiental en minereas de uranio y torio

Energy Technology Data Exchange (ETDEWEB)

Perreira, E G [Centro de Desenvolvimento da Tecnologia Nuclear, Divisao de Engenharia Ambiental, Belo Horizonte, MG (Brazil)

1991-07-01

This work suggests a plan for the elaboration of a program of environmental monitoring of radioactive pollutants around mining of uranium and thorium with the purpose of protecting the man and the environment.

Uranium recovery research sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory. Annual progress report, May 1982-May 1983

International Nuclear Information System (INIS)

Foley, M.G.; Opitz, B.E.; Deutsch, W.J.

1983-06-01

Pacific Northwest Laboratory (PNL) is currently conducting research for the US Nuclear Regulatory Commission (NRC) on uranium recovery process wastes for both active and inactive operations. NRC-sponsored uranium recovery research at PNL is focused on NRC regulatory responsibilities for uranium-recovery operations: license active milling and in situ extraction operations; concur on the acceptability of DOE remedial-action plans for inactive sites; and license DOE to maintain inactive sites following remedial actions. PNL's program consists of four coordinated projects comprised of a program management task and nine research tasks that address the critical technical and safety issues for uranium recovery. Specifically, the projects endeavor to find and evaluate methods to: prevent erosion of tailings piles and prevent radon release from tailings piles; evaluate the effectiveness of interim stabilization techniques to prevent wind erosion and transport of dry tailings from active piles; estimate the dewatering and consolidation behavior of slurried tailings to promote early cover placement; design a cover-protection system to prevent erosion of the cover by expected environmental stresses; reduce seepage into ground water and prevent ground-water degradation; control solution movement and reaction with ground water in in-situ extraction operations; evaluate natural and induced restoration of ground water in in-situ extraction operations; and monitor releases to the environment from uranium recovery facilities

Uranium recovery research sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory. Annual progress report, May 1982-May 1983

Energy Technology Data Exchange (ETDEWEB)

Foley, M.G.; Opitz, B.E.; Deutsch, W.J.; Peterson, S.R.; Gee, G.W.; Serne, R.J.; Hartley, J.N.; Thomas, V.W.; Kalkwarf, D.R.; Walters, W.H.

1983-06-01

Pacific Northwest Laboratory (PNL) is currently conducting research for the US Nuclear Regulatory Commission (NRC) on uranium recovery process wastes for both active and inactive operations. NRC-sponsored uranium recovery research at PNL is focused on NRC regulatory responsibilities for uranium-recovery operations: license active milling and in situ extraction operations; concur on the acceptability of DOE remedial-action plans for inactive sites; and license DOE to maintain inactive sites following remedial actions. PNL's program consists of four coordinated projects comprised of a program management task and nine research tasks that address the critical technical and safety issues for uranium recovery. Specifically, the projects endeavor to find and evaluate methods to: prevent erosion of tailings piles and prevent radon release from tailings piles; evaluate the effectiveness of interim stabilization techniques to prevent wind erosion and transport of dry tailings from active piles; estimate the dewatering and consolidation behavior of slurried tailings to promote early cover placement; design a cover-protection system to prevent erosion of the cover by expected environmental stresses; reduce seepage into ground water and prevent ground-water degradation; control solution movement and reaction with ground water in in-situ extraction operations; evaluate natural and induced restoration of ground water in in-situ extraction operations; and monitor releases to the environment from uranium recovery facilities.

Evaluation of residual uranium contamination in the dirt floor of an abandoned metal rolling mill.

Science.gov (United States)

Glassford, Eric; Spitz, Henry; Lobaugh, Megan; Spitler, Grant; Succop, Paul; Rice, Carol

2013-02-01

A single, large, bulk sample of uranium-contaminated material from the dirt floor of an abandoned metal rolling mill was separated into different types and sizes of aliquots to simulate samples that would be collected during site remediation. The facility rolled approximately 11,000 tons of hot-forged ingots of uranium metal approximately 60 y ago, and it has not been used since that time. Thirty small mass (≈ 0.7 g) and 15 large mass (≈ 70 g) samples were prepared from the heterogeneously contaminated bulk material to determine how measurements of the uranium contamination vary with sample size. Aliquots of bulk material were also resuspended in an exposure chamber to produce six samples of respirable particles that were obtained using a cascade impactor. Samples of removable surface contamination were collected by wiping 100 cm of the interior surfaces of the exposure chamber with 47-mm-diameter fiber filters. Uranium contamination in each of the samples was measured directly using high-resolution gamma ray spectrometry. As expected, results for isotopic uranium (i.e., U and U) measured with the large-mass and small-mass samples are significantly different (p 0.05) from results for the large- or small-mass samples. Large-mass samples are more reliable for characterizing heterogeneously distributed radiological contamination than small-mass samples since they exhibit the least variation compared to the mean. Thus, samples should be sufficiently large in mass to insure that the results are truly representative of the heterogeneously distributed uranium contamination present at the facility. Monitoring exposure of workers and the public as a result of uranium contamination resuspended during site remediation should be evaluated using samples of sufficient size and type to accommodate the heterogeneous distribution of uranium in the bulk material.

Annual status report on the Uranium Mill Tailings Remedial Action Program

International Nuclear Information System (INIS)

1992-12-01

This fourteenth annual status report for the Uranium Mill Tailings Remedial Action (UMTRA) Project Office summarizes activities of the Uranium Mill Tailings Remedial Action Surface (UMTRA-Surface) and Uranium Mill Tailings Remedial Action Groundwater (UMTRA-Groundwater) Projects undertaken during fiscal year (FY) 1992 by the US Department of Energy (DOE) and other agencies. Project goals for FY 1993 are also presented. An annual report of this type was a statutory requirement through January 1, 1986, pursuant to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604. The DOE will continue to submit annual reports to DOE-Headquarters, the states, tribes, and local representatives through Project completion in order to inform the public of the yearly Project status. The purpose of the remedial action is to stabilize and control the tailings and other residual radioactive material (RRM) located on the inactive uranium processing sites in a safe and environmentally sound manner, and to minimize or eliminate potential health hazards. Commercial and residential properties near designated processing sites that are contaminated with material from the sites, herein referred to as ''vicinity properties (VP),'' are also eligible for remedial action. Included in the UMTRA Project are 24 inactive uranium processing sites and associated VPs located in 10 states, and the VPs associated with the Edgemont, South Dakota, uranium mill currently owned by the Tennessee Valley Authority (TVA) (Figure A.1, Appendix A)

Uranium: the nuclear fuel. [Canada

Energy Technology Data Exchange (ETDEWEB)

Smith, E E.N. [Eldorado Nuclear Ltd., Ottawa, Ontario (Canada)

1976-05-01

A brief history is presented of Canadian uranium exploration, production, and sales. Statistics show that Canada is a good customer for its own uranium due to a rapidly expanding nuclear power program. Due to an average 10 year lag between commencement of exploration and production, and with current producers sold out through 1985, it is imperative that exploration efforts be increased.

Recent activity on disposal of uranium waste

International Nuclear Information System (INIS)

Fujiwara, Noboru

1999-01-01

The concept on the disposal of uranium waste has not been discussed in the Atomic Energy Commission of Japan, but the research and development of it are carried out in the company and agency which are related to uranium waste. In this paper, the present condition and problems on disposal of uranium waste were shown in aspect of the nuclear fuel manufacturing companies' activity. As main contents, the past circumstances on the disposal of uranium waste, the past activity of nuclear fuel manufacturing companies, outline and properties of uranium waste were shown, and ideas of nuclear fuel manufacturing companies on the disposal of uranium waste were reported with disposal idea in the long-term program for development and utilization of nuclear energy. (author)

Research and economic evaluation on uranium enrichment by gaseous diffusion process in Japan

International Nuclear Information System (INIS)

Aochi, T.; Takahashi, S.

1977-01-01

Research and development works on uranium enrichment by gaseous diffusion process were carried out by JAERI, IPCR and industries since 1965. There are two important keys to reduce the uranium separation cost. One is the characteristics of the barrier and the other is financing and/or political planning. The technics to prepare the barrier with pore diameter of 40A have been developed with polytetrafluoroethylene, alumina and nickel. The experiment on corrosion behavior of PTFE barriers has shown better characteristics than the others. In the field of engineering research, the adiabatic efficiency of axial compressor for UF 6 was resulted to as high as 90% by long term operation tests. Based on these experimental data, techno-economic evaluation on a uranium enrichment plant was carried out with regard to the optimization of separation efficiency, numbers of step and operating conditions of the plant. Sensitivity in the separation cost were calculated as a function of pore diameter, uranium hexafluoride cost, plant capacity, electric power cost, and the plant annual expenditure. A financing plan must be such as to achieve 1. maximization of debt in a percentage of total capitalization 2. off-take contracts to utilities as security for financing 3. minimization of risks to equity and achievable cost of capital. Therefore the cash flow analysis and the schedule for construction and operation are very important for a economical feasibility of a uranium enrichment plant. To minimize the risk, not only economical but also political environment are important. The governmental supports and international agreements will be necessary

Evaluation of the performance of a metrohm titrator titrando-836 in potentiometric analysis of uranium for safeguards purposes

International Nuclear Information System (INIS)

Cristiano, Barbara Fernandes; Silva, Jose Wanderley S. da; Barros, Pedro Dionisio de; Araujo, Radier Mario S. de

2009-01-01

To achieve the requirements of the Brazilian State System of Accounting for and Control of Nuclear Materials - SSAC the Safeguards Laboratory of Brazilian Nuclear Energy Commission, LASAL, has been applying the 'Davies and Gray/NBL' method for Potentiometric determination of total uranium concentration in several forms of nuclear materials since 1984. To improve the accuracy and the repeatability the method uses as titrant, standard reference potassium dichromate NIST SRM 136e and the results are also corrected for bias with NBL CRM 112A uranium metal assay standard. This work describes the assays performed for validation of a Metrohm 836 potentiometric titrator acquired by LASAL in order to improve the analytical methodology of the laboratory. The titrator is attached to a Pt:Rh (90:10) as indicator electrode and a mercurous sulfate as the reference electrode. The evaluation of accuracy and repeatability were made by comparison, the results provided by the titrator with the certified value of standards and also by the participation in round robin program sponsored by New Brunswick Laboratory - NBL. The validation was done by a comparison of the performance between the Metrohm 836 and a Mettler - DL67 titrator which has currently been used by the laboratory. It included evaluation of the results of both equipment, the repeatability of the measurement, any systematic contributions and its uncertainties. (author)

Uranium supply and demand. Proceedings of an international symposium held by the Uranium Institute in London, June 15-17, 1976

Energy Technology Data Exchange (ETDEWEB)

Spriggs, M J [ed.

1976-01-01

The symposium received and discussed papers on uranium production in South Africa, Australia, North America and other countries (excluding USSR, Eastern Europe and China) with substantial uranium resources, and on uranium demand. All aspects of the subject were covered, including the historical development of the uranium mining and production industry in the different countries, resources, forecasts of supply and demand, costs, prices, economics, and government policies in relation both to the control of production and to the development of nuclear power program.

A mathematical model to forecast uranium production

International Nuclear Information System (INIS)

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

1987-01-01

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