Environmental assessment: Transfer of normal and low-enriched uranium billets to the United Kingdom, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1995-11-01

Under the auspices of an agreement between the U.S. and the United Kingdom, the U.S. Department of Energy (DOE) has an opportunity to transfer approximately 710,000 kilograms (1,562,000 pounds) of unneeded normal and low-enriched uranium (LEU) to the United Kingdom; thus, reducing long-term surveillance and maintenance burdens at the Hanford Site. The material, in the form of billets, is controlled by DOE's Defense Programs, and is presently stored as surplus material in the 300 Area of the Hanford Site. The United Kingdom has expressed a need for the billets. The surplus uranium billets are currently stored in wooden shipping containers in secured facilities in the 300 Area at the Hanford Site (the 303-B and 303-G storage facilities). There are 482 billets at an enrichment level (based on uranium-235 content) of 0.71 weight-percent. This enrichment level is normal uranium; that is, uranium having 0.711 as the percentage by weight of uranium-235 as occurring in nature. There are 3,242 billets at an enrichment level of 0.95 weight-percent (i.e., low-enriched uranium). This inventory represents a total of approximately 532 curies. The facilities are routinely monitored. The dose rate on contact of a uranium billet is approximately 8 millirem per hour. The dose rate on contact of a wooden shipping container containing 4 billets is approximately 4 millirem per hour. The dose rate at the exterior of the storage facilities is indistinguishable from background levels

Remediation of Hanford tank waste using magnetic separation

International Nuclear Information System (INIS)

Worl, L.A.; Avens, L.R.; de Aguero, K.J.; Coyne Prenger, F.; Stewart, W.F.; Hill, D.D.

1992-01-01

Large volumes of high-level radioactive waste are stored at the Department of Energy's Hanford site. Magnetic separation, a physical separation, process, can be used to segregate actinides and certain fission products from the waste. High gradient magnetic separation (HGMS) tests have been performed successfully using a simulated, nonradioactive underground storage tank (UST) waste. Variations in HGMS test parameters included separator matrix material, magnetic field strength, slurry surfactant, and slurry solids loading. Cerium was added to the simulated tank waste to act as a uranium surrogate. Results show that over 77% of the uranium surrogate can be captured and concentrated from the original bulk with a simple procedure. The results of these tests and the feasibility of magnetic separation for pretreatment of UST waste are discussed

Development of in-structure design spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site

International Nuclear Information System (INIS)

Julyk, L.J.

1995-09-01

In-structure response spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site are developed on the basis of recent soil-structure-interaction analyses. Recommended design spectra are provided for various locations on the tank dome

Some elementary concepts of radiation health and safety in underground uranium mines

International Nuclear Information System (INIS)

Bigu, J.

1980-02-01

Some elementary concepts of radiation health and safety in underground uranium mines are discussed. This report reviews the main radiation sources which contribute to the contamination of mine atmospheres and hence to the exposure of mine workers. A brief discussion of the biological effects of ionizing radiation, with special reference to radon and its progeny, is followed by the introduction of the presently accepted radiation indexes for radiation hazard (WL) and radiation exposure (WLM). Finally, a succinct review of the available techniques for radiation control and monitoring in underground uranium mines is complemented by a discussion of various methods of personnel radiation protection, including the use of respirators, job rotation, personnel dosimetry and medical surveillance

FLUOR HANFORD (FH) MAKES CLEANUP A REALITY IN NEARLY 11 YEARS AT HANFORD

Energy Technology Data Exchange (ETDEWEB)

GERBER, M.S.

2007-05-24

For nearly 11 years, Fluor Hanford has been busy cleaning up the legacy of nuclear weapons production at one of the Department of Energy's (DOE'S) major sites in the United States. As prime nuclear waste cleanup contractor at the vast Hanford Site in southeastern Washington state, Fluor Hanford has changed the face of cleanup. Fluor beginning on October 1, 1996, Hanford Site cleanup was primarily a ''paper exercise.'' The Tri-Party Agreement, officially called the Hanford Federal Facility Agreement and Consent Order - the edict governing cleanup among the DOE, U.S. Environmental Protection Agency (EPA) and Washington state - was just seven years old. Milestones mandated in the agreement up until then had required mainly waste characterization, reporting, and planning, with actual waste remediation activities off in the future. Real work, accessing waste ''in the field'' - or more literally in huge underground tanks, decaying spent fuel POO{approx}{approx}S, groundwater, hundreds of contaminated facilities, solid waste burial grounds, and liquid waste disposal sites -began in earnest under Fluor Hanford. The fruits of labors initiated, completed and/or underway by Fluor Hanford can today be seen across the site. Spent nuclear fuel is buttoned up in secure, dry containers stored away from regional water resources, reactive plutonium scraps are packaged in approved containers, transuranic (TRU) solid waste is being retrieved from burial trenches and shipped offsite for permanent disposal, contaminated facilities are being demolished, contaminated groundwater is being pumped out of aquifers at record rates, and many other inventive solutions are being applied to Hanford's most intransigent nuclear wastes. (TRU) waste contains more than 100 nanocuries per gram, and contains isotopes higher than uranium on the Periodic Table of the Elements. (A nanocurie is one-billionth of a curie.) At the same time, Fluor Hanford

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

Conceptual Model of Uranium in the Vadose Zone for Acidic and Alkaline Wastes Discharged at the Hanford Site Central Plateau

Energy Technology Data Exchange (ETDEWEB)

Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Szecsody, James E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Qafoku, Nikolla [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Serne, R. Jeffrey [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-09-01

Historically, uranium was disposed in waste solutions of varying waste chemistry at the Hanford Site Central Plateau. The character of how uranium was distributed in the vadose zone during disposal, how it has continued to migrate through the vadose zone, and the magnitude of potential impacts on groundwater are strongly influenced by geochemical reactions in the vadose zone. These geochemical reactions can be significantly influenced by the disposed-waste chemistry near the disposal location. This report provides conceptual models and supporting information to describe uranium fate and transport in the vadose zone for both acidic and alkaline wastes discharged at a substantial number of waste sites in the Hanford Site Central Plateau. The conceptual models include consideration of how co-disposed acidic or alkaline fluids influence uranium mobility in terms of induced dissolution/precipitation reactions and changes in uranium sorption with a focus on the conditions near the disposal site. This information, when combined with the extensive information describing uranium fate and transport at near background pH conditions, enables focused characterization to support effective fate and transport estimates for uranium in the subsurface.

System-Scale Model of Aquifer, Vadose Zone, and River Interactions for the Hanford 300 Area - Application to Uranium Reactive Transport

Energy Technology Data Exchange (ETDEWEB)

Rockhold, Mark L.; Bacon, Diana H.; Freedman, Vicky L.; Parker, Kyle R.; Waichler, Scott R.; Williams, Mark D.

2013-10-01

This report represents a synthesis and integration of basic and applied research into a system-scale model of the Hanford 300 Area groundwater uranium plume, supported by the U.S. Department of Energy’s Richland Operations (DOE-RL) office. The report integrates research findings and data from DOE Office of Science (DOE-SC), Office of Environmental Management (DOE-EM), and DOE-RL projects, and from the site remediation and closure contractor, Washington Closure Hanford, LLC (WCH). The three-dimensional, system-scale model addresses water flow and reactive transport of uranium for the coupled vadose zone, unconfined aquifer, and Columbia River shoreline of the Hanford 300 Area. The system-scale model of the 300 Area was developed to be a decision-support tool to evaluate processes of the total system affecting the groundwater uranium plume. The model can also be used to address “what if” questions regarding different remediation endpoints, and to assist in design and evaluation of field remediation efforts. For example, the proposed cleanup plan for the Hanford 300 Area includes removal, treatment, and disposal of contaminated sediments from known waste sites, enhanced attenuation of uranium hot spots in the vadose and periodically rewetted zone, and continued monitoring of groundwater with institutional controls. Illustrative simulations of polyphosphate infiltration were performed to demonstrate the ability of the system-scale model to address these types of questions. The use of this model in conjunction with continued field monitoring is expected to provide a rigorous basis for developing operational strategies for field remediation and for defining defensible remediation endpoints.

Indigenous development and networking of online radon monitors in the underground uranium mine

International Nuclear Information System (INIS)

Gaware, J.J.; Sahoo, B.K.; Sapra, B.K.; Mayya, Y.S.

2011-01-01

There has been a long standing demand for online monitoring of radon level in various locations of underground Uranium mine for taking care of radiological protection to workers. Nowadays, radon ( 222 Rn) monitors, based on electrostatic collection of charged progeny and subsequent detection by semiconductor detector are increasingly employed for radon monitoring in environment. However, such instruments have some limitations such as (i) requirement of additional dryer since sensitivity is dependent on the humidity (ii) cannot be connected to a network and (iii) not cost effective etc. Hence use of such instruments in underground uranium mine (humidity level >90), may not be reliable. Towards this end, we have indigenously developed radon monitor based on electrostatic collection and scintillation technology for the online monitoring in uranium mine. This instrument overcomes the above mentioned limitation of commercial radon monitors and based on custom made features. Different tests and measurements were carried out and compared with commercial instruments. It was found to be in an excellent agreement with the commercial instruments. A few such instruments have been installed in different locations of uranium mine at Turamdih and connected to a network system for online monitoring and display. (author)

TREATMENT TESTS FOR EX SITU REMOVAL OF CHROMATE & NITRATE & URANIUM (VI) FROM HANFORD (100-HR-3) GROUNDWATER FINAL REPORT

Energy Technology Data Exchange (ETDEWEB)

BECK MA; DUNCAN JB

1994-01-03

This report describes batch and ion exchange column laboratory scale studies investigating ex situ methods to remove chromate (chromium [VI]), nitrate (NO{sub 3}{sup -}) and uranium (present as uranium [VI]) from contaminated Hanford site groundwaters. The technologies investigated include: chemical precipitation or coprecipitation to remove chromate and uranium; and anion exchange to remove chromate, uranium and nitrate. The technologies investigated were specified in the 100-HR-3 Groundwater Treatability Test Plan. The method suggested for future study is anion exchange.

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

A spectroscopic and microscopic study of uranium speciation in the infiltration pond sediments at Hanford, USA

International Nuclear Information System (INIS)

Wang, Z.; Zachara, J.M.; McKinley, J.P.; Smith, S.C.; Qafoku, O.; Catalano, J.G.

2005-01-01

Full text of publication follows: The infiltration ponds in the '300 area' of the U.S. Department of Energy Hanford Site received large volumes of nuclear waste that contained tens of metric tons of uranium along with high concentrations of other metals such as Cu, Fe, Mn, Al and Ca during their operations from 1943 to 1975. Leaching and migration of uranium in the pond sediments threatens the integrity of the Columbia River that is with 100 m of these ponds. A clear understanding of the speciation of uranium in the pond sediments is key to predict the dissolution and migration behavior of uranium and to develop any necessary containment or decontamination strategies. In this work, we studied the speciation of uranium in a series of Hanford infiltration pond sediments and its changes after dissolution in various solution media including DDI water, sodium bicarbonate (pH 9.5) and 1 M sodium acetate (pH 4.8), using liquid-helium temperature time-resolved laser-induced fluorescence spectroscopy (TRLFS) and time-resolved laser-induced fluorescence imaging spectro-microscopy (TRLFISM), and X-ray absorption spectroscopy (XAS). XAS analysis indicated that uranium in the sediment primarily existed in the 6+ oxidation state. The TRLFS spectra of uranium in several sediments resembled those in natural, uranyl-bearing calcite and those reported for uranium co-precipitated synthetic calcite and aragonite, suggesting the presence of similar uranyl coordination environments. The TRLFS spectra varied with both sediment location and depth and there was not a linear correlation between the spectral intensity and the overall concentration of uranium, indicating the presence of multiple uranium species. While for some sediment the major spectral characteristics appeared to remain the same after extraction using DDI water, sodium bicarbonate and even sodium acetate, for others, spectral changes were observed. Comparison of the sediment uranium TRLFS spectra with a standard spectral

Changes in Uranium Speciation through a Depth Sequence of Contaminated Hanford Sediments

International Nuclear Information System (INIS)

Catalano, Jeffrey G.; McKinley, James P.; Zachara, John M.; Heald, Steve M.; Smith, Steven C.; Brown, Gordon E.

2006-01-01

The disposal of basic sodium-aluminate and acidic U(VI)-Cu(II) wastes into the now-dry North and South 300 A Process Ponds at the Hanford site resulted in U(VI) groundwater plume. To gain insight into the geochemical processes that occurred during waste disposal and that will affect the future fate and transport of this uranium plume, the solid-phase speciation of uranium in a depth sequence from the base of the North Process Pond through the vadose zone to the water table was investigated using electron microprobe measurements and x-ray absorption fine structure spectroscopy. Uranium in sediments from the base of the pond was predominantly coprecipitated with calcite. From ∼2 m below the pond base to the water table uranium occurred dominantly in a sorbed form, likely on the surface aluminosilicate clay minerals. The presence of a U(VI)-phosphate phase was also observed in this region, but it only occurred as a major uranium species at one depth. The initial sequestration of U(VI) in these sediments likely occurred through coprecipitation with calcite as conditions did not favor adsorption. As the calcite-bearing pond sediments have been removed as part of a remediation effort, future uranium fate and transport will likely be controlled primarily by adsorption/desorption phenomena

Possible application of underground leaching of uranium in ''sandstone'' deposits by drilling method

International Nuclear Information System (INIS)

Bareja, E.

1988-01-01

Underground leaching as the method for excavation of uranium from its sandstone deposits is applied in many countries. A preliminary examination of a possible use of this method to sandstone deposits in Poland suggests it to be analysed against the uranium mineralization, noted within sediments of the Lower Triassic age in the Peribaltic Syneclise in the Krynica Morska - Paslek area. Before a definite decision on such exploitation of uranium, geologic and hydrogeologic conditions should be studied of individual uranium-bearing beds, particularly their permeability and insulation by impermeable claystone series as well as extraction of uranium from its bearing sandstones. The depth at which uranium-bearing beds occur, forms a very important item. The depth at which uranium ores described in literature and exploited by this method occur, does not exceed 700 m. 7 refs. (author)

Uranium Phases in Contaminated Sediments Below Hanford's U Tank Farm

International Nuclear Information System (INIS)

Um, Wooyong; Wang, Zheming; Serne, R. Jeffrey; Williams, Benjamin D.; Brown, Christopher F.; Dodge, Cleveland J.; Francis, Arokiasamy J.

2009-01-01

Macroscopic and spectroscopic investigations (XAFS, XRF and TRLIF) on Hanford contaminated vadose zone sediments from the U-tank farm showed that U(VI) exists as different surface phases as a function of depth below ground surface (bgs). Dominant U(VI) silicate precipitates (boltwoodite and uranophane) were present in shallow-depth sediments (15-16 m bgs). In the intermediate depth sediments (20-25 m bgs), adsorbed U(VI) phases dominated but small amounts of surface precipitates consisting of polynuclear U(VI) surface complex were also identified. The deep depth sediments (> 28 m bgs) showed no signs of contact with tank wastes containing Hanford-derived U(VI), but natural uranium solid phases were observed. Most of the U(VI) was preferentially associated with the silt and clay size fractions and showed strong correlation with Ca, especially for the precipitated U(VI) silicate phase in the shallow depth sediments. Because U(VI) silicate precipitates dominate the U(VI) phases in the shallow depth sediments, macroscopic (bi)carbonate leaching should result in U(VI) releases from both desorption and dissolution processes. Having several different U(VI) surface phases in the Hanford contaminated sediments indicates that the U(VI) release mechanism could be complicated and that detailed characterization of the sediments would be needed to estimate U(VI) fate and transport in vadose zone

Registration of Hanford Site Class V underground injection wells

International Nuclear Information System (INIS)

1988-05-01

This document was requested by the Washington State Department of Ecology. Based on the State Underground Injection Control Program, as described in the Washington Administrative Code, French drains and reverse wells are being registered as Class V wells. Information on out-of-service French drains, out-of-service reverse wells, and out-of-service cribs that are deeper than their largest surface dimension is also provided. The data for this submittal were taken from the Waste Information Database System (WIDS) and the Hanford Environmental Compliance Record (HECR) database. The current definition used in WIDS for an ''inactive facility'' is one that either no longer receives waste or plans to in the future. The facilities listed in WIDS as inactive have all been listed as ''out-of-service.'' Information concerning the deactivation method for a facility is included when such information is available. The French drains registered in this submittal are based on the information available at the present time. Additional French drains may be registered on a periodic basis as the drains are identified

Regulatory analysis for the use of underground barriers at the Hanford Site tank farms

International Nuclear Information System (INIS)

Hampsten, K.L.

1994-01-01

Sixty-seven of the single-shell tanks at the Hanford Site, Richland, Washington, are assumed to have leaked in the past. Some of the waste retrieval options being considered, such as past-practice sluicing (a process that uses hot water to dislodge waste for subsequent removal by pumping), have the potential for increasing releases of dangerous waste from these tanks. Underground barrier systems are being evaluated as a method to mitigate releases of tank waste to the soil and groundwater that may occur during retrieval activities. The following underground barrier system options are among those being evaluated to determine whether their construction at the Single-Shell Tank Farms is viable. (1) A desiccant barrier would be created by circulating air through the subsurface soil to lower and then maintain the water saturation below the levels required for liquids to flow. (2) An injected materials barrier would be created by injecting materials such as grout or silica into the subsurface soils to form a barrier around and under a given tank or tank farm. (3) A cryogenic barrier would be created by freezing subsurface soils in the vicinity of a tank or tank farm. An analysis is provided of the major regulatory requirements that may impact full scale construction and operation of an underground barrier system and a discussion of factors that should be considered throughout the barrier selection process, irrespective of the type of underground barrier system being considered. However, specific barrier systems will be identified when a given regulation will have significant impact on a particular type of barrier technology. Appendix A provides a matrix of requirements applicable to construction and operation of an underground barrier system

Scale-Up Information for Gas-Phase Ammonia Treatment of Uranium in the Vadose Zone at the Hanford Site Central Plateau

Energy Technology Data Exchange (ETDEWEB)

Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Szecsody, James E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zhong, Lirong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Thomle, Jonathan N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Timothy C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-09-01

Uranium is present in the vadose zone at the Hanford Central Plateau and is of concern for protection of groundwater. The Deep Vadose Zone Treatability Test Plan for the Hanford Central Plateau identified gas-phase treatment and geochemical manipulation as potentially effective treatment approaches for uranium and technetium in the Hanford Central Plateau vadose zone. Based on laboratory evaluation, use of ammonia vapor was selected as the most promising uranium treatment candidate for further development and field testing. While laboratory tests have shown that ammonia treatment effectively reduces the mobility of uranium, additional information is needed to enable deployment of this technology for remediation. Of importance for field applications are aspects of the technology associated with effective distribution of ammonia to a targeted treatment zone, understanding the fate of injected ammonia and its impact on subsurface conditions, and identifying effective monitoring approaches. In addition, information is needed to select equipment and operational parameters for a field design. As part of development efforts for the ammonia technology for remediation of vadose zone uranium contamination, field scale-up issues were identified and have been addressed through a series of laboratory and modeling efforts. This report presents a conceptual description for field application of the ammonia treatment process, engineering calculations to support treatment design, ammonia transport information, field application monitoring approaches, and a discussion of processes affecting the fate of ammonia in the subsurface. The report compiles this information from previous publications and from recent research and development activities. The intent of this report is to provide technical information about these scale-up elements to support the design and operation of a field test for the ammonia treatment technology.

Distribution of radium-226 body burden among workers in an underground uranium mine in India

International Nuclear Information System (INIS)

Patnaik, R.L.; Srivastava, V.S.; Kumar, Rajesh; Shukla, A.K.; Tripathi, R.M.; Puranik, V.D.

2007-01-01

Workers are exposed to ore dust containing uranium and its daughter products during mining and processing of uranium ore. These radio nuclides may be an inhalation hazard to the workers during the course of their occupation. The most significant among these radio nuclides is 226 Ra. Measurement of radium body burden of uranium mine and mill workers are important to control the exposure of workers within the prescribed limit. Radon-in-breath measurement technique is used for measurement of radium body burden. Workers associated with different category of underground mining operations were monitored. The measurement results indicate that workers associated with different category of underground mining operations are having 226 Ra body burden ranging from 0.15 - 2.85 kBq. It was also observed that workers involved in timbering operation are having maximum average 226 Ra body burden of 0.97 ± 0.54 kBq. Overall average radium body burden observed for 683 workers is 0.80 kBq. (author)

Underground leaching - A method for the economic extraction of uranium from low-grade ores; Podzemnoe vyshchelachivanie - sposob ehkonomicheskogo izvlecheniya urana iz bednykh rud

Energy Technology Data Exchange (ETDEWEB)

Zefirov, A P [Gosudarstvennyj Komitet po Ispol' zovaniyu Atomnoj EHnergii SSSR, Moskva, Union of Soviet Socialist Republics (Russian Federation)

1967-06-15

The method of underground leaching of uranium ores has a number of advantages over extraction followed by processing of the ores in factories. It has been studied in two types of deposit, occurring in rock masses and sandy shales. Research techniques were worked out accordingly for the leaching of uranium from large-grained ore (-200 mm) and from layers in natural stratification. Special models were constructed permitting the simulation of underground leaching conditions. The results obtained were checked in field conditions on experimental plots and experimental underground blocks. The investigations demonstrated the practicability of the process of underground leaching of uranium from certain ores and made it possible to work out flow-sheets and routines for an industrial process, information about which is given in the paper. (author)

Uranium Release from Acidic Weathered Hanford Sediments: Single-Pass Flow-Through and Column Experiments

Energy Technology Data Exchange (ETDEWEB)

Wang, Guohui [Pacific Northwest National Laboratory, Richland, Washington 99354, United States; Um, Wooyong [Pacific Northwest National Laboratory, Richland, Washington 99354, United States; Pohang University of Science and Technology (POSTECH), Pohang, South Korea; Wang, Zheming [Pacific Northwest National Laboratory, Richland, Washington 99354, United States; Reinoso-Maset, Estela [Sierra; Washton, Nancy M. [Pacific Northwest National Laboratory, Richland, Washington 99354, United States; Mueller, Karl T. [Pacific Northwest National Laboratory, Richland, Washington 99354, United States; Perdrial, Nicolas [Department; Department; O’Day, Peggy A. [Sierra; Chorover, Jon [Department

2017-09-21

The reaction of acidic radioactive waste with sediments can induce mineral transformation reactions that, in turn, control contaminant fate. Here, sediment weathering by synthetic uranium-containing acid solutions was investigated using bench-scale experiments to simulate waste disposal conditions at Hanford’s cribs, USA. During acid weathering, the presence of phosphate exerted a strong influence over uranium mineralogy and a rapidly precipitated, crystalline uranium phosphate phase (meta-ankoleite [K(UO2)(PO4)·3H2O]) was identified using spectroscopic and diffraction-based techniques. In phosphate-free system, uranium oxyhydroxide minerals such as K-compreignacite [K2(UO2)6O4(OH)6·7H2O] were formed. Single-pass flow-through (SPFT) and column leaching experiments using synthetic Hanford pore water showed that uranium precipitated as meta-ankoleite during acid weathering was strongly retained in the sediments, with an average release rate of 2.67E-12 mol g-1 s-1. In the absence of phosphate, uranium release was controlled by dissolution of uranium oxyhydroxide (compreignacite-type) mineral with a release rate of 1.05-2.42E-10 mol g-1 s-1. The uranium mineralogy and release rates determined for both systems in this study support the development of accurate U-release models for prediction of contaminant transport. These results suggest that phosphate minerals may be a good candidate for uranium remediation approaches at contaminated sites.

Uranium Mobility During In Situ Redox Manipulation of the 100 Areas of the Hanford Site

International Nuclear Information System (INIS)

Resch, C.T.; Szecsody, J.E.; Fruchter, J.S.; Cantrell, K.J.; Krupka, K.M.; Williams, M.D.

1998-01-01

A series of laboratory experiments and computer simulations was conducted to assess the extent of uranium remobilization that is likely to occur at the end of the life cycle of an in situ sediment reduction process. The process is being tested for subsurface remediation of chromate- and chlorinated solvent-contaminated sediments at the Hanford Site in southeastern Washington. Uranium species that occur naturally in the +6 valence state ∼(VI) at 10 ppb in groundwater at Hanford will accumulate as U(N) through the reduction and subsequent precipitation conditions of the permeable barrier created by in situ redox manipulation. The precipitated uranium will W remobilized when the reductive capacity of the barrier is exhausted and the sediment is oxidized by the groundwater containing dissolved oxygen and other oxidants such as chromate. Although U(N) accumulates from years or decades of reduction/precipitation within the reduced zone, U(W) concentrations in solution are only somewhat elevated during aquifer oxidation because oxidation and dissolution reactions that release U(N) precipitate to solution are slow. The release rate of uranium into solution was found to be controlled mainly by the oxidation/dissolution rate of the U(IV) precipitate (half-life 200 hours) and partially by the fast oxidation of adsorbed Fe(II) (half- life 5 hours) and the slow oxidation of Fe(II)CO 3 (half-life 120 hours) in the reduced sediment. Simulations of uranium transport that incorporated these and other reactions under site-relevant conditions indicated that 35 ppb U(VI) is the maximum concentration likely to result from mobilization of the precipitated U(IV) species. Experiments also indicated that increasing the contact time between the U(IV) precipitates and the reduced sediment, which is likely to occur in the field, results in a slower U(IV) oxidation rate, which, in turn, would lower the maximum concentration of mobilized U(W). A six-month-long column experiment confirmed that

Modelling of radon control and air cleaning requirements in underground uranium mines

International Nuclear Information System (INIS)

El Fawal, M.; Gadalla, A.

2014-01-01

As a part of a comprehensive study concerned with control workplace short-lived radon daughter concentration in underground uranium mines to safe levels, a computer program has been developed and verified, to calculate ventilation parameters e.g. local pressures, flow rates and radon daughter concentration levels. The computer program is composed of two parts, one part for mine ventilation and the other part for radon daughter levels calculations. This program has been validated in an actual case study to calculate radon concentration levels, pressure and flow rates required to maintain acceptable levels of radon concentrations in each point of the mine. The required fan static pressure and the approximate energy consumption were also estimated. The results of the calculations have been evaluated and compared with similar investigation. It was found that the calculated values are in good agreement with the corresponding values obtained using ''REDES'' standard ventilation modelling software. The developed computer model can be used as an available tool to help in the evaluation of ventilation systems proposed by mining authority, to assist the uranium mining industry in maintaining the health and safety of the workers underground while efficiently achieving economic production targets. It could be used also for regulatory inspection and radiation protection assessments of workers in the underground mining. Also with using this model, one can effectively design, assess and manage underground mine ventilation systems. Values of radon decay products concentration in units of working level, pressures drop and flow rates required to reach the acceptable radon concentration relative to the recommended levels, at different extraction points in the mine and fan static pressure could be estimated which are not available using other software. (author)

Bio-chemical remediation of under-ground water contaminated by uranium in-situ leaching

International Nuclear Information System (INIS)

Wang Qingliang; Li Qian; Zhang Hongcan; Hu Eming; Chen Yongbo

2014-01-01

In the process of uranium in-situ leaching, it was serious that strong acid, uranium and heavy metals, and SO_4"2"-, NO_3"- could contaminate underground water. To remedy these pollutants, conventional methods are high-cost and low-efficient, so a bio-chemical remediation method was proposed to cope with the under-ground water pollution in this study. The results showed, in the chemical treatment with Ca(OH)_2 neutralization, pH went up from 2.0 to 7.0, the removal rates of U, Mn"2"+, Zn"2"+, Pb"2"+, SO_4"2"-, NO_3"- were 91.5%, 78.3%, 85.1%, 100%, 71.4% and 2.6% respectively, SO_4"2"- and NO_3"- need to be treated again by bio-method. In the biological process, the Hydraulic Retention Time (HRT) of bioreactor was controlled at 42 h, and 100% NO_3"- and 70% SO_4"2"- in the contaminated water were removed; Acidithiobacillus ferrooxidans (A. f) liquid to H_2S showed better absorption effect, can fully meet the process requirements of H_2S removal. (authors)

Real time gamma monitoring for employees working in an operational underground copper / uranium mine

International Nuclear Information System (INIS)

Lawrence, Cameron E.

2010-01-01

For many years electronic devices have been available that are compact enough to utilise for personal gamma radiation monitoring. At BHP Billiton's Olympic Dam underground copper / uranium mine two different types of electronic gamma dosimeters are being used to assess and control exposure to gamma rays present in the underground operations. Canberra Dosicards are being used as part of a program that replaced the use of monthly issued Thermoluminescent Dosimeter (TLD) badges with quarterly issue for some work groups. Two types of Polimaster gamma watches have also been introduced to specific work groups to assist with the determination of sites that may require remedial controls for their level of gamma radiation. To date, both programs have been successfully implemented into the radiation monitoring program for the underground operation and have provided dramatic improvements for the control and determination of sources of gamma radiation in the underground environment.

An investigation into radiation exposures in underground non-uranium mines in Western Australia

International Nuclear Information System (INIS)

Hewson, G.S.; Ralph, M.I.

1994-01-01

A preliminary investigation into the radiological conditions in underground non-uranium mines in Western Australia has been undertaken. Measurements of radon concentration by passive track etch monitors and absorbed gamma dose-rate by thermoluminescent dosimetry were undertaken in 27 mines. These mines employed 2173 workers which represented nearly 80% of the underground workforce at the time of the survey. Radon progeny concentration by both grab sampling and automatic devices were undertaken at selected mines. Radiological conditions in all surveyed underground workplaces were such that it was estimated that most underground workers should not exceed an annual effective dose of 5 mSv. The average annual effective dose across all mines was estimated to be 1.4±1.0 mSv, ranging from 0.4 mSv for a nickel mine to 4.2 mSv for a coal mine. Radon progeny exposure contributed approximately 70% of the total effective dose. The estimated average annual effective dose in three coal mines (employing 297 workers) was 2.9±1.5 mSv. On the basis of this preliminary investigation it was concluded that no regulatory controls are specifically required to limit radiation exposures in Western Australian underground mines. (author)

Chemistry of application of calcination/dissolution to the Hanford tank waste inventory

International Nuclear Information System (INIS)

Delegard, C.H.; Elcan, T.D.; Hey, B.E.

1994-05-01

Approximately 330,000 metric tons of sodium-rich radioactive waste originating from separation of plutonium from irradiated uranium fuel are stored in underground tanks at the Hanford Site in Washington State. Fractionation of the waste into low-level waste (LLW) and high-level waste (HLW) streams is envisioned via partial water dissolution and limited radionuclide extraction operations. Under optimum conditions, LLW would contain most of the chemical bulk while HLW would contain virtually all of the transuranic and fission product activity. Calcination at around 850 C, followed by water dissolution, has been proposed as an alternative initial treatment of Hanford Site waste to improve waste dissolution and the envisioned LLW/HLW split. Results of literature and laboratory studies are reported on the application of calcination/dissolution (C/D) to the fractionation of the Hanford Site tank waste inventory. Both simulated and genuine Hanford Site waste materials were used in the lab tests. To evaluation confirmed that C/D processing reduced the amount of several components from the waste. The C/D dissolutions of aluminum and chromium allow redistribution of these waste components from the HLW to the LLW fraction. Comparisons of simple water-washing with C/D processing of genuine Hanford Site waste are also reported based on material (radionuclide and chemical) distributions to solution and solid residue phases. The lab results show that C/D processing yielded superior dissolution of aluminum and chromium sludges compared to simple water dissolution. 57 refs., 26 figs., 18 tabs

Chemistry of application of calcination/dissolution to the Hanford tank waste inventory

Energy Technology Data Exchange (ETDEWEB)

Delegard, C.H.; Elcan, T.D.; Hey, B.E.

1994-05-01

Approximately 330,000 metric tons of sodium-rich radioactive waste originating from separation of plutonium from irradiated uranium fuel are stored in underground tanks at the Hanford Site in Washington State. Fractionation of the waste into low-level waste (LLW) and high-level waste (HLW) streams is envisioned via partial water dissolution and limited radionuclide extraction operations. Under optimum conditions, LLW would contain most of the chemical bulk while HLW would contain virtually all of the transuranic and fission product activity. Calcination at around 850 C, followed by water dissolution, has been proposed as an alternative initial treatment of Hanford Site waste to improve waste dissolution and the envisioned LLW/HLW split. Results of literature and laboratory studies are reported on the application of calcination/dissolution (C/D) to the fractionation of the Hanford Site tank waste inventory. Both simulated and genuine Hanford Site waste materials were used in the lab tests. To evaluation confirmed that C/D processing reduced the amount of several components from the waste. The C/D dissolutions of aluminum and chromium allow redistribution of these waste components from the HLW to the LLW fraction. Comparisons of simple water-washing with C/D processing of genuine Hanford Site waste are also reported based on material (radionuclide and chemical) distributions to solution and solid residue phases. The lab results show that C/D processing yielded superior dissolution of aluminum and chromium sludges compared to simple water dissolution. 57 refs., 26 figs., 18 tabs.

Occurrence forms of uranium in the production solutions in the areas of underground leaching of epigenetic uranium deposits

International Nuclear Information System (INIS)

Serebrennikov, V.S.; Dorofeeva, V.A.

1980-01-01

Redox, acid-basic features of solutions (Eh changes from + 50 to 650 mV, pH from 7.5 to 1.5) and their chemical composition are studied in the process of hydrogeochemical investigations at the areas of underground leaching (UL) of epigenetic uranium deposits. It is shown that at studied areas of UL under neutral and weakly acidic conditions up to (pH 6.0-5.8), carbonate complexes of uranyl are the prevailing form of uranium existence in the solution, and sulfate complexes prevail under more acidic conditions. A supposition is made that it is expedient to process separate ore blocks with increased carbonate contents, particularly with oxidant additions under near-neutral acid-basic conditions (pH 7.2-6.8) with the use of weakly acid pumping solutions, which act (at the expense of their interaction with carbonates of ore-containing rocks) for enrichment of working solutions with HCO 3 - and CO 3 2- ions, promoting uranium transfer into solution

Underground storage tank integrated demonstration: Evaluation of pretreatment options for Hanford tank wastes

International Nuclear Information System (INIS)

Lumetta, G.J.; Wagner, M.J.; Colton, N.G.; Jones, E.O.

1993-06-01

Separation science plays a central role inn the pretreatment and disposal of nuclear wastes. The potential benefits of applying chemical separations in the pretreatment of the radioactive wastes stored at the various US Department of Energy sites cover both economic and environmental incentives. This is especially true at the Hanford Site, where the huge volume (>60 Mgal) of radioactive wastes stored in underground tanks could be partitioned into a very small volume of high-level waste (HLW) and a relatively large volume of low-level waste (LLW). The cost associated with vitrifying and disposing of just the HLW fraction in a geologic repository would be much less than those associated with vitrifying and disposing of all the wastes directly. Futhermore, the quality of the LLW form (e.g., grout) would be improved due to the lower inventory of radionuclides present in the LLW stream. In this report, we present the results of an evaluation of the pretreatment options for sludge taken from two different single-shell tanks at the Hanford Site-Tanks 241-B-110 and 241-U-110 (referred to as B-110 and U-110, respectively). The pretreatment options examined for these wastes included (1) leaching of transuranic (TRU) elements from the sludge, and (2) dissolution of the sludge followed by extraction of TRUs and 90 Sr. In addition, the TRU leaching approach was examined for a third tank waste type, neutralized cladding removal waste

200 Area plateau inactive miscellaneous underground storage tanks locations

International Nuclear Information System (INIS)

Brevick, C.H.

1997-01-01

Fluor Daniel Northwest (FDNW) has been tasked by Lockheed Martin Hanford Corporation (LMHC) to incorporate current location data for 64 of the 200-Area plateau inactive miscellaneous underground storage tanks (IMUST) into the centralized mapping computer database for the Hanford facilities. The IMUST coordinate locations and tank names for the tanks currently assigned to the Hanford Site contractors are listed in Appendix A. The IMUST are inactive tanks installed in underground vaults or buried directly in the ground within the 200-East and 200-West Areas of the Hanford Site. The tanks are categorized as tanks with a capacity of less than 190,000 liters (50,000 gal). Some of the IMUST have been stabilized, pumped dry, filled with grout, or may contain an inventory or radioactive and/or hazardous materials. The IMUST have been out of service for at least 12 years

Hanford tank initiative test facility site selection study

International Nuclear Information System (INIS)

Staehr, T.W.

1997-01-01

The Hanford Tanks Initiative (HTI) project is developing equipment for the removal of hard heel waste from the Hanford Site underground single-shell waste storage tanks. The HTI equipment will initially be installed in the 241-C-106 tank where its operation will be demonstrated. This study evaluates existing Hanford Site facilities and other sites for functional testing of the HTI equipment before it is installed into the 241-C-106 tank

Radiological modeling software for underground uranium mines

International Nuclear Information System (INIS)

Bjorndal, B.; Moridi, R.

1999-01-01

The Canadian Institute for Radiation Safety (CAIRS) has developed computer simulation software for modeling radiological parameters in underground uranium mines. The computer program, called 3d RAD, allows radiation protection professionals and mine ventilation engineers to quickly simulate radon and radon progeny activity concentrations and potential alpha energy concentrations in complex mine networks. The simulation component of 3d RAD, called RSOLVER, is an adaptation of an existing modeling program called VENTRAD, originally developed at Queen's University, Ontario. Based on user defined radiation source terms and network physical properties, radiological parameters in the network are calculated iteratively by solving Bateman's Equations in differential form. The 3d RAD user interface was designed in cooperation with the Canada Centre for Mineral and Energy Technology (CANMET) to improve program functionality and to make 3d RAD compatible with the CANMET ventilation simulation program, 3d CANVENT. The 3d RAD program was tested using physical data collected in Canadian uranium mines. 3d RAD predictions were found to agree well with theoretical calculations and simulation results obtained from other modeling programs such as VENTRAD. Agreement with measured radon and radon progeny levels was also observed. However, the level of agreement was found to depend heavily on the precision of source term data, and on the measurement protocol used to collect radon and radon progeny levels for comparison with the simulation results. The design and development of 3d RAD was carried out under contract with the Saskatchewan government

Hanford Waste Vitrification Plant Dangerous Waste Permit Application

International Nuclear Information System (INIS)

1991-10-01

The Hanford Facility currently stores mixed waste, resulting from various processing operations, in underground storage tanks. The Hanford Waste Vitrification Plant will be constructed and operated to process the high-activity fraction of mixed waste stored in these underground tanks. The Hanford Waste Vitrification Plant will solidify pretreated tank waste into a glass product that will be packaged for disposal in a national repository. This Vitrification Plant Dangerous Waste Permit Application, Revision 2, consists of both a Part A and a Part B permit application. An explanation of the Part A revisions, including Revision 4 submitted with this application, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987)

Hanford Site Waste Storage Tank Information Notebook

International Nuclear Information System (INIS)

Husa, E.I.; Raymond, R.E.; Welty, R.K.; Griffith, S.M.; Hanlon, B.M.; Rios, R.R.; Vermeulen, N.J.

1993-07-01

This report provides summary data on the radioactive waste stored in underground tanks in the 200 East and West Areas at the Hanford Site. The summary data covers each of the existing 161 Series 100 underground waste storage tanks (500,000 gallons and larger). It also contains information on the design and construction of these tanks. The information in this report is derived from existing reports that document the status of the tanks and their materials. This report also contains interior, surface photographs of each of the 54 Watch List tanks, which are those tanks identified as Priority I Hanford Site Tank Farm Safety Issues in accordance with Public Law 101-510, Section 3137*

Hanford underground storage tank waste filtration process evaluation

International Nuclear Information System (INIS)

Walker, B.W.; McCabe, D.J.

1997-01-01

The purpose of this filter study was to evaluate cross-flow filtration as effective solid-liquid separation technology for treating Hanford wastes, outline operating conditions for equipment, examine the expected filter flow rates, and determine proper cleaning. Two Hanford waste processing applications have been identified as candidates for the use of cross-flow filtration. The first of the Hanford applications involves filtration of the decanted supernate from sludge leaching and washing operations. This process involves the concentration and removal of dilute (0.05 wt percent) fines from the bulk of the supernate. The second application involves filtration to wash and concentrate the sludge during out-of-tank processing. This process employs a relatively concentrated (8 wt percent) solids feed stream. Filter studies were conducted with simulants to evaluate whether 0.5 micron cross-flow sintered metal Mott filters and 0.1 micron cross-flow Graver filters can perform solid-liquid separation of the solid/liquid waste streams effectively. In cross-flow filtration the fluid to be filtered flows in parallel to the membrane surface and generates shearing forces and/or turbulence across the filter medium. This shearing influences formation of filter cake stabilizing the filtrate flow rate

Environmental report of Purex Plant and Uranium Oxide Plant - Hanford reservation

International Nuclear Information System (INIS)

1979-04-01

A description of the site, program, and facilities is given. The data and calculations indicate that there will be no significant adverse environmental impact from the resumption of full-scale operations of the Purex and Uranium Oxide Plants. All significant pathways of radionuclides in Purex Plant effluents are evaluated. This includes submersion in the airborne effluent plumes, consumption of drinking water and foodstuffs irrigated with Columbia River water, ingestion of radioactive iodine through the cow-to-milk pathway, consumption of fish, and other less significant pathways. A summary of research and surveillance programs designed to assess the possible changes in the terresstrial and aquatic environments on or near the Hanford Reservation is presented. The nonradiological discharges to the environment of prinicpal interest are chemicals, sewage, and solid waste. These discharges will not lead to any significant adverse effects on the environment

Indigenous development and networking of online radon monitors in the underground uranium mine

International Nuclear Information System (INIS)

Gaware, J.J.; Sahoo, B.K.; Sapra, B.K.; Mayya, Y.S.

2010-01-01

Full text: There has been a long standing demand for online monitoring of radon level in various locations of underground uranium mine for taking care of radiological protection to workers. Nowadays, radon ( 222 Rn) monitors, based on semiconductor detector are increasingly employed for radon monitoring in environment. However, such instruments have some limitations such as (i) requirement of additional dryer in the sampling path, (ii) cannot be connected to a online data logging and monitoring network, (iii) not cost effective for large number of installations. Due to need for dryer, unattended continuous operation of such instruments is not possible particularly in underground uranium mine with humidity in the range of 80 to 98 %. So it is required to develop radon monitors which overcome the above limitations so that large number of monitors can be deployed in the uranium mine. Often radon progeny is electrostatically collected on the detector surface to increase the sensitivity. However, the collection efficiency is highly dependent upon the humidity and trace gas concentration in the sample gas due to charge neutralization effect. This effect can be minimized by applying a high electric field throughout the detector's chamber volume. This cannot be achieved using planner silicon PIN diode (area ∼ 4 cm 2 ) due to its inherent size limitations. This is because the electric field, in case of small inner electrode, falls off rapidly towards the outer electrode. Hence, an instrument has been indigenously developed by designing an annular cylindrical chamber with larger inner cathode (area = 140 cm 2 ) by employing flexible ZnS:Ag sheet (scintillation detector). With this design, the high sensitivity of 2.8 cph/Bqm -3 has been accomplished with the nominal deviation within 15% for vast change in humidity of 5% to 95%. In this instrument, although the alpha spectroscopy is not possible, the high sensitivity of the instruments makes it possible to achieve the MDL as

A review of technology for verification of waste removal from Hanford Underground Storage Tanks (WHC Issue 30)

International Nuclear Information System (INIS)

Thunborg, S.

1994-09-01

Remediation of waste from Underground Storage Tanks (UST) at the Hanford Waste storage sites will require removal of all waste to a nearly clean condition. Current requirements are 99% clean. In order to meet remediation legal requirements, a means to remotely verify that the waste has been removed to sufficient level is needed. This report discusses the requirements for verification and reviews major technologies available for inclusion in a verification system. The report presents two operational scenarios for verification of residual waste volume. Thickness verification technologies reviewed are Ultrasonic Sensors, Capacitance Type Sensors, Inductive Sensors, Ground Penetrating Radar, and Magnetometers. Of these technologies Inductive (Metal Detectors) and Ground Penetrating Radar appear to be the most suitable for use as waste thickness sensors

Hanford Site Tank Waste Remediation System

International Nuclear Information System (INIS)

1993-05-01

The US Department of Energy's (DOE) Hanford Site in southeastern Washington State has the most diverse and largest amount of highly radioactive waste of any site in the US. High-level radioactive waste has been stored in large underground tanks since 1944. A Tank Waste Remediation System Program has been established within the DOE to safely manage and immobilize these wastes in anticipation of permanent disposal in a geologic repository. The Hanford Site Tank Waste Remediation System Waste Management 1993 Symposium Papers and Viewgraphs covered the following topics: Hanford Site Tank Waste Remediation System Overview; Tank Waste Retrieval Issues and Options for their Resolution; Tank Waste Pretreatment - Issues, Alternatives and Strategies for Resolution; Low-Level Waste Disposal - Grout Issue and Alternative Waste Form Technology; A Strategy for Resolving High-Priority Hanford Site Radioactive Waste Storage Tank Safety Issues; Tank Waste Chemistry - A New Understanding of Waste Aging; Recent Results from Characterization of Ferrocyanide Wastes at the Hanford Site; Resolving the Safety Issue for Radioactive Waste Tanks with High Organic Content; Technology to Support Hanford Site Tank Waste Remediation System Objectives

McArthur River underground exploration program: report of the joint Federal-Provincial panel on uranium mining developments in Northern Saskatchewan

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-01-15

A report of the joint federal-provincial panel on uranium mining developments in northern Saskatchewan, on the McArthur River underground exploration program. The proposal to construct the surface and underground facilities required for the exploration and delineation of the McArthur River ore body, and any necessary additional infrastructure has been examined and public hearings have been held. The panel recommends that the underground exploration program as described by Cameco in its Environmental Impact Statement, and as clarified in its written and oral responses to the panel, be allowed to proceed under the conditions described within the report.

McArthur River underground exploration program: report of the joint Federal-Provincial panel on uranium mining developments in Northern Saskatchewan

International Nuclear Information System (INIS)

1993-01-01

A report of the joint federal-provincial panel on uranium mining developments in northern Saskatchewan, on the McArthur River underground exploration program. The proposal to construct the surface and underground facilities required for the exploration and delineation of the McArthur River ore body, and any necessary additional infrastructure has been examined and public hearings have been held. The panel recommends that the underground exploration program as described by Cameco in its Environmental Impact Statement, and as clarified in its written and oral responses to the panel, be allowed to proceed under the conditions described within the report

Uranium release from different size fractions of sediments in Hanford 300 area, Washington, USA

International Nuclear Information System (INIS)

Du Jiangkun; Bao Jianguo; Hu Qinhong; Ewing, Robert P.

2012-01-01

Stirred-flow cell tests were carried out to investigate uranium (U) release from different size fractions of sediments from the U.S. Department of Energy’s Hanford 300 Area in Washington, USA. Results show that the measured concentration of U release varies with different size fractions, with the fine-grained mass fractions (<75 μm, 75–500 μm, and 500–2000 μm) being the main U carriers. However, because the sediment is mainly composed of gravel (2000–8000 μm) materials, the gravel fraction is a non-negligible U pool. Our elution experiments give a value of 8.7% of the total U being in the gravel fraction, significantly reducing the current uncertainty in evaluating U inventory. A log–log plot of released U concentration vs. elution volume (i.e., elution time) shows a power-law relationship for all size fractions, with identical exponents for the three fine size fractions (−0.875). For the <2000 μm mass fraction, comparing our eluted U values with reported total U concentrations, we estimate that a lower bound value 8.6% of the total uranium is labile. This compares well with the previously published value of 11.8% labile U after extraction with a dilute extractant for three weeks. - Highlights: ► Stirred-flow cells were used to study U release in Hanford 300 Area sediment. ► Fine-grained size fractions have higher U concentrations. ► U in coarse fraction is less studied, but its 8.7–9.3% of total U is non-negligible. ► A power-law relationship is observed between released U and elution volume. ► About 8.6% of U in the <2 mm sediment is labile.

The effect of time-dependent ventilation and radon (thoron) gas emanation rates in underground uranium mines

International Nuclear Information System (INIS)

Bigu, J.

1987-01-01

A theoretical radiation mine model, suitable for underground uranium mines, has been investigated. In this model, the rate of ventilation and/or the radon (thoron) gas emanation from mine walls are time-dependent. Several cases of practical interest have been investigated including sinusoidal, linear, exponential, stepwise, or a combination of two or more of the above. Analytical solutions were obtained for the time-dependent radon (thoron) gas emanation rate. However, because of the extreme analytical complexity of the solutions corresponding to the time-dependent ventilation rate case, numerical solutions were found using a special Runge-Kutta procedure and the Hamming's modified predictor-corrector method for the solution of linear initial-value problems. The mine model makes provisions for losses of radioactivity, other than by ventilation and radioactive decay, by, say, plate-out on mine walls, and by other mechanisms. Radioactivity data, i.e., radon, thoron, and their progeny, obtained with the above mine model for a number of ventilation and emanation conditions, are presented. Experimental data obtained in an inactive stope of an underground uranium mine for a time-dependent air flow case are shown. Air flow conditions (ventilation rate) were determined by tracer gas techniques using SF 6

Review of sensors for the in situ chemical characterization of the Hanford underground storage tanks

International Nuclear Information System (INIS)

Kyle, K.R.; Mayes, E.L.

1994-01-01

Lawrence Livermore National Laboratory (LLNL), in the Technical Task Plan (TTP) SF-2112-03 subtask 2, is responsible for the conceptual design of a Raman probe for inclusion in the in-tank cone penetrometer. As part of this task, LLNL is assigned the further responsibility of generating a report describing a review of sensor technologies other than Raman that can be incorporated in the in-tank cone penetrometer for the chemical analysis of the tank environment. These sensors would complement the capabilities of the Raman probe, and would give information on gaseous, liquid, and solid state species that are insensitive to Raman interrogation. This work is part of a joint effort involving several DOE laboratories for the design and development of in-tank cone penetrometer deployable systems for direct UST waste characterization at Westinghouse Hanford Company (WHC) under the auspices of the U.S. Department of Energy (DOE) Underground Storage Tank Integrated Demonstration (UST-ID)

Review of sensors for the in situ chemical characterization of the Hanford underground storage tanks

Energy Technology Data Exchange (ETDEWEB)

Kyle, K.R.; Mayes, E.L.

1994-07-29

Lawrence Livermore National Laboratory (LLNL), in the Technical Task Plan (TTP) SF-2112-03 subtask 2, is responsible for the conceptual design of a Raman probe for inclusion in the in-tank cone penetrometer. As part of this task, LLNL is assigned the further responsibility of generating a report describing a review of sensor technologies other than Raman that can be incorporated in the in-tank cone penetrometer for the chemical analysis of the tank environment. These sensors would complement the capabilities of the Raman probe, and would give information on gaseous, liquid, and solid state species that are insensitive to Raman interrogation. This work is part of a joint effort involving several DOE laboratories for the design and development of in-tank cone penetrometer deployable systems for direct UST waste characterization at Westinghouse Hanford Company (WHC) under the auspices of the U.S. Department of Energy (DOE) Underground Storage Tank Integrated Demonstration (UST-ID).

Vitrification technology for Hanford Site tank waste

International Nuclear Information System (INIS)

Weber, E.T.; Calmus, R.B.; Wilson, C.N.

1995-04-01

The US Department of Energy's (DOE) Hanford Site has an inventory of 217,000 m 3 of nuclear waste stored in 177 underground tanks. The DOE, the US Environmental Protection Agency, and the Washington State Department of Ecology have agreed that most of the Hanford Site tank waste will be immobilized by vitrification before final disposal. This will be accomplished by separating the tank waste into high- and low-level fractions. Capabilities for high-capacity vitrification are being assessed and developed for each waste fraction. This paper provides an overview of the program for selecting preferred high-level waste melter and feed processing technologies for use in Hanford Site tank waste processing

LITERATURE SURVEY FOR GROUNDWATER TREATMENT OPTIONS FOR NITRATE IODINE-129 AND URANIUM 200-ZP-1 OPERABLE UNIT HANFORD SITE

Energy Technology Data Exchange (ETDEWEB)

BYRNES ME

2008-06-05

This literature review presents treatment options for nitrate, iodine-129, and uranium, which are present in groundwater at the 200-ZP-I Groundwater Operable Unit (OU) within the 200 West Area of the Hanford Site. The objective of this review is to determine available methods to treat or sequester these contaminants in place (i.e., in situ) or to pump-and-treat the groundwater aboveground (i.e., ex situ). This review has been conducted with emphasis on commercially available or field-tested technologies, but theoretical studies have, in some cases, been considered when no published field data exist. The initial scope of this literature review included only nitrate and iodine-I 29, but it was later expanded to include uranium. The focus of the literature review was weighted toward researching methods for treatment of nitrate and iodine-129 over uranium because of the relatively greater impact of those compounds identified at the 200-ZP-I OU.

LITERATURE SURVEY FOR GROUNDWATER TREATMENT OPTIONS FOR NITRATE, IODINE-129 AND URANIUM 200-ZP-1 OPERABLE UNIT, HANFORD SITE

International Nuclear Information System (INIS)

BYRNES ME

2008-01-01

This literature review presents treatment options for nitrate, iodine-129, and uranium, which are present in groundwater at the 200-ZP-I Groundwater Operable Unit (OU) within the 200 West Area of the Hanford Site. The objective of this review is to determine available methods to treat or sequester these contaminants in place (i.e., in situ) or to pump-and-treat the groundwater aboveground (i.e., ex situ). This review has been conducted with emphasis on commercially available or field-tested technologies, but theoretical studies have, in some cases, been considered when no published field data exist. The initial scope of this literature review included only nitrate and iodine-I 29, but it was later expanded to include uranium. The focus of the literature review was weighted toward researching methods for treatment of nitrate and iodine-129 over uranium because of the relatively greater impact of those compounds identified at the 200-ZP-I OU

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

Stratified random sampling plans designed to assist in the determination of radon and radon daughter concentrations in underground uranium mine atmosphere

International Nuclear Information System (INIS)

Makepeace, C.E.

1981-01-01

Sampling strategies for the monitoring of deleterious agents present in uranium mine air in underground and surface mining areas are described. These methods are designed to prevent overexposure of the lining of the respiratory system of uranium miners to ionizing radiation from radon and radon daughters, and whole body overexposure to external gamma radiation. A detailed description is provided of stratified random sampling monitoring methodology for obtaining baseline data to be used as a reference for subsequent compliance assessment

Removing Phosphate from Hanford High-Phosphate Tank Wastes: FY 2010 Results

Energy Technology Data Exchange (ETDEWEB)

Lumetta, Gregg J.; Braley, Jenifer C.; Edwards, Matthew K.; Qafoku, Odeta; Felmy, Andrew R.; Carter, Jennifer C.; MacFarlan, Paul J.

2010-09-22

The U.S. Department of Energy (DOE) is responsible for environmental remediation at the Hanford Site in Washington State, a former nuclear weapons production site. Retrieving, processing, immobilizing, and disposing of the 2.2 × 105 m3 of radioactive wastes stored in the Hanford underground storage tanks dominates the overall environmental remediation effort at Hanford. The cornerstone of the tank waste remediation effort is the Hanford Tank Waste Treatment and Immobilization Plant (WTP). As currently designed, the capability of the WTP to treat and immobilize the Hanford tank wastes in the expected lifetime of the plant is questionable. For this reason, DOE has been pursuing supplemental treatment options for selected wastes. If implemented, these supplemental treatments will route certain waste components to processing and disposition pathways outside of WTP and thus will accelerate the overall Hanford tank waste remediation mission.

Steam reforming as a method to treat Hanford underground storage tank (UST) wastes

International Nuclear Information System (INIS)

Miller, J.E.; Kuehne, P.B.

1995-07-01

This report summarizes a Sandia program that included partnerships with Lawrence Livermore National Laboratory and Synthetica Technologies, Inc. to design and test a steam reforming system for treating Hanford underground storage tank (UST) wastes. The benefits of steam reforming the wastes include the resolution of tank safety issues and improved radionuclide separations. Steam reforming destroys organic materials by first gasifying, then reacting them with high temperature steam. Tests indicate that up to 99% of the organics could be removed from the UST wastes by steam exposure. In addition, it was shown that nitrates in the wastes could be destroyed by steam exposure if they were first distributed as a thin layer on a surface. High purity alumina and nickel alloys were shown to be good candidates for materials to be used in the severe environment associated with steam reforming the highly alkaline, high nitrate content wastes. Work was performed on designing, building, and demonstrating components of a 0.5 gallon per minute (gpm) system suitable for radioactive waste treatment. Scale-up of the unit to 20 gpm was also considered and is feasible. Finally, process demonstrations conducted on non-radioactive waste surrogates were carried out, including a successful demonstration of the technology at the 0.1 gpm scale

Prostate cancer mortality risk in relation to working underground in the Wismut cohort study of German uranium miners, 1970-2003.

Science.gov (United States)

Walsh, Linda; Dufey, Florian; Tschense, Annemarie; Schnelzer, Maria; Sogl, Marion; Kreuzer, Michaela

2012-01-01

A recent study and comprehensive literature review has indicated that mining could be protective against prostate cancer. This indication has been explored further here by analysing prostate cancer mortality in the German 'Wismut' uranium miner cohort, which has detailed information on the number of days worked underground. An historical cohort study of 58 987 male mine workers with retrospective follow-up before 1999 and prospective follow-up since 1999. Uranium mine workers employed during the period 1970-1990 in the regions of Saxony and Thuringia, Germany, contributing 1.42 million person-years of follow-up ending in 2003. Simple standardised mortality ratio (SMR) analyses were applied to assess differences between the national and cohort prostate cancer mortality rates and complemented by refined analyses done entirely within the cohort. The internal comparisons applied Poisson regression excess relative prostate cancer mortality risk model with background stratification by age and calendar year and a whole range of possible explanatory covariables that included days worked underground and years worked at high physical activity with γ radiation treated as a confounder. The analysis is based on miner data for 263 prostate cancer deaths. The overall SMR was 0.85 (95% CI 0.75 to 0.95). A linear excess relative risk model with the number of years worked at high physical activity and the number of days worked underground as explanatory covariables provided a statistically significant fit when compared with the background model (p=0.039). Results (with 95% CIs) for the excess relative risk per day worked underground indicated a statistically significant (p=0.0096) small protective effect of -5.59 (-9.81 to -1.36) ×10(-5). Evidence is provided from the German Wismut cohort in support of a protective effect from working underground on prostate cancer mortality risk.

Light duty utility arm deployment in Hanford tank T-106

International Nuclear Information System (INIS)

Kiebel, G.R.

1997-07-01

An existing gap in the technology for the remediation of underground waste storage tanks filled by the Light Duty Utility Arm (LDUA) System. On September 27 and 30, 1996, the LDUA System was deployed in underground storage tank T-106 at Hanford. The system performed successfully, satisfying all objectives of the in-tank operational test (hot test); performing close-up video inspection of features of tank dome, risers, and wall; and grasping and repositioning in-tank debris. The successful completion of hot testing at Hanford means that areas of tank structure and waste surface that were previously inaccessible are now within reach of remote tools for inspection, waste analysis, and small-scale retrieval. The LDUA System has become a new addition to the arsenal of technologies being applied to solve tank waste remediation challenges

Light duty utility arm deployment in Hanford tank T-106

Energy Technology Data Exchange (ETDEWEB)

Kiebel, G.R.

1997-07-01

An existing gap in the technology for the remediation of underground waste storage tanks filled by the Light Duty Utility Arm (LDUA) System. On September 27 and 30, 1996, the LDUA System was deployed in underground storage tank T-106 at Hanford. The system performed successfully, satisfying all objectives of the in-tank operational test (hot test); performing close-up video inspection of features of tank dome, risers, and wall; and grasping and repositioning in-tank debris. The successful completion of hot testing at Hanford means that areas of tank structure and waste surface that were previously inaccessible are now within reach of remote tools for inspection, waste analysis, and small-scale retrieval. The LDUA System has become a new addition to the arsenal of technologies being applied to solve tank waste remediation challenges.

Uranium (VI) Sorption and Transport in Unsaturated, Subsurface Hanford Site Sediments - Effect of Moisture Content and Sediment Texture: Final Report for Subtask 2b

International Nuclear Information System (INIS)

Gamerdinger, A.P.; Resch, C.T.; Kaplan, D.I.

1998-01-01

A series of experiments were conducted in fiscal year 1998 at the Pacific Northwest National Laboratory as part of the Immobilized Low-Activity Waste-Performance Assessment. These experiments evaluated the sorption and transport of uranium, U(VI), under conditions of partial moisture saturation that are relevant to arid region burial sites and vadose-zone far-field conditions at the Hanford Site. The focus was on measuring breakthrough curves (from which distribution coefficient [K d ] values can be calculated) for U(W) in three Hanford Site sediments that represent different texture classes in two unsaturated moisture conditions. Previous research showed that K d values measured during transport in unsaturated sediments varied with moisture saturation

Stability of underground excavations in a repository system

International Nuclear Information System (INIS)

Calash, A.Y.; Greer, J.C.; Andrea, S.J.; Chowdhury, A.H.; Nguyen, V.V.

1988-01-01

The DOE is investigating the feasibility of constructing a deep geologic repository at the Hanford Site, Washington, for the permanent disposal of nuclear waste. The underground openings associated with the repository design include shafts, tunnels, emplacement rooms and boreholes. The stability of these underground openings, the extent and characteristics of the disturbed zones due to excavation, and their effects on groundwater flow path and travel time have a primary influence on the performance assessment of the Hanford Site as a nuclear waste repository. This study is being done in accordance with the requirements of the NRC. Results of structural analyses of shafts and tunnels under in situ stresses and/or medium weight are presented in this paper. Four different analyses were carried out to analyze the shaft: a plane strain model, axisymmetric model, 3-D model of a single material medium, and 3-D model of a three material medium

Investigation of radon-222 emissions from underground uranium mines. Progress report No. 2

International Nuclear Information System (INIS)

Jackson, P.O.; Glissmeyer, J.A.; Enderlin, W.I.; Schwendiman, L.C.; Wogman, N.A.; Perkins, R.W.

1980-02-01

A reliable estimate of radon emissions to the environment from underground uranium mines was obtained through measurements of radon in ventilation exhaust air at 24 uranium mines and estimates of radon release from ore piles and waste piles at mines and in water pumped from mines. Three additional mines sampled in 1978 but not in 1979 were included in the overall results. Total production of U 3 O 8 from the mines thus far sampled represent about 63% of total 1978 US production from underground mines. Wide variation in radon emission per unit of production was shown from mine to mine; hence, it became necessary to sum all radon from all mines measured and divide by the sum of all U 3 O 8 production in 1978 from these mines to arrive at a valid estimate of Ci per ton of U 3 O 8 . This value was found to be 26.7 per ton or 5400 Ci/RRY (182 metric tons). The radon emitted in mine ventilation air was by far the dominant source, with other than ventilation exhaust sources accounting for less than three percent of radon in ventilation exhaust. Other observations of interest in this study were the diurnal fluctuations of radon with barometric pressure and the statistically significant relationship between radon released per year from a mine and the cumulative ore production at the time of radon measurement. The linear relationship between Ci/yr of radon and cumulative ore accounted for about half the variability.Several sources of random errors and possible biases were evaluated using some simple descriptive statistics insofar as the current data permitted. Errors in air flow rate in the vents sampled, fluctuations in radon emission with time of day, counting instrument calibration and production rate were estimated and combined to give an uncertainty of about +- 24 percent at the 95 percent confidence level

Development and underground testing of the α dosimeter: a solid state electronic personal radiation dosimeter for uranium miners

International Nuclear Information System (INIS)

Parkinson, R.N.; Roze, V.; Shepherd, R.

1981-01-01

The αDOSIMETER is a complete, integrated system designed to monitor the immediate worksite of underground miners where the disintegration for radon daughters is a risk to the health of mining personnel. The dosimeter weighing little more than one pound is worn by each miner throughout the entire shift and is powered by the miner's cap lamp battery. After this integration period, the unit is connected to a reading network whereupon the day's data is dumped, calculated and stored. Beginning in July 1980, prototype units were subjected to vigorous underground testing in uranium mines in Canada and the United States and in tin mines in Cornwall, UK. The testing results are summarized and proposals advanced for a typical mine monitoring system utilizing the αDOSIMETER

Factors influencing the reliability of non-electric detonating circuit in underground uranium mines and preventive measures of misfiring

International Nuclear Information System (INIS)

Li Qin

2010-01-01

Characteristics of non-electric detonating circuit are introduced. The main factors influencing the reliability of non-electric detonating circuit are described. Taking an underground blasting of a uranium mine for example, the reliability of various kinds of detonating network system is calculated using the reliability theory and numerical analysis method. The reasons that cause the misfiring in non-electric detonating circuit system are analyzed, and preventive measures are put forward.(authors)

HANFORD GROUNDWATER REMEDIATION

Energy Technology Data Exchange (ETDEWEB)

CHARBONEAU, B; THOMPSON, M; WILDE, R.; FORD, B.; GERBER, M.S.

2006-02-01

By 1990 nearly 50 years of producing plutonium put approximately 1.70E + 12 liters (450 billion gallons) of liquid wastes into the soil of the 1,518-square kilometer (586-square mile) Hanford Site in southeast Washington State. The liquid releases consisted of chemicals used in laboratory experiments, manufacturing and rinsing uranium fuel, dissolving that fuel after irradiation in Hanford's nuclear reactors, and in liquefying plutonium scraps needed to feed other plutonium-processing operations. Chemicals were also added to the water used to cool Hanford's reactors to prevent corrosion in the reactor tubes. In addition, water and acid rinses were used to clean plutonium deposits from piping in Hanford's large radiochemical facilities. All of these chemicals became contaminated with radionuclides. As Hanford raced to help win World War II, and then raced to produce materials for the Cold War, these radioactive liquid wastes were released to the Site's sandy soils. Early scientific experiments seemed to show that the most highly radioactive components of these liquids would bind to the soil just below the surface of the land, thus posing no threat to groundwater. Other experiments predicted that the water containing most radionuclides would take hundreds of years to seep into groundwater, decaying (or losing) most of its radioactivity before reaching the groundwater or subsequently flowing into the Columbia River, although it was known that some contaminants like tritium would move quickly. Evidence today, however, shows that many contaminants have reached the Site's groundwater and the Columbia River, with more on its way. Over 259 square kilometers (100 square miles) of groundwater at Hanford have contaminant levels above drinking-water standards. Also key to successfully cleaning up the Site is providing information resources and public-involvement opportunities to Hanford's stakeholders. This large, passionate, diverse, and

Hanford Waste Physical and Rheological Properties: Data and Gaps

Energy Technology Data Exchange (ETDEWEB)

Wells, Beric E.; Kurath, Dean E.; Mahoney, Lenna A.; Onishi, Yasuo; Huckaby, James L.; Cooley, Scott K.; Burns, Carolyn A.; Buck, Edgar C.; Tingey, Joel M.; Daniel, Richard C.; Anderson, K. K.

2011-08-01

The Hanford Site in Washington State manages 177 underground storage tanks containing approximately 250,000 m3 of waste generated during past defense reprocessing and waste management operations. These tanks contain a mixture of sludge, saltcake and supernatant liquids. The insoluble sludge fraction of the waste consists of metal oxides and hydroxides and contains the bulk of many radionuclides such as the transuranic components and 90Sr. The saltcake, generated by extensive evaporation of aqueous solutions, consists primarily of dried sodium salts. The supernates consist of concentrated (5-15 M) aqueous solutions of sodium and potassium salts. The 177 storage tanks include 149 single-shell tanks (SSTs) and 28 double -hell tanks (DSTs). Ultimately the wastes need to be retrieved from the tanks for treatment and disposal. The SSTs contain minimal amounts of liquid wastes, and the Tank Operations Contractor is continuing a program of moving solid wastes from SSTs to interim storage in the DSTs. The Hanford DST system provides the staging location for waste feed delivery to the Department of Energy (DOE) Office of River Protection’s (ORP) Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP is being designed and constructed to pretreat and then vitrify a large portion of the wastes in Hanford’s 177 underground waste storage tanks.

Accelerated clean-up at the Hanford Site

International Nuclear Information System (INIS)

Frain, J.M.; Johnson, W.L.

1994-01-01

The Hanford Site began operations in 1943 as one of the sites for plutonium production associated with the Manhattan Project. It has been used, in part, for nuclear reactor operation, reprocessing of spent fuel, and management of radioactive waste. The Hanford Site covers approximately 1,434 km 2 (560 mi 2 2) in southeastern Washington State. The subject of this paper, the 618-9 Burial Ground, is located on the Hanford Site approximately 1.6 km (1 mi) west of the Columbia River, and a few miles north of Richland, Washington. Throughout Hanford Site history, prior to legislation regarding disposal of chemical waste products, some chemical waste byproducts were disposed ,ia burial in trenches. One such trench was the 618-9 Burial Ground. This burial ground was suspected to contain approximately 19,000 L (5,000 gal) of uranium-contaminated organic solvent, disposed in standard 55-gal (208-L) metal drums. The waste was produced from research and development activities related to fuel reprocessing

Investigation of groundwater seepage from the Hanford shoreline of the Columbia River

International Nuclear Information System (INIS)

McCormack, W.D.; Carlile, J.M.V.

1984-11-01

Groundwater discharges to the Columbia River are evaluated by the Hanford Environmental Surveillance and Groundwater Surveillance Programs via monitoring of the Columbia River and Hanford groundwater. Both programs concluded that Hanford groundwater has not adversely affected Columbia River water quality. This report supplements the above programs by investigating the general characteristics of groundwater entering the Columbia River from the Hanford Site. Specific objectives of the investigation were to identify general shoreline areas where Hanford-related materials were entering the river, and to evaluate qualitatively the physical characteristics and relative magnitudes of those discharges. The study was conducted in two phases. Phase 1 involved visual inspection of Columbia River shoreline, within the Hanford Site, for indications of groundwater seepage. As a result of that inspection, 115 springs suspected of discharging groundwater were recorded. During Phase 2, water samples were collected from these springs and analyzed for Hanford-related materials known to be present in the groundwater. The specific materials used as indicators for the majority of samples were tritium or uranium and nitrate. The magnitude and distribution of concentrations measured in the spring samples were consistent with concentrations of these materials measured in groundwater near the sampled spring locations. Water samples were also collected from the Columbia River to investigate the localized effects of groundwater discharges occurring above and below river level. These samples were collected within 2 to 4 m of the Hanford shoreline and analyzed for tritium, nitrate, and uranium. Elevated concentrations were measured in river samples collected near areas where groundwater and spring concentrations were elevated. All concentrations were below applicable DOE Concentration Guides. 8 references, 6 figures, 7 tables

Underground storage tanks soft waste dislodging and conveyance

International Nuclear Information System (INIS)

Wellner, A.F.

1993-10-01

Currently 140 million liters (37 million gallons) of waste are stored in the single shell underground storage tanks (SSTs) at Hanford. The wastes contain both hazardous and radioactive constituents. This paper focuses on the Westinghouse Hanford Company's testing program for soft waste dislodging and conveyance technology. This program was initialized to investigate methods of dislodging and conveying soft waste. The main focus was on using air jets, water jets, and/or mechanical blades to dislodge the waste and air conveyance to convey the dislodged waste. These waste dislodging and conveyance technologies would be used in conjunction with a manipulator based retrieval system

TANK WASTE RETRIEVAL LESSONS LEARNED AT THE HANFORD SITE

International Nuclear Information System (INIS)

DODD, R.A.

2006-01-01

One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the US Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60% of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons of this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring the waste to the DST system since 1997 as part of the interim stabilization program. Retrieval of SST saltcake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. This paper presents lessons learned from retrieval of tank waste at the Hanford Site and discusses how this information is used to optimize retrieval system efficiency, improve overall cost effectiveness of retrieval operations, and ensure that HFFACO requirements are met

Progress and challenges in cleaning up Hanford

Energy Technology Data Exchange (ETDEWEB)

Wagoner, J.D. [Dept. of Energy, Richland, WA (United States)

1997-08-01

This paper presents captioned viewgraphs which briefly summarize cleanup efforts at the Hanford Site. Underground waste tank and spent nuclear fuel issues are described. Progress is reported for the Plutonium Finishing Plant, PUREX plant, B-Plant/Waste Encapsulation Storage Facility, and Fast Flux Test Facility. A very brief overview of costs and number of sites remediated and/or decommissioned is given.

Independent technical review of the Hanford Tank Farm Operations

International Nuclear Information System (INIS)

1992-07-01

The Independent Technical Assessment of the Hanford Tank Farm Operations was commissioned by the Assistant Secretary for Environmental Restoration and Waste Management on November 1, 1991. The Independent Technical Assessment team conducted on-site interviews and inspections during the following periods: November 18 to 22,1991; April 13 to 17; and April 27 to May 1, 1992. Westinghouse Hanford Company is the management and operating contractor for the Department of Energy at the Hanford site. The Hanford Tank Farm Operations consists of 177 underground storage tanks containing 61 million gallons of high-level radioactive mixed wastes from the chemical reprocessing of nuclear fuel. The Tank Farm Operations also includes associated transfer lines, ancillary equipment, and instrumentation. The Independent Technical Assessment of the Hanford Tank Farm Operations builds upon the prior assessments of the Hanford Waste Vitrification System and the Hanford Site Tank Waste Disposal Strategy.The objective of this technical assessment was to determine whether an integrated and sound program exists to manage the tank-waste storage and tankfarm operations consistent with the Assistant Secretary for Environmental Restoration and Waste Management's guidance of overall risk minimization. The scope of this review includes the organization, management, operation, planning, facilities, and mitigation of the safety-concerns of the Hanford Tank Waste Remediation System. The assessments presented in the body of this report are based on the detailed observations discussed in the appendices. When the assessments use the term ''Hanford'' as an organizational body it means DOE-RL and Westinghouse Hanford Company as a minimum, and in many instances all of the stake holders for the Hanford site

Radiological survey of shoreline vegetation from the Hanford Reach of the Columbia River, 1990--1992

International Nuclear Information System (INIS)

Antonio, E.J.; Poston, T.M.; Rickard, W.H. Jr.

1993-09-01

A great deal of interest exists concerning the seepage of radiologically contaminated groundwater into the Columbia River where it borders the US Department of Energy's Hanford Site (Hanford Reach). Areas of particular interest include the 100-N Area, the Old Hanford Townsite, and the 300 Area springs. While the radiological character of the seeps and springs along the Hanford Site shoreline has been studied, less attention has been given to characterizing the radionuclides that may be present in shoreline vegetation. The objective of this study was to characterize radionuclide concentrations in shoreline plants along the Hanford Reach of the Columbia River that were usable by humans for food or other purposes. Vegetation in two areas was found to have elevated levels of radionuclides. Those areas were the 100-N Area and the Old Hanford Townsite. There was also some indication of uranium accumulation in milfoil and onions collected from the 300 Area. Tritium was elevated above background in all areas; 60 Co and 9O Sr were found in highest concentrations in vegetation from the 100-N Area. Technetium-99 was found in 2 of 12 plants collected from the Old Hanford Townsite and 1 of 10 samples collected upstream from the Vernita Bridge. The concentrations of 137 Cs, 238 Pu, 239,240 Pu, and isotopes of uranium were just above background in all three areas (100-N Area, Old Hanford Townsite, and 300 Area)

Radiological survey of shoreline vegetation from the Hanford Reach of the Columbia River, 1990--1992

Energy Technology Data Exchange (ETDEWEB)

Antonio, E.J.; Poston, T.M.; Rickard, W.H. Jr.

1993-09-01

A great deal of interest exists concerning the seepage of radiologically contaminated groundwater into the Columbia River where it borders the US Department of Energy`s Hanford Site (Hanford Reach). Areas of particular interest include the 100-N Area, the Old Hanford Townsite, and the 300 Area springs. While the radiological character of the seeps and springs along the Hanford Site shoreline has been studied, less attention has been given to characterizing the radionuclides that may be present in shoreline vegetation. The objective of this study was to characterize radionuclide concentrations in shoreline plants along the Hanford Reach of the Columbia River that were usable by humans for food or other purposes. Vegetation in two areas was found to have elevated levels of radionuclides. Those areas were the 100-N Area and the Old Hanford Townsite. There was also some indication of uranium accumulation in milfoil and onions collected from the 300 Area. Tritium was elevated above background in all areas; {sup 60}Co and {sup 9O}Sr were found in highest concentrations in vegetation from the 100-N Area. Technetium-99 was found in 2 of 12 plants collected from the Old Hanford Townsite and 1 of 10 samples collected upstream from the Vernita Bridge. The concentrations of {sup 137}Cs, {sup 238}Pu, {sup 239,240}Pu, and isotopes of uranium were just above background in all three areas (100-N Area, Old Hanford Townsite, and 300 Area).

Radioactive air emissions notice of construction and application for approval to construct the Hanford Waste Vitrification Plant

International Nuclear Information System (INIS)

1992-10-01

The Hanford Site is owned by the US Government and operated by the US Department of Energy, Richland Field Office. The Hanford Site manages and produces dangerous waste and mixed waste. (containing both radioactive and dangerous components). The US Department of Energy, Richland Field Office, currently stores mixed waste, resulting from various processing operations, in underground storage tanks. The Hanford Waste Vitrification Plant will be constructed and operated to process the high-activity fraction of mixed waste stored in these underground tanks. The Hanford Waste Vitrification Plant will solidify pretreated tank waste into a glass product that will be packaged for disposal in a national repository. Emissions from the Hanford Waste Vitrification Plant will be regulated by both the federal and state Clean Air Acts. The proposed Hanford Waste Vitrification Plant represents a new source of radioactive air emissions. Construction of the plant will require approval from both federal and state agencies. The Notice of Construction and Application for Approval to Construct the Hanford Waste Vitrification Plant contains information required under Title 40 of the Code of Federal Regulations, Chapter 61; and Chapter 246-247 of the Washington Administrative Code for a proposed new source of radioactive air emissions. The document contents are based on information contained in the Hanford Waste Vitrification Plant Reference Conceptual Design Report, the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report, Revision 0, and subsequent design changes made before August 1, 1992. The contents of this document may be modified to include more specific information generated during subsequent detailed design phases. Modifications will be submitted for regulatory review and approval, as appropriate

Optimization long hole blast fragmentation techniques and detonating circuit underground uranium mine stope

International Nuclear Information System (INIS)

Li Qin; Yang Lizhi; Song Lixia; Qin De'en; Xue Yongshe; Wang Zhipeng

2012-01-01

Aim at high rate of large blast fragmentation, a big difficulty in long hole drilling and blasting underground uranium mine stope, it is pointed out at the same time of taking integrated technical management measures, the key is to optimize the drilling and blasting parameters and insure safety the act of one that primes, adopt 'minimum burden' blasting technique, renew the stope fragmentation process, and use new process of hole bottom indirect initiation fragmentation; optimize the detonating circuit and use safe, reliable and economically rational duplex non-electric detonating circuit. The production practice shows that under the guarantee of strictly controlled construction quality, the application of optimized blast fragmentation technique has enhanced the reliability of safety detonation and preferably solved the problem of high rate of large blast fragments. (authors)

Assuring safe interim storage of Hanford high-level tank wastes

International Nuclear Information System (INIS)

Bacon, R.F.; Babad, H.; Lerch, R.E.

1996-01-01

The federal government established the Hanford Site in South-Eastern Washington near the City of Richland in 1943 to produce plutonium for national defense purposes. The Hanford Site occupies approximately 1,450 square kilometers (560 square miles) of land North of the City of Richland. The production mission ended in 1988, transforming the Hanford Site mission to waste management, environmental restoration, and waste disposal. Thus the primary site mission has shifted from production to the management and disposal of radioactive, hazardous, and mixed waste that exist at the Hanford Site. This paper describes the focus and challenges facing the Tank Waste Remediation System (TWRS) Program related to the dual and parallel missions of interim safe storage and disposal of the tank associated waste. These wastes are presently stored in 2.08E+05 liters (55,000) to 4.16E+06 liters (1,100,000) gallon low-carbon steel tanks. There are 149 single- and 28 double-shell radioactive underground storage tanks, as well as approximately 40 inactive miscellaneous underground storage tanks. In addition, the TWRS mission includes the storage and disposal of the inventory of 1,929 cesium and strontium capsules created as part of waste management efforts. Tank waste was a by-product of producing plutonium and other defense related materials. From 1944 through 1990, four (4) different major chemical processing facilities at the Hanford Site processed irradiated (spent) fuel from defense reactors to separate and recover plutonium for weapons production. As new and improved processes were developed over the last 50 years, the processing efficiency improved and the waste compositions sent to the tanks for storage changed both chemically and radiologically. The earliest separation processes (e.g., bismuth phosphate coprecipitation) carried out in T Plant (1944-1956) and B Plant (1945-1952) recovered only plutonium

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

International Nuclear Information System (INIS)

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

2012-01-01

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

Resource book: Decommissioning of contaminated facilities at Hanford

International Nuclear Information System (INIS)

1991-09-01

In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 68 refs., 54 figs., 18 tabs

Resource book: Decommissioning of contaminated facilities at Hanford

International Nuclear Information System (INIS)

1991-09-01

In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 49 refs., 44 figs., 14 tabs

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs

Draft site characterization analysis of the site characterization report for the Basalt Waste Isolation Project, Hanford, Washington site. Appendices E through W

International Nuclear Information System (INIS)

1983-03-01

Volume 2 contains Appendices E through W: potential for large-scale pump tests in the Grande Ronde; review of hydrochemical characterization related to flow system interpretation in Hanford basalts; limitations of packer-testing for head evaluation in Hanford basalts; hydrogeologic data integration for conceptual groundwater flow models; drilling mud effects on hydrogeologic testing; site issue analyses related to the nature at the present groundwater system at the Hanford site, Washington; structural and stratigraphic characteristics related to groundwater flow at the Hanford site, Washington; seismic hazard and some examples of hazard studies at Hanford; earthquake swarms in the Columbia Plateau; seismic ground motion at depth; failure modes for the metallic waste package component; degradation mechanisms of borosilicate glass; transport and retardation of radionuclides in the waste package; determination and interpretation of redox conditions and changes in underground high-level repositories; determination and interpretation of sorption data applied to radionuclide migration in underground repositories; solubility of radionuclide compounds presented in the BWIP site characterization report; and release rate from engineered system

Effects of hydrated lime on radionuclides stabilization of Hanford tank residual waste.

Science.gov (United States)

Wang, Guohui; Um, Wooyong; Cantrell, Kirk J; Snyder, Michelle M V; Bowden, Mark E; Triplett, Mark B; Buck, Edgar C

2017-10-01

Chemical stabilization of tank residual waste is part of a Hanford Site tank closure strategy to reduce overall risk levels to human health and the environment. In this study, a set of column leaching experiments using tank C-104 residual waste were conducted to evaluate the leachability of uranium (U) and technetium (Tc) where grout and hydrated lime were applied as chemical stabilizing agents. The experiments were designed to simulate future scenarios where meteoric water infiltrates through the vadose zones into the interior of the tank filled with layers of grout or hydrated lime, and then contacts the residual waste. Effluent concentrations of U and Tc were monitored and compared among three different packing columns (waste only, waste + grout, and waste + grout + hydrated lime). Geochemical modeling of the effluent compositions was conducted to determine saturation indices of uranium solid phases that could control the solubility of uranium. The results indicate that addition of hydrated lime strongly stabilized the uranium through transforming uranium to a highly insoluble calcium uranate (CaUO 4 ) or similar phase, whereas no significant stabilization effect of grout or hydrated lime was observed on Tc leachability. The result implies that hydrated lime could be a great candidate for stabilizing Hanford tank residual wastes where uranium is one of the main concerns. Published by Elsevier Ltd.

Influence of Contact Time on the Extraction of 233Uranyl Spike and Contaminant Uranium From Hanford Sediment

International Nuclear Information System (INIS)

Smith, Steven C.; Szecsody, James E.

2011-01-01

In this study 233Uranyl nitrate was added to uranium (U) contaminated Hanford 300 Area sediment and incubated under moist conditions for 1 year. It hypothesized that geochemical transformations and/or physical processes will result in decreased extractability of 233U as the incubation period increases, and eventually the extraction behavior of the 233U spike will be congruent to contaminant U that has been associated with sediment for decades. Following 1 week, 1 month, and 1 year incubation periods, sediment extractions were performed using either batch or dynamic (sediment column flow) chemical extraction techniques. Overall, extraction of U from sediment using batch extraction was less complicated to conduct compared to dynamic extraction, but dynamic extraction could distinguish the range of U forms associated with sediment which are eluted at different times.

A Short History of Waste Management at the Hanford Site

International Nuclear Information System (INIS)

Gephart, Roy E.

2010-01-01

The world's first full-scale nuclear reactors and chemical reprocessing plants built at the Hanford Site in the desert of eastern Washington State produced two-thirds of the plutonium generated in the United States for nuclear weapons. Operating these facilities also created large volumes of radioactive and chemical waste, some of which was released into the environment exposing people who lived downwind and downstream. Hanford now contains the largest accumulation of nuclear waste in the Western Hemisphere. Hanford's last reactor shut down in 1987 followed by closure of the last reprocessing plant in 1990. Today, Hanford's only mission is cleanup. Most onsite radioactive waste and nuclear material lingers inside underground tanks or storage facilities. About half of the chemical waste remains in tanks while the rest persists in the soil, groundwater, and burial grounds. Six million dollars each day, or nearly two billion dollars each year, are spent on waste management and cleanup activities. There is significant uncertainty in how long cleanup will take, how much it will cost, and what risks will remain for future generations. This paper summarizes portions of the waste management history of the Hanford Site published in the book 'Hanford: A Conversation about Nuclear Waste and Cleanup.'

Washing and caustic leaching of Hanford tank sludges

International Nuclear Information System (INIS)

Lumetta, G.J.; Rapko, B.M.; Colton, N.G.

1994-01-01

Methods are being developed to treat and dispose of large volumes of radioactive wastes stored in underground tanks at the U.S. Department of Energy's Hanford Site. The wastes will be partitioned into high-level waste (HLW) and low-level waste (LLW) fractions. The HLW will be vitrified into borosilicate glass and disposed of in a geologic repository, while the LLW will be immobilized in a glass matrix and will likely be disposed of by shallow burial at the Hanford Site. The wastes must be pretreated to reduce the volume of the HLW fraction, so that vitrification and disposal costs can be minimized. The current baseline process for pretreating Hanford tank sludges is to leach the sludge under caustic conditions, then remove the solubilized components of the sludge by water washing. Tests of this method have been performed with samples taken from several different tanks at Hanford. The results of these tests are presented in terms of the composition of the sludge before and after leaching. X-ray diffraction and scanning electron microscopy coupled with electron dispersive x-ray techniques have been used to identify the phases in the untreated and treated sludges

Control of radon daughters in underground mining

International Nuclear Information System (INIS)

Swent, L.W.

1983-01-01

This paper discusses technical developments that may enable uranium mine operators to improve engineering controls of radon daughter concentrations in mines, and developments in regulatory controls. The origin of radon daughters in underground mines is explained. The procedure for sampling and determining the concentration of alpha radiation in sampled air is reviewed. The principal technical development in the last few years has been the perfection and use of a class of meters which determine radon daughter concentrations in an air sample in a matter of two or three minutes without any aging period. A number of underground uranium mine operators are now using ''instant'' type meters and the Mine Safety and Health Administration (MSHA) has approved their use in a number of mines. The difficulty experienced by uranium mine operators in complying with a MSHA regulation which requires that no person be exposed to radon daughter concentrations exceeding 1 Working Level (WL) in any active working place is discussed

Glass forms for immobilization of Hanford wastes

International Nuclear Information System (INIS)

Schulz, W.W.; Dressen, A.L.; Hobbick, C.W.; Babad, H.

1975-03-01

Approximately 140 million liters of solid salt cake (mainly NaNO 3 ), produced by evaporation of aged alkaline high-level liquid wastes, will be stored in underground tanks when the present Hanford Waste Management Program is completed in the early 1980's. At this time also, large volumes of various other solid radioactive wastes (sludges, excavated Pu-contaminated soil, and doubly encapsulated 137 CsCl and 90 SrF 2 ) will be stored on the Hanford Reservation. All these solid wastes can be converted to immobile silicate and aluminosilicate glasses of low water leachability by melting them at 1100 0 to 1400 0 C with appropriate amounts of basalt (or sand) and other glass-formers such as B 2 O 3 or CaO. Reviewed in this paper are formulations and other melt conditions used successfully in batch tests to make glasses from actual and synthetic wastes; leachability and other properties of these glasses show them to be satisfactory vehicles for immobilization of the Hanford wastes. (U.S.)

Comparison of radon-daughter exposures calculated for US- underground uranium miners based on MSHA and company records

International Nuclear Information System (INIS)

Cooper, W.E.

1981-01-01

How accurate are past and present employee radon-daughter exposure records of underground uranium miners employed in the United States. This often-debated question is essential for future substantiation of safe exposure limits. An apparent discrepancy between company-reported exposures and Mining Enforcement and Safety Administration (MESA) projected exposures was detected in 1977. For these reasons a need for an updated comparison of these exposure data was indicated. This paper gives some of the conclusions of the earlier study and compares more recent exposure records compiled by the Atomic Industrial Forum, Inc., with projected exposures based on sampling by Federal mine inspectors

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

241-CX-70, 241-CX-71, and 241-CX-72 underground storage tanks at the strontium semiworks facility supplemental information to the Hanford Facility Contingency Plan

International Nuclear Information System (INIS)

Ingle, S.J.

1996-03-01

This document is a unit-specific contingency plan for the underground storage tanks at the Strontium Semiworks Facility and is intended to be used as a supplement to the Hanford Facility Contingency Plan. This unit-specific plan is to be used to demonstrate compliance with the contingency plan requirements of WAC 173-303 for certain Resource Conservation and Recovery Act of 1976 (RCRA) waste management units. Radioactive material is contained in three underground storage tanks: 241-CX-70, 241-CX-71, and 241-CX-72. Tank 241-CX-70 has been emptied, except for residual quantities of waste, and has been classified as an elementary neutralization tank under the RCRA. Tanks 241-CX-71 and 241-CX-72 contain radioactive and Washington State-only dangerous waste material, but do not present a significant hazard to adjacent facilities, personnel, or the environment. Currently, dangerous waste management activities are not being applied at the tanks. It is unlikely that any incidents presenting hazards to public health or the environment would occur at the Strontium Semiworks Facility

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)

Radioactive waste management at the Hanford Reservation

International Nuclear Information System (INIS)

Anon.

1979-01-01

During some 30 years of plutonium production, the Hanford Reservation has accumulated large quantities of low- and high-level radioactive wastes. The high-level wastes have been stored in underground tanks, and the low-level wastes have been percolated into the soil. In recent years some programs for solidification and separation of the high-level wastes have been initiated. The Hanford waste-management system was studied by a panel of the Committee on Radioactive Waste Management of the National Academy of Sciences. The panel concluded that Hanford waste-management practices were adequate at present and for the immediate future but recommended increased research and development programs related to long-term isolation of the wastes. The panel also considered some alternatives for on-site disposal of the wastes. The Hanford Reservation was originally established for the production of plutonium for military purposes. During more than 30 years of operation, large volumes of high- and low-level radioactive wastes have been accumulated and contained at the site. The Management of these wastes has been the subject of controversy and criticism. To obtain a true technical evaluation of the Hanford waste situation, the Energy Research and Development Administration (now part of the Department of Energy) issued a contract to the National Academy of Sciences and the National Research Councilto conduct an independent review and evaluation of the Hanford waste-management practices and plans. A panel of the Committee on Radioactive Waste Management (CRWM) of the National Academy of Sciences conducted this study between the summer of 1976 and the summer of 1977. This article is a summary of the final report of that panel

Hanford waste tank cone penetrometer

International Nuclear Information System (INIS)

Seda, R.Y.

1995-12-01

A new tool is being developed to characterize tank waste at the Hanford Reservation. This tool, known as the cone penetrometer, is capable of obtaining chemical and physical properties in situ. For the past 50 years, this tool has been used extensively in soil applications and now has been modified for usage in Hanford Underground Storage tanks. These modifications include development of new ''waste'' data models as well as hardware design changes to accommodate the hazardous and radioactive environment of the tanks. The modified cone penetrometer is scheduled to be deployed at Hanford by Fall 1996. At Hanford, the cone penetrometer will be used as an instrumented pipe which measures chemical and physical properties as it pushes through tank waste. Physical data, such as tank waste stratification and mechanical properties, is obtained through three sensors measuring tip pressure, sleeve friction and pore pressure. Chemical data, such as chemical speciation, is measured using a Raman spectroscopy sensor. The sensor package contains other instrumentation as well, including a tip and side temperature sensor, tank bottom detection and an inclinometer. Once the cone penetrometer has reached the bottom of the tank, a moisture probe will be inserted into the pipe. This probe is used to measure waste moisture content, water level, waste surface moisture and tank temperature. This paper discusses the development of this new measurement system. Data from the cone penetrometer will aid in the selection of sampling tools, waste tank retrieval process, and addressing various tank safety issues. This paper will explore various waste models as well as the challenges associated with tank environment

Hanford tank residual waste - Contaminant source terms and release models

International Nuclear Information System (INIS)

Deutsch, William J.; Cantrell, Kirk J.; Krupka, Kenneth M.; Lindberg, Michael L.; Jeffery Serne, R.

2011-01-01

Highlights: → Residual waste from five Hanford spent fuel process storage tanks was evaluated. → Gibbsite is a common mineral in tanks with high Al concentrations. → Non-crystalline U-Na-C-O-P ± H phases are common in the U-rich residual. → Iron oxides/hydroxides have been identified in all residual waste samples. → Uranium release is highly dependent on waste and leachant compositions. - Abstract: Residual waste is expected to be left in 177 underground storage tanks after closure at the US Department of Energy's Hanford Site in Washington State, USA. In the long term, the residual wastes may represent a potential source of contamination to the subsurface environment. Residual materials that cannot be completely removed during the tank closure process are being studied to identify and characterize the solid phases and estimate the release of contaminants from these solids to water that might enter the closed tanks in the future. As of the end of 2009, residual waste from five tanks has been evaluated. Residual wastes from adjacent tanks C-202 and C-203 have high U concentrations of 24 and 59 wt.%, respectively, while residual wastes from nearby tanks C-103 and C-106 have low U concentrations of 0.4 and 0.03 wt.%, respectively. Aluminum concentrations are high (8.2-29.1 wt.%) in some tanks (C-103, C-106, and S-112) and relatively low ( 2 -saturated solution, or a CaCO 3 -saturated water. Uranium release concentrations are highly dependent on waste and leachant compositions with dissolved U concentrations one or two orders of magnitude higher in the tests with high U residual wastes, and also higher when leached with the CaCO 3 -saturated solution than with the Ca(OH) 2 -saturated solution. Technetium leachability is not as strongly dependent on the concentration of Tc in the waste, and it appears to be slightly more leachable by the Ca(OH) 2 -saturated solution than by the CaCO 3 -saturated solution. In general, Tc is much less leachable (<10 wt.% of the

Radiation protection in uranium mining and milling industry

International Nuclear Information System (INIS)

Raghavayya, M.

2005-01-01

The first phase of the Nuclear Fuel Cycle is exploration for uranium and the next is mining and milling of uranium ore. This phase is mostly characterised by low levels of radioactivity and radiation exposure of the workers involved. Yet it is a paradoxical truth that incidence of cancer among the work force, especially miners, due to occupational radiation exposure (from radon and decay products) has been proved only in uranium mines in the entire Nuclear Fuel Cycle. Of course such incidence occurred before the detrimental effect of radiation exposure was realised and understood. Therefore it is important to familiarise oneself with the radiation hazards prevalent in the uranium mining and milling facilities so as to take appropriate remedial measures for the protection of not only the workers but also the public at large. There are both open cast and underground uranium mines around the world. Radiation hazards are considerably less significant in open cast mines than in underground mines unless the ore grade is very high. By default therefore the discussion which ensues relates mainly to radiation hazards in underground uranium mines and associated milling operations. The discussion gives a brief outline of typical uranium mine and mining and milling operations. This is followed by a description of the radiation hazards therein and protection measures that are to be taken to minimise radiation exposure. (author)

Uranium resource technology, Seminar 3, 1980

International Nuclear Information System (INIS)

Morse, J.G.

1980-01-01

This conference proceedings contains 20 papers and 1 panel discussion on uranium mining and ore treatment, taking into account the environmental issues surrounding uranium supply. Topics discussed include: the US uranium resource base, the technology and economics of uranium recovery from phosphate resources, trends in preleash materials handling of sandstone uranium ores, groundwater restoration after in-situ uranium leaching, mitigation of the environmental impacts of open pit and underground uranium mining, remedial actions at inactive uranium mill tailings sites, environmental laws governing in-situ solution mining of uranium, and the economics of in-situ solution mining. 16 papers are indexed separately

Hanford double shell tank corrosion monitoring instrument trees

International Nuclear Information System (INIS)

Nelson, J.L.

1995-03-01

High-level nuclear wastes at the Hanford site are stored underground in carbon steel double-shell and single-shell tanks - (DSTs and SSTS). Westinghouse Hanford Company is considering installation of a prototype corrosion monitoring instrument tree in at least one DST in the summer of 1995. The instrument tree will have the ability to detect and discriminate between uniform corrosion, stress corrosion cracking (SCC), and pitting. Additional instrument trees will follow in later years. Proof-of-technology testing is currently underway for the use of commercially available electric field pattern (EFP) analysis and electrochemical noise (EN) corrosion monitoring equipment. Creative use and combinations of other existing technologies is also being considered. Successful demonstration of these technologies will be followed by the development of a Hanford specific instrument tree. The first instrument tree will incorporate one of these technologies. Subsequent trees may include both technologies, as well as a more standard assembly of corrosion coupons. Successful development of these trees will allow their application to single shell tanks and the transfer of technology to other U.S. Department of Energy (DOE) sites

Removal of radionuclides from the water-soluble fraction of Hanford nuclear defense wastes

International Nuclear Information System (INIS)

Strachan, D.M.; Schulz, W.W.

1980-01-01

The current Hanford Waste Management Program has operated since 1968 to remove the bulk of the long-lived heat emitters /sup 90/Sr and /sup 137/Cs from stored high-level wastes. The liquid waste remaining after removal of /sup 90/Sr and /sup 137/Cs is returned to underground tanks for eventual evaporation to damp solid salt cake. Approximately 95,000 m/sup 3/ of salt cake and 49,000 m/sup 3/ of ''sludge'' will eventually accumulate in approximately 50 underground single-shell tanks. One alternative for long-term management of high-level Hanford wastes involves retrieval, after a yet-to-be determined interim storage time, conversion to more immobile forms, and terminal storage in a suitable geologic repository. Another alternative for long-term management of salt cake and residual liquid involves removing most of the long-lived radionuclides and many of the shorter-lived ones from these wastes. This paper describes conditions and results of recent hot cell tests of the complete Hanford Radionuclide Removal Process. These advanced tests, made with actual residual liquid containing large concentrations of ethylenediaminetetracetic acid (EDTA) and other organic compounds, provided a rigorous and convincing proof of the process flowsheet. 16 refs

Water quality restoration during and after flooding of the underground Banat mines

International Nuclear Information System (INIS)

Iuhas, T.; Bragadireanu, M.; Filip, D.; Dumitrescu, N.

2001-01-01

Closing out and flooding of the underground Banat mines are priority concerns of the Uranium National Company S.A during the period 2000-2007, the economical uranium ores being exhausted after some 45 years of underground exploitation. Water quality restoration during the flooding process and after its completion was a part of a pilot project undertaken in the frame of a PHARE programme. The mines have two water treatment plants in operation with four modules with 3 ion exchange columns each, being in exploitation. The long term plans for the remediation of uranium mines will stop the Ciudanovita water treatment facility, all the underground mine waters being further pumped and treated within a single plant located at Lisava. The exploitation of the treatment plant will be ensured as long as needed, with a first foreseen period of ten years after total flooding of the Banat mines, linked with a long term environment monitoring programme. Necessary measures to be taken for ensuring the foreseen both uranium and radium separation are presented within this paper. Proposals for radium removal are present as a decision should be taken in the nearest future. (orig.)

Technical status report on environmental aspects of long-term management of high-level defense waste at the Hanford Site

International Nuclear Information System (INIS)

1980-10-01

Since 1944, radioactive wastes have accumulated at the US Department of Energy's (DOE) 1500-km 2 Hanford Site in southeastern Washington, where nine nuclear reactors have produced nuclear materials for National defense. Today, only one production reactor is still operating, but a large inventory of radioactive high-level waste (HLW), the residue from processing the spent fuel to recover plutonium and uranium, remains stored in underground tanks and in metal capsules in water basins. So that this waste will pose no significant threat to the public health and safety, it must be isolated from the biosphere for thousands of years. This document contains an evaluation of environmental impacts of four alternative methods for long-term management of these HLW. The alternatives range from continuing the present action of storing the waste near the surface of the ground to retrieving the waste and disposing of it deep underground in a mined geologic repository. The alternatives are: near-term geologic disposal of stored waste; deferred geologic disposal of in-tank waste; in situ disposal of in-tank waste; and continued present action for stored waste. The environmental impacts of the four alternatives are small relative to that radiation received from natural sources or the available natural resources in the earth

Epidemiologic studies of underground miners: New information from an old source

International Nuclear Information System (INIS)

Samet, J.

1997-01-01

Over 100 years have passed since Harting and Hesse first described an unusual pattern of thoracic malignancy in the underground metal miners of Schneeberg. It is now known that these miners had primary cancer of the lung, caused by exposure to radon progeny released into the air of the mines from the ore. The early case series of Harting and Hesse, based on the Schneeberg miners, and of Pirchan and Sikl, based on the Joachamisthal mines, have been followed by epidemiologic studies of more formal design of uranium and other underground miners exposed to radon throughout the world. These studies have confirmed the causal association of radon and its progeny with lung cancer and provided quantification of the risk of lung cancer in relation to exposure to radon progeny. These studies have also provided insights concerning the effect of radon progeny on smokers and on nonsmokers. The findings of the epidemiologic studies have provided a clear imperative for reducing exposures of miners to radon progeny. Consequently, exposures of underground uranium miners to radon progeny have been lowered substantially over the last 50 years in countries reporting exposures of underground miners. The epidemiologic studies have also documented the substantial burden of radon-caused lung cancers among miners of uranium and other ores. While the causal link of radon with lung cancer in underground miners is now established and unquestioned, the risk of radon in indoor air remains a highly controversial issue. During the last few decades, there has been increasing recognition that radon is ubiquitous in indoor environments, in some instances at concentrations as high as measured in underground mines. As a foundation for risk management, the epidemiologic evidence from underground miners has been the primary basis for estimating the risk of indoor radon

Estimating heel retrieval costs for underground storage tank waste at Hanford. Draft

International Nuclear Information System (INIS)

DeMuth, S.

1996-01-01

Approximately 100 million gallons (∼400,000 m 3 ) of existing U.S. Department of Energy (DOE) owned radioactive waste stored in underground tanks can not be disposed of as low-level waste (LLW). The current plan for disposal of UST waste which can not be disposed of as LLW is immobilization as glass and permanent storage in an underground repository. Disposal of LLW generally can be done sub-surface at the point of origin. Consequently, LLW is significantly less expensive to dispose of than that requiring an underground repository. Due to the lower cost for LLW disposal, it is advantageous to separate the 100 million gallons of waste into a small volume of high-level waste (HLW) and a large volume of LLW

Electrostatic purification of uranium mine stope atmospheres

International Nuclear Information System (INIS)

Case, G.; Phyper, J.D.; Lowe, L.M.; Chambers, D.B.

1986-01-01

Electrostatic precipitators have been and are currently being used to reduce levels of radioactive aerosols in uranium mine stope atmospheres. Historically, while the electrostatic precipitators have been reported to be successful in reducing levels of radioactive aerosols many practical problems have been encountered with their use in the underground mine environment. Electrical short circuiting appears to have been the major problem with the use of precipitators in humid underground environments. On the basis of literature reviewed for this study it seems that the problems encountered in the past can be overcome. The most likely use of a precipitator in an underground uranium mine is to treat some or all of the air immediately upstream of a work station. The possible locations and uses of a precipitator would vary from work station to work station and from mine to mine. The desirability and cost of using elctrostatic precipitators to purify the air entering a work station are application specific. SENES Consultants therefore is not recommending for or against the use of electrostatic precipitators in underground uranium mines. The information provided in this report can be used however to assist in such determinations. 72 refs

Preliminary flowsheet for the conversion of Hanford high-level waste to glass

International Nuclear Information System (INIS)

Beary, M.M.; Chick, L.A.; Ely, P.C.; Gott, S.A.

1977-06-01

The flowsheets describe a process for converting waste removed from the Hanford underground waste tanks to more immobile form. The process involves a chemical separation of the radionuclides from industrial chemicals, and then making glass from the resulting small volume of highly radioactive waste. Removal of Sr, actinides, cesium, and technetium is discussed

Summary of uncertainty estimation results for Hanford tank chemical and radionuclide inventories

International Nuclear Information System (INIS)

Ferryman, T.A.; Amidan, B.G.; Chen, G.

1998-09-01

The exact physical and chemical nature of 55 million gallons of radioactive waste held in 177 underground waste tanks at the Hanford Site is not known in sufficient detail to support safety, retrieval, and immobilization missions. The Hanford Engineering Analysis Best-Basis team has made point estimates of the inventories in each tank. The purpose of this study is to estimate probability distributions for each of the analytes and tanks for which the Hanford Best-Basis team has made point estimates. Uncertainty intervals can then be calculated for the Best-Basis inventories and should facilitate the cleanup missions. The methodology used to generate the results published in the Tank Characterization Database (TCD) and summarized in this paper is based on scientific principles, sound technical knowledge of the realities associated with the Hanford waste tanks, the chemical analysis of actual samples from the tanks, the Hanford Best-Basic research, and historical data records. The methodology builds on research conducted by Pacific Northwest National Laboratory (PNNL) over the last few years. Appendix A of this report summarizes the results of the study. The full set of results (in percentiles, 1--99) is available through the TCD, (http://twins.pnl.gov:8001)

Summary of uncertainty estimation results for Hanford tank chemical and radionuclide inventories

Energy Technology Data Exchange (ETDEWEB)

Ferryman, T.A.; Amidan, B.G.; Chen, G. [and others

1998-09-01

The exact physical and chemical nature of 55 million gallons of radioactive waste held in 177 underground waste tanks at the Hanford Site is not known in sufficient detail to support safety, retrieval, and immobilization missions. The Hanford Engineering Analysis Best-Basis team has made point estimates of the inventories in each tank. The purpose of this study is to estimate probability distributions for each of the analytes and tanks for which the Hanford Best-Basis team has made point estimates. Uncertainty intervals can then be calculated for the Best-Basis inventories and should facilitate the cleanup missions. The methodology used to generate the results published in the Tank Characterization Database (TCD) and summarized in this paper is based on scientific principles, sound technical knowledge of the realities associated with the Hanford waste tanks, the chemical analysis of actual samples from the tanks, the Hanford Best-Basic research, and historical data records. The methodology builds on research conducted by Pacific Northwest National Laboratory (PNNL) over the last few years. Appendix A of this report summarizes the results of the study. The full set of results (in percentiles, 1--99) is available through the TCD, (http://twins.pnl.gov:8001).

Radon exposure in selected underground touring routes in Poland

International Nuclear Information System (INIS)

Olszewski, J.; Chruscielewski, W.; Jankowski, J.

2006-01-01

The radioactive elements abounding in the natural environment cause that the whole human population is exposed to radiation. In Poland, mean gamma radiation dose power is 45.4 n Gy h -1 , while atmospheric radon concentration is 4.4 Bq m -3 [1]. In closed rooms, where radon tends to accumulate, the concentrations may be many times higher.Underground touring routes located in caves, mines, ancient cellars, vaults may accumulate radon at concentrations several thousand times exceeding its atmospheric levels. Studies on natural radioactivity in underground touring routes, with particular reference to caves, have continued worldwide since the 80's. Current register of underground touring routes in Poland comprises over 30 items, which include caves (e.g. Niedzwiedzia), mines (Wieliczka), cellars and underground stores (Opatow City vaults) and military objects (underground factories of Walim). The Nofer Institute of Occupational Medicine has for several years already continued determinations of periodical mean radon concentrations in four underground touring routes (starting date in parentheses): Niedzwiedzia Cave (1995); Kowary Drifts closed uranium mine (2001); closed uranium mine in Kletno (2004); Zloty Stok closed gold mine (2004); Osowka underground city in Gluszyca (2004).The results of our determinations of radon concentrations at five selected touring routes lead to the following conclusions. 1. The exposure in the Kowary Drifts touring route is at the level of 5% of the recommended maximum annual admissible limit of 20 mSv. 2. It is assessed that workers of the touring routes where exposures are estimated from the measured concentrations and the time spent underground may receive doses ranging from 0.01 to 5 mSv. (N.C.)

Radon exposure in selected underground touring routes in Poland

Energy Technology Data Exchange (ETDEWEB)

Olszewski, J.; Chruscielewski, W.; Jankowski, J. [Nofer Institute of Occupational Medicine, Dept. of Radiation Protection, Lodz (Poland)

2006-07-01

The radioactive elements abounding in the natural environment cause that the whole human population is exposed to radiation. In Poland, mean gamma radiation dose power is 45.4 n Gy h{sup -1}, while atmospheric radon concentration is 4.4 Bq m{sup -3} [1]. In closed rooms, where radon tends to accumulate, the concentrations may be many times higher.Underground touring routes located in caves, mines, ancient cellars, vaults may accumulate radon at concentrations several thousand times exceeding its atmospheric levels. Studies on natural radioactivity in underground touring routes, with particular reference to caves, have continued worldwide since the 80's. Current register of underground touring routes in Poland comprises over 30 items, which include caves (e.g. Niedzwiedzia), mines (Wieliczka), cellars and underground stores (Opatow City vaults) and military objects (underground factories of Walim). The Nofer Institute of Occupational Medicine has for several years already continued determinations of periodical mean radon concentrations in four underground touring routes (starting date in parentheses): Niedzwiedzia Cave (1995); Kowary Drifts closed uranium mine (2001); closed uranium mine in Kletno (2004); Zloty Stok closed gold mine (2004); Osowka underground city in Gluszyca (2004).The results of our determinations of radon concentrations at five selected touring routes lead to the following conclusions. 1. The exposure in the Kowary Drifts touring route is at the level of 5% of the recommended maximum annual admissible limit of 20 mSv. 2. It is assessed that workers of the touring routes where exposures are estimated from the measured concentrations and the time spent underground may receive doses ranging from 0.01 to 5 mSv. (N.C.)

U for uranium

International Nuclear Information System (INIS)

Anon.

1982-01-01

The Beisa Mine is unique in South Africa - it is the only underground mine with uranium as its main product and gold as a by-product. At the rate of 1,2 Mt/a, the life of Beisa is estimated on 26 years. Beisa's metallurgical plant is designed to handle initially a monthly throughput of 100 000t of ore, from which uranium, gold and silver will be extracted

PROGRESS WITH K BASINS SLUDGE RETRIEVAL STABILIZATION & PACKAGING AT THE HANFORD NUCLEAR SITE

Energy Technology Data Exchange (ETDEWEB)

KNOLLMEYER, P.M.; PHILLIPS, C; TOWNSON, P.S.

2006-01-30

This paper shows how Fluor Hanford and BNG America have combined nuclear plant skills from the U.S. and the U.K. to devise methods to retrieve and treat the sludge that has accumulated in K Basins at the Hanford Site over many years. Retrieving the sludge is the final stage in removing fuel and sludge from the basins to allow them to be decontaminated and decommissioned, so as to remove the threat of contamination of the Columbia River. A description is given of sludge retrieval using vacuum lances and specially developed nozzles and pumps into Consolidation Containers within the basins. The special attention that had to be paid to the heat generation and potential criticality issues with the irradiated uranium-containing sludge is described. The processes developed to re-mobilize the sludge from the Consolidation Containers and pump it through flexible and transportable hose-in-hose piping to the treatment facility are explained with particular note made of dealing with the abrasive nature of the sludge. The treatment facility, housed in an existing Hanford building, is described, and the uranium-corrosion and grout packaging processes explained. The uranium corrosion process is a robust, tempered process very suitable for dealing with a range of differing sludge compositions. Optimization and simplification of the original sludge corrosion process design is described and the use of transportable and reusable equipment is indicated. The processes and techniques described in the paper are shown to have wide applicability to nuclear cleanup.

Overview of the spent nuclear fuel project at Hanford

International Nuclear Information System (INIS)

Daily, J.L.

1995-02-01

The Spent Nuclear Fuel Project's mission at Hanford is to open-quotes Provide safe, economic and environmentally sound management of Hanford spent nuclear fuel in a manner which stages it to final disposition.close quotes The inventory of spent nuclear fuel (SNF) at the Hanford Site covers a wide variety of fuel types (production reactor to space reactor) in many facilities (reactor fuel basins to hot cells) at locations all over the Site. The 2,129 metric tons of Hanford SNF represents about 80% of the total US Department of Energy (DOE) inventory. About 98.5% of the Hanford SNF is 2,100 metric tons of metallic uranium production reactor fuel currently stored in the 1950s vintage K Basins in the 100 Area. This fuel has been slowly corroding, generating sludge and contaminating the basin water. This condition, coupled with aging facilities with seismic vulnerabilities, has been identified by several groups, including stakeholders, as being one of the most urgent safety and environmental concerns at the Hanford Site. As a direct result of these concerns, the Spent Nuclear Fuel Project was recently formed to address spent fuel issues at Hanford. The Project has developed the K Basins Path Forward to remove fuel from the basins and place it in dry interim storage. Alternatives that addressed the requirements were developed and analyzed. The result is a two-phased approach allowing the early removal of fuel from the K Basins followed by its stabilization and interim storage consistent with the national program

Hanford Engineer Works technical manual

Energy Technology Data Exchange (ETDEWEB)

1944-05-01

The uranium metal, as discharged from the piles in the 100 Areas, contains the alpha emitting product, plutonium, in concentration in the neighborhood of 150--250 grams per metric ton, along with similar amounts of beta and gamma fission elements. It is the purpose of the Separations Plant to effect the separation of this product from the uranium metal and fission elements, and to prepare a concentrated, relatively pure solution of plutonium nitrate as the final product of the Hanford Plant. This section of the manual discusses the chemistry of the separations process, describes the buildings and equipment provided for carrying out the various steps in the operation, and presents the detailed operating procedures used. There are included, in many instances, references to other documents presenting a more detailed view of a specific point in the process.

Laboratory characterization and vitrification of Hanford radioactive high-level waste

International Nuclear Information System (INIS)

Tingey, J.M.; Elliott, M.L.; Larson, D.E.; Morrey, E.V.

1991-05-01

Radioactive high-level wastes generated at the Department of Energy's Hanford Site are stored in underground carbon steel tanks. Two double-shell tanks contain neutralized current acid waste (NCAW) from the reprocessing of irradiated nuclear fuel in the Plutonium and Uranium Extraction (PUREX) Plant. The tanks were sampled for characterization and waste immobilization process/product development. The high-level waste generated in PUREX was denitrated with sugar to form current acid waste (CAW). The CAW was ''neutralized'' to a pH of approximately 14 by adding sodium hydroxide to reduce corrosion of the tanks. This ''neutralized'' waste is called Neutralized Current Acid Waste. Both precipitated solids and liquids are stored in the NCAW waste tanks. The NCAW contains small amounts of plutonium and most of the fission products and americium from the irradiated fuel. NCAW also contains stainless steel corrosion products, and iron and sulfate from the ferrous sulfamate reductant used in the PUREX process. The NCAW will be retrieved, pretreated, and immobilized prior to final disposal. Pretreatment consists of water washing the precipitated NCAW solids for sulfate and soluble salts removal as a waste reduction step prior to vitrification. This waste is expected to be the first waste type to be retrieved and vitrified in the Hanford Waste Vitrification Plant (HWVP). A characterization plan was developed that details the processing of the small-volume NCAW samples through retrieval, pretreatment and vitrification process steps. Physical, rheological, chemical, and radiochemical properties were measured throughout these process steps. The results of nonradioactive simulant tests were used to develop appropriate pretreatment and vitrification process steps. The processing and characterization of simulants and actual NCAW tank samples are used to evaluate the operation of these processes. 3 refs., 1 fig., 4 tabs

Electrical resistivity tomography at the DOE Hanford site

International Nuclear Information System (INIS)

Narbutovskih, S.M.; Halter, T.D.; Sweeney, M.D.; Daily, W.; Ramirez, A.L.

1996-01-01

Recent work at the DOE Hanford site has established the potential of applying Electrical Resistivity Tomography (ERT) for early leak detection under hazardous waste storage facilities. Several studies have been concluded to test the capabilities and limitations of ERT for two different applications. First, field experiments have been conducted to determine the utility of ERT to detect and map leaks from underground storage tanks during waste removal processes. Second, the use of ERT for long term vadose zone monitoring has been tested under different field conditions of depth, installation design, acquisition mode/equipment and infiltration chemistry. This work involves transferring the technology from Lawrence Livermore National Laboratory (LLNL) to the Resource Conservation and Recovery Act (RCRA) program at the DOE Hanford Site. This paper covers field training studies relevant to the second application for long term vadose zone monitoring

Uranium and environment in Kazakstan

International Nuclear Information System (INIS)

Fyodorov, G.; Bayadilov, E.; Zhelnov, V.; Akhmetov, M.; Abakumov, A.

1997-01-01

Kazakstan's data on uranium as a state report has been included for the first time in the Red Book. Therefore the report contains two large themes presented in Suggested Topics for Papers: Country report, based on the 1995 NEA/IAEA Red Book Questionnaire and environmental impact regulations. Kazakstan is considered as one of the world leaders on uranium supply. In Kazakstan there are many well known types of deposits but the main one is the sandstone-rollfront type. That type is represented by the group of deposits of the Syr-Darya uranium ore province. Deposits of that type include that main part of uranium ore of the Republic of Kazakstan and supply almost all of its uranium mining. At the large three enterprises the uranium is extracted by underground leaching. The mining method of uranium extraction is stopped. Because of the poor development of nuclear energy, Kazakstan's need for uranium is not very high. Presence of a large amount of cheap and technological uranium ores allow the Republic to export uranium. There are plans to increase uranium mining and perhaps to establish new mining facilities including joint-ventures. More than 50 uranium deposits are known in Kazakstan. During prospecting and exploitation of these deposits a large amount of rad wastes in the form of ore dumps and tailings were generated. They have a substantial influence on the environment. Moreover, near the sandstone-rollfront type uranium deposits the large amount of underground water has been contaminated by radionuclides. Special investigation of this phenomenon is necessary. In Kazakstan there are the rad waste disposal conception and contaminated earth recultivation regulations. At present ''The Rad Wastes Management Law'' is submitted for approval. (author). 2 figs

A Short History of Hanford Waste Generation, Storage, and Release

International Nuclear Information System (INIS)

Gephart, Roy E.

2003-01-01

Nine nuclear reactors and four reprocessing plants at Hanford produced nearly two-thirds of the plutonium used in the United States for government purposes . These site operations also created large volumes of radioactive and chemical waste. Some contaminants were released into the environment, exposing people who lived downwind and downstream. Other contaminants were stored. The last reactor was shut down in 1987, and the last reprocessing plant closed in 1990. Most of the human-made radioactivity and about half of the chemicals remaining onsite are kept in underground tanks and surface facilities. The rest exists in the soil, groundwater, and burial grounds. Hanford contains about 40% of all the radioactivity that exists across the nuclear weapons complex. Today, environmental restoration activities are under way.

Uranium mining and milling

International Nuclear Information System (INIS)

Floeter, W.

1976-01-01

In this report uranium mining and milling are reviewed. The fuel cycle, different types of uranium geological deposits, blending of ores, open cast and underground mining, the mining cost and radiation protection in mines are treated in the first part of this report. In the second part, the milling of uranium ores is treated, including process technology, acid and alkaline leaching, process design for physical and chemical treatment of the ores, and the cost. Each chapter is clarified by added figures, diagrams, tables, and flowsheets. (HK) [de

The Japanese aerial attack on Hanford Engineer Works

Science.gov (United States)

Clark, Charles W.

The day before the Pearl Harbor attack, December 6, 1941, the University of Chicago Metallurgical Laboratory was given four goals: design a plutonium (Pu) bomb; produce Pu by irradiation of uranium (U); extract Pu from the irradiated U; complete this in time to be militarily significant. A year later the first controlled nuclear chain reaction was attained in Chicago Pile 1 (CP-1). In January 1943, Hanford, WA was chosen as the site of the Pu factory. Neutron irradiation of 238U was to be used to make 239Pu. This was done by a larger version of CP-1, Hanford Reactor B, which went critical in September 1944. By July 1945 it had made enough Pu for two bombs: one used at the Trinity test in July; the other at Nagasaki, Japan in August. I focus on an ironic sidelight to this story: disruption of hydroelectric power to Reactor B by a Japanese fire balloon attack on March 10, 1945. This activated the costly coal-fired emergency backup plant to keep the reactor coolant water flowing, thwarting disaster and vindicating the conservative design of Hanford Engineer Works. Management of the Hanford Engineer Works in World War II, H. Thayer (ASCE Press 1996).

Modeling Hydrogen Generation Rates in the Hanford Waste Treatment and Immobilization Plant

Energy Technology Data Exchange (ETDEWEB)

Camaioni, Donald M.; Bryan, Samuel A.; Hallen, Richard T.; Sherwood, David J.; Stock, Leon M.

2004-03-29

This presentation describes a project in which Hanford Site and Environmental Management Science Program investigators addressed issues concerning hydrogen generation rates in the Hanford waste treatment and immobilization plant. The hydrogen generation rates of radioactive wastes must be estimated to provide for safe operations. While an existing model satisfactorily predicts rates for quiescent wastes in Hanford underground storage tanks, pretreatment operations will alter the conditions and chemical composition of these wastes. Review of the treatment process flowsheet identified specific issues requiring study to ascertain whether the model would provide conservative values for waste streams in the plant. These include effects of adding hydroxide ion, alpha radiolysis, saturation with air (oxygen) from pulse-jet mixing, treatment with potassium permanganate, organic compounds from degraded ion exchange resins and addition of glass-former chemicals. The effects were systematically investigated through literature review, technical analyses and experimental work.

Nuclear isotope measurement in the Hanford environment

International Nuclear Information System (INIS)

Wacker, J.F.; Stoffel, J.J.; Kelley, J.M.

1995-01-01

The Pacific Northwest Laboratory (PNL) is located at the federal government's Hanford Site in southeastern Washington State, which was built during World War II as part of the secret Manhattan Project to develop the atomic bomb. Monitoring of the Site itself and surrounding environs for Hanford-related radionuclides has been a routine part of the operations since 1944. One of the most sensitive analytical methods used is thermal ionization mass spectrometry (TIMS) with triple-sector mass spectrometers. Normal geometry instruments have an abundance sensitivity of 10 -9 for uranium while the authors' newest Triple-Sector Isotope Mass Spectrometer (TRISM), utilizing a new ion-optical design developed at PNL, has an abundance sensitivity of 10 -11 . In favorable cases, sensitivity is such that complete isotopic analyses are obtained on total samples in the femtogram range; and minor isotopes in the attogram range are measured

Tank Waste Remediation System, Hanford Site, Richland, Washington. Final environmental impact statement. Summary

International Nuclear Information System (INIS)

1996-08-01

This document analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks

Energy Technology Data Exchange (ETDEWEB)

ROGERS, C.A.

2000-02-17

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

Criticality Safety Evaluation of Hanford Site High-Level Waste Storage Tanks

International Nuclear Information System (INIS)

ROGERS, C.A.

2000-01-01

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions

Decommissioning of Division of Military Application equipment at Hanford. Summary report

International Nuclear Information System (INIS)

Raile, M.N.

1977-06-01

This report describes the successful decommissioning of plutonium-contaminated equipment used for weapon component fabrication and inspection at the Hanford Plant. Special materials, techniques, and equipment were employed during the course of the decommissioning program. Most significant was the development and design of large, double-wall fiberglassed plywood boxes for long-term (20-years, minimum) retrievable storage of the contaminated equipment in underground transuranic waste trenches

Chemical Disposition of Plutonium in Hanford Site Tank Wastes

Energy Technology Data Exchange (ETDEWEB)

Delegard, Calvin H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, Susan A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-05-07

This report examines the chemical disposition of plutonium (Pu) in Hanford Site tank wastes, by itself and in its observed and potential interactions with the neutron absorbers aluminum (Al), cadmium (Cd), chromium (Cr), iron (Fe), manganese (Mn), nickel (Ni), and sodium (Na). Consideration also is given to the interactions of plutonium with uranium (U). No consideration of the disposition of uranium itself as an element with fissile isotopes is considered except tangentially with respect to its interaction as an absorber for plutonium. The report begins with a brief review of Hanford Site plutonium processes, examining the various means used to recover plutonium from irradiated fuel and from scrap, and also examines the intermediate processing of plutonium to prepare useful chemical forms. The paper provides an overview of Hanford tank defined-waste–type compositions and some calculations of the ratios of plutonium to absorber elements in these waste types and in individual waste analyses. These assessments are based on Hanford tank waste inventory data derived from separately published, expert assessments of tank disposal records, process flowsheets, and chemical/radiochemical analyses. This work also investigates the distribution and expected speciation of plutonium in tank waste solution and solid phases. For the solid phases, both pure plutonium compounds and plutonium interactions with absorber elements are considered. These assessments of plutonium chemistry are based largely on analyses of idealized or simulated tank waste or strongly alkaline systems. The very limited information available on plutonium behavior, disposition, and speciation in genuine tank waste also is discussed. The assessments show that plutonium coprecipitates strongly with chromium, iron, manganese and uranium absorbers. Plutonium’s chemical interactions with aluminum, nickel, and sodium are minimal to non-existent. Credit for neutronic interaction of plutonium with these absorbers

Uranium Metal Analysis via Selective Dissolution

Energy Technology Data Exchange (ETDEWEB)

Delegard, Calvin H.; Sinkov, Sergey I.; Schmidt, Andrew J.; Chenault, Jeffrey W.

2008-09-10

Uranium metal, which is present in sludge held in the Hanford Site K West Basin, can create hazardous hydrogen atmospheres during sludge handling, immobilization, or subsequent transport and storage operations by its oxidation/corrosion in water. A thorough knowledge of the uranium metal concentration in sludge therefore is essential to successful sludge management and waste process design. The goal of this work was to establish a rapid routine analytical method to determine uranium metal concentrations as low as 0.03 wt% in sludge even in the presence of up to 1000-fold higher total uranium concentrations (i.e., up to 30 wt% and more uranium) for samples to be taken during the upcoming sludge characterization campaign and in future analyses for sludge handling and processing. This report describes the experiments and results obtained in developing the selective dissolution technique to determine uranium metal concentration in K Basin sludge.

New advances in processing ore and minerals underground

International Nuclear Information System (INIS)

Lloyd, P.J.D.

1979-01-01

An outline of the basis for the design of a process for the efficient concentration of gold, uranium and pyrite is carried out underground. Practical steps of comminution, concentration and classification are described and probable further development is considered

In situ characterization of Hanford K Basins fuel

Energy Technology Data Exchange (ETDEWEB)

Pitner, A.L.

1998-01-06

Irradiated N Reactor uranium metal fuel is stored underwater in the Hanford K East and K West Basins. In K East Basin, fuel is stored in open canisters and defected fuel is free to react with the basin water. In K West Basin, the fuel is stored in sealed canisters filled with water containing a corrosion inhibitor (potassium nitrite). To gain a better understanding of the physical condition of the fuel in these basins, visual surveys using high resolution underwater cameras were conducted. The inspections included detailed lift and look examinations of a number of fuel assemblies from selected canisters in each basin. These examinations formed the bases for selecting specific fuel elements for laboratory testing and analyses as prescribed in the characterization plan for Hanford K Basin Spent Nuclear Fuel.

Hanford tank clean up: A guide to understanding the technical issues

Energy Technology Data Exchange (ETDEWEB)

Gephart, R.E.; Lundgren, R.E.

1995-12-31

One of the most difficult technical challenges in cleaning up the US Department of Energy`s (DOE) Hanford Site in southeast Washington State will be to process the radioactive and chemically complex waste found in the Site`s 177 underground storage tanks. Solid, liquid, and sludge-like wastes are contained in 149 single- and 28 double-shelled steel tanks. These wastes contain about one half of the curies of radioactivity and mass of hazardous chemicals found on the Hanford Site. Therefore, Hanford cleanup means tank cleanup. Safely removing the waste from the tanks, separating radioactive elements from inert chemicals, and creating a final waste form for disposal will require the use of our nation`s best available technology coupled with scientific advances, and an extraordinary commitment by all involved. The purpose of this guide is to inform the reader about critical issues facing tank cleanup. It is written as an information resource for the general reader as well as the technically trained person wanting to gain a basic understanding about the waste in Hanford`s tanks -- how the waste was created, what is in the waste, how it is stored, and what are the key technical issues facing tank cleanup. Access to information is key to better understanding the issues and more knowledgeably participating in cleanup decisions. This guide provides such information without promoting a given cleanup approach or technology use.

Progress and future directions for remediation of Hanford facilities and contaminated sites

International Nuclear Information System (INIS)

McClain, L.K.; Nemec, J.F.

1996-01-01

A great deal of physical progress is being made in the Hanford Environmental Restoration (ER) Project, which is responsible for the portion of work at Hanford that deals with contaminated soil and groundwater, and with inactive nuclear facilities. This work accounts for 10 to 15 percent of the Hanford site budget. (Other US Department of Energy [DOE] programs and contractors are responsible for the high-level liquid waste in underground storage tanks and the spent nuclear fuel). The project open-quotes closed the circleclose quotes on environmental restoration at Hanford this summer when the Environmental Restoration Disposal Facility (ERDF) went into operation and began receiving wastes being excavated from contaminated areas in Hanford's open-quotes 100 Areaclose quotes along the Columbia River. With this milestone event, environmental restoration at Hanford now has a clear path forward: (1) Waste areas along the Columbia River have been identified, volume estimates are being refined, and excavation has started. (2) The million-cubic-yard capacity ERDF is receiving waste from excavation in the 100 Area. (3) Deactivation of the N Reactor will be completed within a year. (4) Numerous other facilities in the 100 Area are being decommissioned, eliminating hazards and reducing the costs of surveillance and maintenance (S ampersand M). (5) A demonstration of long-term protective storage for one of the reactor blocks is in progress. (6) A comprehensive groundwater treatment strategy is in place. This paper describes the Hanford ER project, the progress being made, and the management techniques that are making the project successful

78 FR 75913 - Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site...

Science.gov (United States)

2013-12-13

... site, including the disposal of Hanford's low-level radioactive waste (LLW) and mixed low-level... would be processed for disposal in Low- Level Radioactive Waste Burial Grounds (LLBGs) Trenches 31 and... treating radioactive waste from 177 underground storage tanks (149 Single-Shell Tanks [SSTs] and 28 Double...

Best-basis estimates of solubility of selected radionuclides in sludges in Hanford single-shell tanks

International Nuclear Information System (INIS)

HARMSEN, R.W.

1999-01-01

The Hanford Defined Waste (HDW) model (Rev. 4) (Agnew et al. 1997) projects inventories (as of January 1, 1994) of 46 radionuclides in the Hanford Site underground waste storage tanks. To model the distribution of the 46 radionuclides among the 177 tanks, it was necessary for Agnew et al. to estimate the solubility of each radionuclide in the various waste types originally added to the single-shell tanks. Previous editions of the HDW model used single-point solubility estimates. The work described in this report was undertaken to provide more accurate estimates of the solubility of all 46 radionuclides in the various wastes

Best-basis estimates of solubility of selected radionuclides in sludges in Hanford single-shell tanks

Energy Technology Data Exchange (ETDEWEB)

HARMSEN, R.W.

1999-02-24

The Hanford Defined Waste (HDW) model (Rev. 4) (Agnew et al. 1997) projects inventories (as of January 1, 1994) of 46 radionuclides in the Hanford Site underground waste storage tanks. To model the distribution of the 46 radionuclides among the 177 tanks, it was necessary for Agnew et al. to estimate the solubility of each radionuclide in the various waste types originally added to the single-shell tanks. Previous editions of the HDW model used single-point solubility estimates. The work described in this report was undertaken to provide more accurate estimates of the solubility of all 46 radionuclides in the various wastes.

Initial laboratory studies into the chemical and radiological aging of organic materials in underground storage tanks at the Hanford Complex

International Nuclear Information System (INIS)

Samuels, W.D.; Camaioni, D.M.; Babad, H.

1994-01-01

The underground storage tanks at the Hanford Complex contain wastes generated over many years from plutonium production and recovery processes, and mixed wastes from radiological degradation processes. The chemical changes of the organic materials used in the extraction processes have a direct bearing on several specific safety issues, including potential energy releases from these tanks. The major portion of organic materials that have been added to the tanks consists of tributyl phosphate, dibutyl phosphate, butyl alcohol, hexone (methyl isobutyl ketone), normal paraffin hydrocarbons (NPH), ethylenediaminetetraacetic acid (EDTA), hydroxyethylethylenediaminetriadetic acid (HEDTA), other complexants, and lesser quantities of ion exchange polymers and minor organic compounds. A study of how thermal and radiological processes that may have changed the composition of organic tanks constituents has been initiated after a review of the open literature revealed little information was available about the rates and products of these processes under basic pH conditions. This paper will detail the initial findings as they relate to gas generation, e.g. H 2 , CO, NH 3 , CH 4 , and to changes in the composition of the organic and inorganic components brought about by ''Aging'' processes

Examination of sludge from the Hanford K Basins fuel canisters

International Nuclear Information System (INIS)

Makenas, B.J.

1998-01-01

Samples of sludges with a high uranium content have been retrieved from the fuel canisters in the Hanford K West and K East basins. The composition of these samples contrasts markedly with the previously reported content of sludge samples taken from the K East basin floor. Chemical composition, chemical reactivity, and particle size of sludge are summarized in this paper

Field-scale model for the natural attenuation of uranium at the Hanford 300 area using high performance computing

Energy Technology Data Exchange (ETDEWEB)

Lichtner, Peter C [Los Alamos National Laboratory; Hammond, Glenn E [PNNL

2009-01-01

Three-dimensional reactive flow and transport simulations are carried out to better understand the persistence of uranium [U(VI)] at the Hanford 300 Area bordering the Columbia River. The massively parallel code PFLOTRAN developed under a DOE SciDAC-2 project is employed in the simulations. The calculations were carried out on 4096 processor cores on ORNL's Jaguar XT4 & 5 Cray supercomputers with run times on the order of 6 hours, equivalent to several years if performed on a single processor with sufficient memory. A new conceptual model is presented for understanding present-day and future attenuation rates of U(VI) at the 300 Area site. Unique to the conceptual model is the recognition of three distinct phases in the evolution of the site corresponding to: (I) initial emplacement of waste; (II) present-day conditions of slow leaching of U(VI) from the Hanford sediments; and (III) the complete removal of non-labile U(VI) from the source region. This work focuses on Phase II. Both labile and non-labile forms of U(VI) are included in the model as sorbed and mineralized forms of U(VI), respectively. The non-labile form plays an important role in providing a long-term source of U(VI) as it slowly leaches out of the Hanford sediment. Rapid fluctuations in the Columbia River stage on hourly, weekly and seasonal time scales are found to' playa major role in determining the migration behavior of U(VI). The calculations demonstrate that U(VI) is released into the Columbia River at a highly fluctuating rate in a ratchet-like behavior with nonzero U(VI) flux occurring only during flow from contaminated sediment into the river. The cumulative flux, however, is found to increase approximately linearly with time. The flow rate and U(VI) flux into the Columbia River predicted by the model is highly sensitive to the value used in the conductance boundary condition at the river-sediment interface. By fitting the conductance to the measured piezometric head at well 399

Midwest Joint Venture high-grade uranium mining

International Nuclear Information System (INIS)

Fredrickson, H.K.

1992-01-01

Midwest Joint Venture (MJV) owns a high-grade uranium deposit in northern Saskatchewan. The deposit is located too deep below surface to be mined economically by open pit methods, and as a consequence, present plans are that it will be mined by underground methods. High-grade uranium ore of the type at MJV, encased in weak, highly altered ground and with radon-rich water inflows, has not before been mined by underground methods. The test mining phase of the project, completed in 1989, had three objectives: To evaluate radiation protection requirements associated with the handling of large quantities of radon-rich water and mining high-grade uranium ore in an underground environment; to investigate the quantity and quality of water inflows into the mine; and, to investigate ground conditions in and around the ore zone as an aid in determining the production mining method to be used. With information gained from the test mining project, a mining method for the production mine has been devised. Level plans have been drawn up, ventilation system designed, pumping arrangements made and methods of ore handling considered. All this is to be done in a manner that will be safe for those doing the work underground. Some of the mining methods planned are felt to be unique in that they are designed to cope with mining problems not known to have been encountered before. New problems underground have required new methods to handle them. Remote drilling, blasting, mucking and backfilling form the basis of the planned mining method

Packaging and Disposal of a Radium-beryllium Source using Depleted Uranium Polyethylene Composite Shielding

International Nuclear Information System (INIS)

Keith Rule; Paul Kalb; Pete Kwaschyn

2003-01-01

Two, 111-GBq (3 Curie) radium-beryllium (RaBe) sources were in underground storage at the Brookhaven National Laboratory (BNL) since 1988. These sources originated from the Princeton Plasma Physics Laboratory (PPPL) where they were used to calibrate neutron detection diagnostics. In 1999, PPPL and BNL began a collaborative effort to expand the use of an innovative pilot-scale technology and bring it to full-scale deployment to shield these sources for eventual transport and burial at the Hanford Burial site. The transport/disposal container was constructed of depleted uranium oxide encapsulated in polyethylene to provide suitable shielding for both gamma and neutron radiation. This new material can be produced from recycled waste products (depleted uranium and polyethylene), is inexpensive, and can be disposed with the waste, unlike conventional lead containers, thus reducing exposure time for workers. This paper will provide calculations and information that led to the initial design of the shielding. We will also describe the production-scale processing of the container, cost, schedule, logistics, and many unforeseen challenges that eventually resulted in the successful fabrication and deployment of this shield. We will conclude with a description of the final configuration of the shielding container and shipping package along with recommendations for future shielding designs

Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume I

International Nuclear Information System (INIS)

1996-08-01

This document, Volume 1 of the Final Environmental Impact Statement, analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

Feasibility Study for the Development of a Surface Plasmon Resonance spectroscopy-based Sensor for the BNFL-Hanford

International Nuclear Information System (INIS)

Anderson, B.B.

2000-01-01

The Department of Energy must treat and dispose of large volumes of radioactive waste stored in underground storage tanks at five DOE sites. Technology development has been focused on the separation and removal of various radionuclides from the supernatant contained in the Hanford waste tanks

Assessment of the total uranium concentration in surface and underground water samples from the Caetite region, Bahia, Brazil

International Nuclear Information System (INIS)

Silva, Julia Grasiela Batista; Geraldo, Luiz Paulo; Yamazaki, Ione Makiko

2011-01-01

At the region of Caetite, BA, it is located the largest uranium mine in exploration at present days in Brazil. During the uranium extraction process, it may be having an environmental contamination by this heavy metal due to rain water and other natural transport mechanism, with potential exposition risk to the local population. The aim of this work was to investigate the total uranium concentration in surface and underground water samples collected at the Caetite region, using the nuclear track registration technique (SSNTD) in a polycarbonate plastic. A 100 mL volume of water samples were initially treated in 10 mL of HNO 3 (PA) and concentrated by evaporation at a temperature around 80 deg C. The resulting residue was diluted to a total volume of 25 mL without pass it to a filter. About 10 μL of this solution was deposited on the plastic detector surface (around 1.0 cm 2 area) together with 5 μL of a Cyastat detergent solution (5%) and evaporated under an infrared lamp. All the resulting deposits of non volatile constituents were irradiated, together with a uranium standard sample, at the IPEN-IEA-R1 (3.5 MW) nuclear reactor for approximately 3 min. After irradiations, chemical etching of the plastic detectors was carried out at 60 deg C, for 65 min. in a NaOH (6N) solution. The fission tracks were counted scanning all the deposit area of the polycarbonate plastic detector with a system consisting of an optical microscope together with a video camera and TV monitor. The average values of uranium concentrations obtained in this work ranged from (0.95±0.19) μg.L -1 to (25.60±3.3) μg.L -1 . These results were compared to values reported in the literature for water samples from other regions and discussed in terms of safe limits recommended by WHO -World Health Organization and CONAMA - Conselho Nacional do Meio Ambiente. (author)

Assessment of the total uranium concentration in surface and underground water samples from the Caetite region, Bahia, Brazil

Energy Technology Data Exchange (ETDEWEB)

Silva, Julia Grasiela Batista; Geraldo, Luiz Paulo [Centro Universitario da Fundacao Educacional de Barretos (UNIFEB), (SP) (Brazil); Yamazaki, Ione Makiko [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

At the region of Caetite, BA, it is located the largest uranium mine in exploration at present days in Brazil. During the uranium extraction process, it may be having an environmental contamination by this heavy metal due to rain water and other natural transport mechanism, with potential exposition risk to the local population. The aim of this work was to investigate the total uranium concentration in surface and underground water samples collected at the Caetite region, using the nuclear track registration technique (SSNTD) in a polycarbonate plastic. A 100 mL volume of water samples were initially treated in 10 mL of HNO{sub 3} (PA) and concentrated by evaporation at a temperature around 80 deg C. The resulting residue was diluted to a total volume of 25 mL without pass it to a filter. About 10 {mu}L of this solution was deposited on the plastic detector surface (around 1.0 cm{sup 2} area) together with 5 {mu}L of a Cyastat detergent solution (5%) and evaporated under an infrared lamp. All the resulting deposits of non volatile constituents were irradiated, together with a uranium standard sample, at the IPEN-IEA-R1 (3.5 MW) nuclear reactor for approximately 3 min. After irradiations, chemical etching of the plastic detectors was carried out at 60 deg C, for 65 min. in a NaOH (6N) solution. The fission tracks were counted scanning all the deposit area of the polycarbonate plastic detector with a system consisting of an optical microscope together with a video camera and TV monitor. The average values of uranium concentrations obtained in this work ranged from (0.95{+-}0.19) {mu}g.L{sup -1} to (25.60{+-}3.3) {mu}g.L{sup -1}. These results were compared to values reported in the literature for water samples from other regions and discussed in terms of safe limits recommended by WHO -World Health Organization and CONAMA - Conselho Nacional do Meio Ambiente. (author)

Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

International Nuclear Information System (INIS)

Peeler, D.

1999-01-01

'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'

Extraction of technetium from simulated Hanford tank wastes

International Nuclear Information System (INIS)

Chaiko, D.J.; Vojta, Y.; Takeuchi, M.

1993-01-01

Aqueous biphasic separation systems are being developed for the treatment of liquid radioactive wastes. These extraction systems are based on the use of polyethylene glycols (PEGs) for the selective extraction and recovery of long-lived radionuclides, such as 129 I, 75 Se, and 99 Tc, from caustic solutions containing high concentrations of nitrate, nitrite, and carbonate. Because of the high ionic strengths of supernatant liquids in Hanford underground storage tanks, aqueous biphasic systems can be generated by simply adding aqueous PEG solutions directly to the waste solution. In the process, anionic species like I - and TcO 4 - are selectively transferred to the less dense PEG phase. The partition coefficient for a wide range of inorganic cations and anions, such as sodium, potassium, aluminum, nitrate, nitrate, and carbonate, are all less than one. The authors present experimental data on extraction of technetium from several simulated Hanford tank wastes at 25 degree and 50 degree C

First generation long-reach manipulator for retrieval of waste from Hanford single-shell tanks

International Nuclear Information System (INIS)

Gibbons, P.W.; McDaniel, L.B.

1994-10-01

The US Department of Energy, Richland Operations Office, has established the Tank Waste Remediation System to resolve environmental and safety issues related to underground waste-storage tanks at the Hanford Site. The Tank Waste Remediation System has identified the use of an advanced-technology, long-reach manipulator system as a low-water-addition retrieval alternative to past-practice sluicing

Use of electrical imaging and distributed temperature sensing methods to characterize surface water–groundwater exchange regulating uranium transport at the Hanford 300 Area, Washington

Science.gov (United States)

Slater, Lee D.; Ntarlagiannis, Dimitrios; Day-Lewis, Frederick D.; Mwakanyamale, Kisa; Versteeg, Roelof J.; Ward, Andy; Strickland, Christopher; Johnson, Carole D.; Lane, John W.

2010-01-01

We explored the use of continuous waterborne electrical imaging (CWEI), in conjunction with fiber‐optic distributed temperature sensor (FO‐DTS) monitoring, to improve the conceptual model for uranium transport within the Columbia River corridor at the Hanford 300 Area, Washington. We first inverted resistivity and induced polarization CWEI data sets for distributions of electrical resistivity and polarizability, from which the spatial complexity of the primary hydrogeologic units was reconstructed. Variations in the depth to the interface between the overlying coarse‐grained, high‐permeability Hanford Formation and the underlying finer‐grained, less permeable Ringold Formation, an important contact that limits vertical migration of contaminants, were resolved along ∼3 km of the river corridor centered on the 300 Area. Polarizability images were translated into lithologic images using established relationships between polarizability and surface area normalized to pore volume (Spor). The FO‐DTS data recorded along 1.5 km of cable with a 1 m spatial resolution and 5 min sampling interval revealed subreaches showing (1) temperature anomalies (relatively warm in winter and cool in summer) and (2) a strong correlation between temperature and river stage (negative in winter and positive in summer), both indicative of reaches of enhanced surface water–groundwater exchange. The FO‐DTS data sets confirm the hydrologic significance of the variability identified in the CWEI and reveal a pattern of highly focused exchange, concentrated at springs where the Hanford Formation is thickest. Our findings illustrate how the combination of CWEI and FO‐DTS technologies can characterize surface water–groundwater exchange in a complex, coupled river‐aquifer system.

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

International Nuclear Information System (INIS)

Tan Chenglong

2004-01-01

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

Inherently safe in situ uranium recovery

Science.gov (United States)

Krumhansl, James L; Brady, Patrick V

2014-04-29

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

Static internal pressure capacity of Hanford Single-Shell Waste Tanks

Energy Technology Data Exchange (ETDEWEB)

Julyk, L.J.

1994-07-19

Underground single-shell waste storage tanks located at the Hanford Site in Richland, Washington, generate gaseous mixtures that could be ignited, challenging the structural integrity of the tanks. The structural capacity of the single-shell tanks to internal pressure is estimated through nonlinear finite-element structural analyses of the reinforced concrete tank. To determine their internal pressure capacity, designs for both the million-gallon and the half-million-gallon tank are evaluated on the basis of gross structural instability.

Static internal pressure capacity of Hanford Single-Shell Waste Tanks

International Nuclear Information System (INIS)

Julyk, L.J.

1994-01-01

Underground single-shell waste storage tanks located at the Hanford Site in Richland, Washington, generate gaseous mixtures that could be ignited, challenging the structural integrity of the tanks. The structural capacity of the single-shell tanks to internal pressure is estimated through nonlinear finite-element structural analyses of the reinforced concrete tank. To determine their internal pressure capacity, designs for both the million-gallon and the half-million-gallon tank are evaluated on the basis of gross structural instability

Trade study of leakage detection, monitoring, and mitigation technologies to support Hanford single-shell waste retrieval

International Nuclear Information System (INIS)

Hertzel, J.S.

1996-03-01

The U.S. Department of Energy has established the Tank Waste Remediation System to safely manage and dispose of low-level, high-level, and transuranic wastes currently stored in underground storage tanks at the Hanford Site in Eastern Washington. This report supports the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone No. M-45-08-T01 and addresses additional issues regarding single-shell tank leakage detection, monitoring, and mitigation technologies and provide an indication of the scope of leakage detection, monitoring, and mitigation activities necessary to support the Tank Waste Remedial System Initial Single-shell Tank Retrieval System project

Hanford double shell tank corrosion monitoring instrument tree prototype

International Nuclear Information System (INIS)

Nelson, J.L.; Edgemon, G.L.; Ohl, P.C.

1995-11-01

High-level nuclear wastes at the Hanford site are stored underground in carbon steel double-shell and single-shell tanks (DSTs and SSTs). The installation of a prototype corrosion monitoring instrument tree into DST 241-A-101 was completed in December 1995. The instrument tree has the ability to detect and discriminate between uniform corrosion, pitting, and stress corrosion cracking (SCC) through the use of electrochemical noise measurements and a unique stressed element, three-electrode probe. The tree itself is constructed of AISI 304L stainless steel (UNS S30403), with probes in the vapor space, vapor/liquid interface and liquid. Successful development of these trees will allow their application to single shell tanks and the transfer of technology to other US Department of Energy (DOE) sites. Keywords: Hanford, radioactive waste, high-level waste tanks, electrochemical noise, probes, double-shell tanks, single-shell tanks, corrosion

Underground tank remediation by use of in situ vitrification

International Nuclear Information System (INIS)

Thompson, L.E.

1991-02-01

Pacific Northwest Laboratory (PNL) is developing a remedial action technology for underground storage tanks through the adaptation of the in situ vitrification (ISV) process. The ISV process is a thermal treatment processes that was originally developed for the stabilization of contaminated soil contaminated with transuranic waste at the Hanford Site in southeastern Washington for the Department of Energy (DOE). The application of ISV to underground storage tanks represents an entirely new application of the ISV technology and is being performed in support of the DOE primarily for the Hanford site and the Oak Ridge National Laboratory (ORNL). A field scale test was conducted in September 1990 at Hanford on a small cement and stainless steel tank (1-m dia.) that contained a simulated refractory sludge representing a worst-case sludge composition. The tank design and sludge composition was based on conditions present at the ORNL. The sludge contained high concentrations of heavy metals including lead, mercury, and cadmium, and also contained high levels of stable cesium and strontium to represent the predominant radionuclide species present in the tank wastes. The test was highly successful in that the entire tank and surrounding soil was transformed into a highly leach resistant glass and crystalline block with a mass of approximately 30 tons. During the process, the metal shell of the tank forms a metal pool at the base of the molten soil. Upon cooling, the glass and metal phases were subjected to TCLP (toxic characteristic leach procedure) testing and passed the TCLP criteria. Additional sampling and analyses are ongoing to determine the bulk composition of the waste forms, the fraction of volatile or semi-volatile species released to the off-gas treatment system, and to determine whether any soil surrounding the monolith was contaminated as a result of the ISV process. 4 refs., 5 figs., 3 tabs

MANHATTAN PROJECT B REACTOR HANFORD WASHINGTON [HANFORD'S HISTORIC B REACTOR (12-PAGE BOOKLET)

Energy Technology Data Exchange (ETDEWEB)

GERBER MS

2009-04-28

The Hanford Site began as part of the United States Manhattan Project to research, test and build atomic weapons during World War II. The original 670-square mile Hanford Site, then known as the Hanford Engineer Works, was the last of three top-secret sites constructed in order to produce enriched uranium and plutonium for the world's first nuclear weapons. B Reactor, located about 45 miles northwest of Richland, Washington, is the world's first full-scale nuclear reactor. Not only was B Reactor a first-of-a-kind engineering structure, it was built and fully functional in just 11 months. Eventually, the shoreline of the Columbia River in southeastern Washington State held nine nuclear reactors at the height of Hanford's nuclear defense production during the Cold War era. The B Reactor was shut down in 1968. During the 1980's, the U.S. Department of Energy began removing B Reactor's support facilities. The reactor building, the river pumphouse and the reactor stack are the only facilities that remain. Today, the U.S. Department of Energy (DOE) Richland Operations Office offers escorted public access to B Reactor along a designated tour route. The National Park Service (NPS) is studying preservation and interpretation options for sites associated with the Manhattan Project. A draft is expected in summer 2009. A final report will recommend whether the B Reactor, along with other Manhattan Project facilities, should be preserved, and if so, what roles the DOE, the NPS and community partners will play in preservation and public education. In August 2008, the DOE announced plans to open B Reactor for additional public tours. Potential hazards still exist within the building. However, the approved tour route is safe for visitors and workers. DOE may open additional areas once it can assure public safety by mitigating hazards.

Methodology for uncertainty estimation of Hanford tank chemical and radionuclide inventories and concentrations

International Nuclear Information System (INIS)

Chen, G.; Ferryman, T.A.; Remund, K.M.

1998-02-01

The exact physical and chemical nature of 55 million gallons of toxic waste held in 177 underground waste tanks at the Hanford Site is not known with sufficient detail to support the safety, retrieval, and immobilization missions presented to Hanford. The Hanford Best Basis team has made point estimates of the inventories in each tank. The purpose of this study is to estimate probability distributions for each of the 71 analytes and 177 tanks that the Hanford Best Basis team has made point estimates for. This will enable uncertainty intervals to be calculated for the Best Basis inventories and should facilitate the safety, retrieval, and immobilization missions. Section 2 of this document describes the overall approach used to estimate tank inventory uncertainties. Three major components are considered in this approach: chemical concentration, density, and waste volume. Section 2 also describes the two different methods used to evaluate the tank wastes in terms of sludges and in terms of supernatant or saltcakes. Sections 3 and 4 describe in detail the methodology to assess the probability distributions for each of the three components, as well as the data sources for implementation. The conclusions are given in Section 5

Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

Energy Technology Data Exchange (ETDEWEB)

Peeler, D.

1999-06-22

'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'

Characterization plan for Hanford spent nuclear fuel

International Nuclear Information System (INIS)

Abrefah, J.; Thornton, T.A.; Thomas, L.E.; Berting, F.M.; Marschman, S.C.

1994-12-01

Reprocessing of spent nuclear fuel (SNF) at the Hanford Site Plutonium-Uranium Extraction Plant (PUREX) was terminated in 1972. Since that time a significant quantity of N Reactor and Single-Pass Reactor SNF has been stored in the 100 Area K-East (KE) and K-West (KW) reactor basins. Approximately 80% of all US Department of Energy (DOE)-owned SNF resides at Hanford, the largest portion of which is in the water-filled KE and KW reactor basins. The basins were not designed for long-term storage of the SNF and it has become a priority to move the SNF to a more suitable location. As part of the project plan, SNF inventories will be chemically and physically characterized to provide information that will be used to resolve safety and technical issues for development of an environmentally benign and efficient extended interim storage and final disposition strategy for this defense production-reactor SNF

Short-term radon activity concentration changes along the Underground Educational Tourist Route in the Old Uranium Mine in Kletno (Sudety Mts., SW Poland)

International Nuclear Information System (INIS)

Fijałkowska-Lichwa, Lidia

2014-01-01

Short-term 222 Rn activity concentration changes along the Underground Educational Tourist Route in the Old Uranium Mine in Kletno were studied, based on continuous measurements conducted between 16 May 2008 and 15 May 2010. The results were analysed in the context of numbers of visitors arriving at the facility in particular seasons and the time per day spent inside by staff and visitors. This choice was based on partially published earlier findings (Fijałkowska-Lichwa and Przylibski, 2011). Results for the year 2009 were analysed in depth, because it is the only period of observation covering a full calendar year. The year 2009 was also chosen for detailed analysis of short-term radon concentration changes, because in each period of this year (hour, month, season) fluctuations of noted values were the most visible. Attention has been paid to three crucial issues linked to the occurrence and behaviour of radon and to the radiological protection of workers and visitors at the tourist route in Kletno. The object of study is a complex of workings in a former uranium mine situated within a metamorphic rock complex in the most radon-prone area in Poland. The facility has been equipped with a mechanical ventilation system, which is turned on after the closing time and at the end of the working day for the visitor service staff, i.e. after 6 p.m. Short-term radon activity concentration changes along the Underground Educational Tourist Route in the Old Uranium Mine in Kletno are related to the activity of the facility's mechanical ventilation. Its inactivity in the daytime results in the fact that the highest values of 222 Rn activity concentration are observed at the time when the facility is open to visitors, i.e. between 10 a.m. and 6 p.m. The improper usage of the mechanical ventilation system is responsible for the extremely unfavourable working conditions, which persist in the facility for practically all year. The absence of appropriate radiological

Fuel-element failures in Hanford single-pass reactors 1944--1971

Energy Technology Data Exchange (ETDEWEB)

Gydesen, S.P.

1993-07-01

The primary objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of emissions since 1944 from the US Department of Energy`s (DOE) Hanford Site near Richland, Washington. To estimate the doses, the staff of the Source Terms Task use operating information from historical documents to approximate the radioactive emissions. One source of radioactive emissions to the Columbia River came from leaks in the aluminum cladding of the uranium metal fuel elements in single-pass reactors. The purpose of this letter report is to provide photocopies of the documents that recorded these failures. The data from these documents will be used by the Source Terms Task to determine the contribution of single-pass reactor fuel-element failures to the radioactivity of the reactor effluent from 1944 through 1971. Each referenced fuel-element failure occurring in the Hanford single-pass reactors is addressed. The first recorded failure was in 1948, the last in 1970. No records of fuel-element failures were found in documents prior to 1948. Data on the approximately 2000 failures which occurred during the 28 years (1944--1971) of Hanford single-pass reactor operations are provided in this report.

TANK FARM RETRIEVAL LESSONS LEARNED AT THE HANFORD SITE

International Nuclear Information System (INIS)

DODD RA

2008-01-01

One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the U. S. Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60 percent of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons of this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste to the surrounding soil. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring this waste to the DST system. Retrieval of SST saltcake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. Regulatory requirements for SST waste retrieval and tank farm closure are established in the Hanford Federal Facility Agreement and Consent Order (HFFACO), better known as the TriParty Agreement, or TPA. The HFFACO was signed by the DOE, the State of Washington Department of Ecology (Ecology), and U. S. Environmental Protection Agency (EPA) and requires retrieval of as much waste as technically possible, with waste residues not to exceed 360 fe in 530,000 gallon or larger tanks; 30 fe in 55,000 gallon or smaller tanks; or the limit of waste retrieval technology, whichever is less. If residual waste volume requirements cannot be achieved, then HFFACO Appendix H provisions can be invoked to request Ecology and EPA approval of an

Hanford Immobilized Low Activity Waste (ILAW) Performance Assessment 2001 Version [Formerly DOE/RL-97-69] [SEC 1 & 2

Energy Technology Data Exchange (ETDEWEB)

MANN, F.M.

2000-08-01

The Hanford Immobilized Low-Activity Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-activity fraction of waste presently contained in Hanford Site tanks. The tank waste is the byproduct of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste is stored in underground single- and double-shell tanks. The tank waste is to be retrieved, separated into low-activity and high-level fractions, and then immobilized by vitrification. The US. Department of Energy (DOE) plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at the Hanford Site until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to modify the current Disposal Authorization Statement for the Hanford Site that would allow the following: construction of disposal trenches; and filling of these trenches with ILAW containers and filler material with the intent to dispose of the containers.

Environmental monitoring at Hanford by the state of Washington

International Nuclear Information System (INIS)

Conklin, A.W.; Mooney, R.R.; Erickson, J.L.

1990-01-01

The Department of Social and Health Services' Office of Radiation Protection (ORP), Washington State's radiation control agency, has a mandate to protect the public from radiation. In 1985, ORP was instructed by the legislature to establish a statewide environmental radiological base line, beginning with Hanford, to verify federal environmental programs, and to enforce federal and state Clean Air Acts. The primary mission of the agency is to protect public health by active involvement in Hanford monitoring and oversight. The state's program was designed not to duplicate but to supplement existing programs and to identify any sampling gaps or problems. Split, side-by-side, and independent samples are collected, with analysis performed by the state's own laboratory. Media sampled have included surface and drinking water, seep and ground water, fruits and vegetables, milk, soils, and air particulates; ambient radiation levels have been determined. Special activities have included split sampling of river seeps with multiple agencies, preliminary dose assessment of early Hanford releases, investigations of 129 I in the environment and in Franklin County drinking water, verification of U.S. Department of Energy (DOE) data on erroneous alarms at the Hanford Plutonium Uranium Extraction Plant, split sampling with a DOE headquarters survey, and participation in several General Accounting Office investigations and a National Academy of Sciences review. The independence of ORP programs guarantees that the public has access to environmental data on the activities of DOE and its contractors. We will describe the interrelationship of ORP and Hanford programs and present results of ORP activities

Hanford Site background: Evaluation of existing soil radionuclide data

International Nuclear Information System (INIS)

1995-07-01

This report is an evaluation of the existing data on radiological background for soils in the vicinity of the Hanford Site. The primary purpose of this report is to assess the adequacy of the existing data to serve as a radiological background baseline for use in environmental restoration and remediation activities at the Hanford Site. The soil background data compiled and evaluated in this report were collected by the Pacific Northwest Laboratory (PNL) and Washington State Department of Health (DOH) radiation surveillance programs in southeastern Washington. These two programs provide the largest well-documented, quantitative data sets available to evaluate background conditions at the Hanford Site. The data quality objectives (DQOs) considered in this evaluation include the amount of data, number of sampling localities, spatial coverage, number and types of radionuclides reported, frequency of reporting, documentation and traceability of sampling and laboratory methods used, and comparability between sets of data. Although other data on soil radionuclide abundances around the Hanford Site exist, they are generally limited in scope and lack the DQOs necessary for consideration with the PNL and DOH data sets. Collectively, these two sources provide data on the activities of 25 radionuclides and four other parameters (gross alpha, gross beta, total uranium, and total thorium). These measurements were made on samples from the upper 2.5 cm of soil at over 70 localities within the region

Uranium production and the environment in Kazakhstan

International Nuclear Information System (INIS)

Fyodorov, G.V.

2002-01-01

The production of uranium from open-pit and underground mines in Kazakhstan has terminated. Currently, uranium is extracted in Kazakhstan only by the In Situ Leaching (ISL) method. This method has a number of economical and ecological advantages. During a short period in the 70s-80s, Kazakhstan created a firm basis for developing uranium extraction by the ISL method. Now more than half of the world's uranium reserves amenable to the ISL method are located in Kazakhstan. By 2005, a significant increase in uranium production is planned. Thereby, Kazakhstan has the ability to grow into a world leader in uranium extraction through a lower cost and low environmental impact operations using the ISL method. (author)

A Review of Iron Phosphate Glasses and Recommendations for Vitrifying Hanford Waste

Energy Technology Data Exchange (ETDEWEB)

Delbert E. Ray; Chandra S. Ray

2013-11-01

This report contains a comprehensive review of the research conducted, world-wide, on iron phosphate glass over the past ~30 years. Special attention is devoted to those iron phosphate glass compositions which have been formulated for the purpose of vitrifying numerous types of nuclear waste, with special emphasis on the wastes stored in the underground tanks at Hanford WA. Data for the structural, chemical, and physical properties of iron phosphate waste forms are reviewed for the purpose of understanding their (a) outstanding chemical durability which meets all current DOE requirements, (b) high waste loadings which can exceed 40 wt% (up to 75 wt%) for several Hanford wastes, (c) low melting temperatures, can be as low as 900°C for certain wastes, and (d) high tolerance for “problem” waste components such as sulfates, halides, and heavy metals (chromium, actinides, noble metals, etc.). Several recommendations are given for actions that are necessary to smoothly integrate iron phosphate glass technology into the present waste treatment plans and vitrification facilities at Hanford.

System design for retrieval of solidified high-level wastes at Hanford

International Nuclear Information System (INIS)

Wallskog, H.A.

1977-01-01

A Waste Retrieval System has been conceptually designed as a step in the process toward the demonstration of the capability to retrieve the projected 36,000,000 gallons of radioactive salt cake and sludge wastes from underground storage tanks at Hanford. This functionally complete, totally remotely operable system consists of a large mobile platform containing all of the tools and equipment necessary to recover, remove and package the wastes for transfer to an onsite processing facility

Identification of contaminants of concern in Hanford ground waters

International Nuclear Information System (INIS)

Sherwood, D.R.; Evans, J.C.; Bryce, R.W.

1990-01-01

More than 1,500 waste-disposal sites have been identified at the U.S. Department of Energy Hanford Site. At the request of the U.S. Environmental Protection Agency, these sites were aggregated into four administrative areas for listing on the National Priority List. Within the four aggregate areas, 646 inactive sites were selected for further evaluation using the Hazard Ranking System (HRS). Evaluation of inactive waste sites by HRS provided valuable insight to design a focused radiological- and hazardous-substance monitoring network. Hanford Site-wide ground-water monitoring was expanded to address not only radioactive constituents but also hazardous chemicals. The HRS scoring process considers the likelihood of ground-water contamination from past disposal practices at inactive waste sites. The network designed to monitor ground water at those facilities identified 129 I, 99 Tc, 90 Sr, uranium, chromium, carbon tetrachloride, and cyanide

Probabilistic safety assessment for Hanford high-level waste tanks

International Nuclear Information System (INIS)

MacFarlane, D.R.; Stack, D.S.; Kindinger, J.P.; Deremer, R.K.

1995-01-01

This paper gives results from the first comprehensive level-3 probabilistic safety assessment (PSA), including consideration of external events, for the Hanford tank farm (HTF). This work was sponsored by the U.S. Department of Energy/Environmental Restoration and Waste Management Division (DOE/EM). At the HTF, there are 177 underground tanks in 18 separate tank farms containing accumulated liquid/sludge/saltcake radioactive wastes from 50 yr of weapons materials production activities. The total waste volume is ∼60 million gal, containing ∼200 million Ci of radioactivity

System Planning With The Hanford Waste Operations Simulator

International Nuclear Information System (INIS)

Crawford, T.W.; Certa, P.J.; Wells, M.N.

2010-01-01

At the U. S. Department of Energy's Hanford Site in southeastern Washington State, 216 million liters (57 million gallons) of nuclear waste is currently stored in aging underground tanks, threatening the Columbia River. The River Protection Project (RPP), a fully integrated system of waste storage, retrieval, treatment, and disposal facilities, is in varying stages of design, construction, operation, and future planning. These facilities face many overlapping technical, regulatory, and financial hurdles to achieve site cleanup and closure. Program execution is ongoing, but completion is currently expected to take approximately 40 more years. Strategic planning for the treatment of Hanford tank waste is by nature a multi-faceted, complex and iterative process. To help manage the planning, a report referred to as the RPP System Plan is prepared to provide a basis for aligning the program scope with the cost and schedule, from upper-tier contracts to individual facility operating plans. The Hanford Tank Waste Operations Simulator (HTWOS), a dynamic flowsheet simulation and mass balance computer model, is used to simulate the current planned RPP mission, evaluate the impacts of changes to the mission, and assist in planning near-term facility operations. Development of additional modeling tools, including an operations research model and a cost model, will further improve long-term planning confidence. The most recent RPP System Plan, Revision 4, was published in September 2009.

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

International Nuclear Information System (INIS)

Boydell, D.W.

1979-01-01

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

Hanford tank clean up: A guide to understanding the technical issues

International Nuclear Information System (INIS)

Gephart, R.E.; Lundgren, R.E.

1995-01-01

One of the most difficult technical challenges in cleaning up the US Department of Energy's (DOE) Hanford Site in southeast Washington State will be to process the radioactive and chemically complex waste found in the Site's 177 underground storage tanks. Solid, liquid, and sludge-like wastes are contained in 149 single- and 28 double-shelled steel tanks. These wastes contain about one half of the curies of radioactivity and mass of hazardous chemicals found on the Hanford Site. Therefore, Hanford cleanup means tank cleanup. Safely removing the waste from the tanks, separating radioactive elements from inert chemicals, and creating a final waste form for disposal will require the use of our nation's best available technology coupled with scientific advances, and an extraordinary commitment by all involved. The purpose of this guide is to inform the reader about critical issues facing tank cleanup. It is written as an information resource for the general reader as well as the technically trained person wanting to gain a basic understanding about the waste in Hanford's tanks -- how the waste was created, what is in the waste, how it is stored, and what are the key technical issues facing tank cleanup. Access to information is key to better understanding the issues and more knowledgeably participating in cleanup decisions. This guide provides such information without promoting a given cleanup approach or technology use

TBP and diluent mass balances in the PUREX Plant at Hanford, 1955--1991

International Nuclear Information System (INIS)

Sederburg, J.P.; Reddick, J.A.

1994-12-01

The purpose of this report is to develop an estimate of the quantities of tributyl phosphate and diluent discharged in aqueous waste streams to the tank farms from the Hanford Purex Plant over its operating life. Purex was not the sole source of organics in the tank farms, but was a major contributor. Tributyl phosphate (TBP) and diluent, which changed from Shell E-2342 reg-sign to Soltrol-170 reg-sign and then to normal paraffin hydrocarbon (NPH), were organic chemicals used in the Purex solvent extraction process at Hanford to separate plutonium and uranium from spent nuclear fuels. This report is an estimate of the material balances for these chemicals in the Purex Plant at Hanford over its entire operating life. The Purex Plant had cold start up in November 1955 and shut down in 1990. It's process used a solution of 30 vol% TBP in diluent

Radon emanation from backfilled mill tailings in underground uranium mine.

Science.gov (United States)

Sahu, Patitapaban; Mishra, Devi Prasad; Panigrahi, Durga Charan; Jha, Vivekananda; Patnaik, R Lokeswara; Sethy, Narendra Kumar

2014-04-01

Coarser mill tailings used as backfill to stabilize the stoped out areas in underground uranium mines is a potential source of radon contamination. This paper presents the quantitative assessment of radon emanation from the backfilled tailings in Jaduguda mine, India using a cylindrical accumulator. Some of the important parameters such as (226)Ra activity concentration, bulk density, bulk porosity, moisture content and radon emanation factor of the tailings affecting radon emanation were determined in the laboratory. The study revealed that the radon emanation rate of the tailings varied in the range of 0.12-7.03 Bq m(-2) s(-1) with geometric mean of 1.01 Bq m(-2) s(-1) and geometric standard deviation of 3.39. An increase in radon emanation rate was noticed up to a moisture saturation of 0.09 in the tailings, after which the emanation rate gradually started declining with saturation due to low diffusion coefficient of radon in the saturated tailings. Radon emanation factor of the tailings varied in the range of 0.08-0.23 with the mean value of 0.21. The emanation factor of the tailings with moisture saturation level over 0.09 was found to be about three times higher than that of the absolutely dry tailings. The empirical relationship obtained between (222)Rn emanation rate and (226)Ra activity concentration of the tailings indicated a significant positive linear correlation (r = 0.95, p < 0.001). This relationship may be useful for quick prediction of radon emanation rate from the backfill material of similar nature. Copyright © 2014 Elsevier Ltd. All rights reserved.

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

Electrochemical organic destruction in support of Hanford tank waste pretreatment

International Nuclear Information System (INIS)

Lawrence, W.E.; Surma, J.E.; Gervais, K.L.; Buehler, M.F.; Pillay, G.; Schmidt, A.J.

1994-10-01

The US Department of Energy's Hanford Site in Richland, Washington, has 177 underground storage tanks that contain approximately 61 million gallons of radioactive waste. The current cleanup strategy is to retrieve the waste and separate components into high-level and low-level waste. However, many of the tanks contain organic compounds that create concerns associated with tank safety and efficiency of anticipated separation processes. Therefore, a need exists for technologies that can safely and efficiently destroy organic compounds. Laboratory-scale studies conducted during FY 93 have shown proof-of-principle for electrochemical destruction of organics. Electrochemical oxidation is an inherently safe technology and shows promise for treating Hanford complexant concentrate aqueous/ slurry waste. Therefore, in support of Hanford tank waste pretreatment needs, the development of electrochemical organic destruction (ECOD) technology has been undertaken. The primary objective of this work is to develop an electrochemical treatment process for destroying organic compounds, including tank waste complexants. Electroanalytical analyses and bench-scale flow cell testing will be conducted to evaluate the effect of anode material and process operating conditions on the rate of organic destruction. Cyclic voltammetry will be used to identify oxygen overpotentials for the anode materials and provide insight into reaction steps for the electrochemical oxidation of complexants. In addition, a bench-scale flow cell evaluation will be conducted to evaluate the influence of process operating conditions and anode materials on the rate and efficiency of organic destruction using the nonradioactive a Hanford tank waste simulant

FINAL FRONTIER AT HANFORD TACKLING THE CENTRAL PLATEAU

International Nuclear Information System (INIS)

GERBER MS

2008-01-01

The large land area in the center of the vast Department of Energy (DOE) Hanford Site in southeast Washington State is known as 'the plateau'--aptly named because its surface elevations are 250-300 feet above the groundwater table. By contrast, areas on the 585-square mile Site that border the Columbia River sit just 30-80 feet above the water table. The Central Plateau, which covers an ellipse of approximately 70 square miles, contains Hanford's radiochemical reprocessing areas--the 200 East and 200 West Areas--and includes the most highly radioactive waste and contaminated facilities on the Site. Five 'canyons' where chemical processes were used to separate out plutonium (Pu), 884 identified soil waste sites (including approximately 50 miles of solid waste burial trenches), more than 900 structures, and all of Hanford's liquid waste storage tanks reside in the Central Plateau. (Notes: Canyons is a nickname given by Hanford workers to the chemical reprocessing facilities. The 177, underground waste tanks at Hanford comprise a separate work scope and are not under Fluor's management). Fluor Hanford, a DOE prime cleanup contractor at the Site for the past 12 years, has moved aggressively to investigate Central Plateau waste sites in the last few years, digging more than 500 boreholes, test pits, direct soil 'pushes' or drive points; logging geophysical data sets; and performing electrical-resistivity scans (a non-intrusive technique that maps patterns of sub-surface soil conductivity). The goal is to identify areas of contamination areas in soil and solid waste sites, so that cost-effective and appropriate decisions on remediation can be made. In 2007, Fluor developed a new work plan for DOE that added 238 soil waste-site characterization activities in the Central Plateau during fiscal years (FYs) 2007-2010. This number represents a 50 percent increase over similar work previously done in central Hanford. Work Plans are among the required steps in the Comprehensive

Cost benefit of caustic recycle for tank waste remediation at the Hanford and Savannah River Sites

International Nuclear Information System (INIS)

DeMuth, S.

1998-01-01

The potential cost savings due to the use of caustic recycle used in conjunction with remediation of radioactive underground storage tank waste, is shown in a figure for the Hanford and Savannah River sites. Two cost savings estimates for each case have been made for Hanford, and one cost savings estimate for each case have been made for Hanford, and one cost savings estimate for each case has been made for the Savannah River site. This is due to the Hanford site remediation effort being less mature than that of Savannah River; and consequently, a range of cost savings being more appropriate for Hanford. This range of cost savings (rather than a ingle value) for each case at Hanford is due to cost uncertainties related to the LAW immobilization operation. Caustic recycle Case-1 has been defined as the sodium required to meet al identified caustic needs for the entire Site. Case-2 has been defined as the maximum sodium which can be separated from the low activity waste without precipitation of Al(OH) 3 . It has been determined that the potential cost savings at Hanford ranges from $194 M to $215 M for Case-1, and $293 M to $324 M for Case-2. The potential cost savings at Savannah River are $186 M for Case-1 and $281 M for Case-2. A discussion of the uncertainty associated with these cost savings estimates can be found in the Discussion and Conclusions section

Development of a carbonate crust on alkaline nuclear waste sludge at the Hanford site.

Science.gov (United States)

Page, Jason S; Reynolds, Jacob G; Ely, Tom M; Cooke, Gary A

2018-01-15

Hard crusts on aging plutonium production waste have hindered the remediation of the Hanford Site in southeastern Washington, USA. In this study, samples were analyzed to determine the cause of a hard crust that developed on the highly radioactive sludge during 20 years of inactivity in one of the underground tanks (tank 241-C-105). Samples recently taken from the crust were compared with those acquired before the crust appeared. X-ray diffraction and scanning electron microscopy (SEM) indicated that aluminum and uranium phases at the surface had converted from (hydr)oxides (gibbsite and clarkeite) into carbonates (dawsonite and cejkaite) and identified trona as the cementing phase, a bicarbonate that formed at the expense of thermonatrite. Since trona is more stable at lower pH values than thermonatrite, the pH of the surface decreased over time, suggesting that CO 2 from the atmosphere lowered the pH. Thus, a likely cause of crust formation was the absorption of CO 2 from the air, leading to a reduction of the pH and carbonation of the waste surface. The results presented here help establish a model for how nuclear process waste can age and can be used to aid future remediation and retrieval activities. Copyright © 2017 Elsevier B.V. All rights reserved.

Deactivation completed at historic Hanford Fuels Laboratory

Energy Technology Data Exchange (ETDEWEB)

Gerber, M.S.

1994-03-01

This report discusses deactivation work which was completed as of March 31, 1994 at the 308 Fuels Development Laboratory (FDL) at the Hanford Site near Richland, Washington. The decision to deactivate the structure, formerly known as the Plutonium Fabrication Pilot Plant (PFPP), was driven by a 1980s Department of Energy (DOE) decision that plutonium fuels should not be fabricated in areas near the Site`s boundaries, as well as by changing facility structural requirements. Inventory transfer has been followed by the cleanout and stabilization of plutonium oxide (PuO{sub 2}) and enriched uranium oxide (UO{sub 2}) residues and powders in the facility`s equipment and duct work. The Hanford Site, located in southeastern Washington state, was one of America`s primary arsenals of nuclear defense production for nearly 50 years beginning in World War II. Approximately 53 metric tons of weapons grade plutonium, over half of the national supply and about one quarter of the world`s supply, were produced at Hanford between 1944 and 1989. Today, many Site buildings are undergoing deactivation, a precursor phase to decontamination and decommissioning (D&D). The primary difference between the two activities is that equipment and structural items are not removed or torn down in deactivation. However, utilities are disconnected, and special nuclear materials (SNM) as well as hazardous and pyrophoric substances are removed from structures undergoing this process.

Deactivation completed at historic Hanford Fuels Laboratory

International Nuclear Information System (INIS)

Gerber, M.S.

1994-03-01

This report discusses deactivation work which was completed as of March 31, 1994 at the 308 Fuels Development Laboratory (FDL) at the Hanford Site near Richland, Washington. The decision to deactivate the structure, formerly known as the Plutonium Fabrication Pilot Plant (PFPP), was driven by a 1980s Department of Energy (DOE) decision that plutonium fuels should not be fabricated in areas near the Site's boundaries, as well as by changing facility structural requirements. Inventory transfer has been followed by the cleanout and stabilization of plutonium oxide (PuO 2 ) and enriched uranium oxide (UO 2 ) residues and powders in the facility's equipment and duct work. The Hanford Site, located in southeastern Washington state, was one of America's primary arsenals of nuclear defense production for nearly 50 years beginning in World War II. Approximately 53 metric tons of weapons grade plutonium, over half of the national supply and about one quarter of the world's supply, were produced at Hanford between 1944 and 1989. Today, many Site buildings are undergoing deactivation, a precursor phase to decontamination and decommissioning (D ampersand D). The primary difference between the two activities is that equipment and structural items are not removed or torn down in deactivation. However, utilities are disconnected, and special nuclear materials (SNM) as well as hazardous and pyrophoric substances are removed from structures undergoing this process

Radionuclide Concentrations in Terrestrial Vegetation and Soil Samples On and Around the Hanford Site, 1971 Through 2008

Energy Technology Data Exchange (ETDEWEB)

Simmons, Mary Ann; Poston, Ted M.; Fritz, Brad G.; Bisping, Lynn E.

2011-07-29

Environmental monitoring is conducted on the U.S. Department of Energy (DOE) Hanford Site to comply with DOE Orders and federal and state regulations. Major objectives of the monitoring are to characterize contaminant levels in the environment and to determine site contributions to the contaminant inventory. This report focuses on surface soil and perennial vegetation samples collected between 1971 and 2008 as part of the Pacific Northwest National Laboratory Surface Environmental Surveillance Project performed under contract to DOE. Areas sampled under this program are located on the Hanford Site but outside facility boundaries and on public lands surrounding the Hanford Site. Additional samples were collected during the past 8 years under DOE projects that evaluated parcels of land for radiological release. These data were included because the same sampling methodology and analytical laboratory were used for the projects. The spatial and temporal trends of six radionuclides collected over a 38-year period were evaluated. The radionuclides----cobalt-60, cesium-137, strontium-90, plutonium-238, plutonium-239/240, and uranium (reported either as uranium-238 or total uranium)----were selected because they persist in the environment and are still being monitored routinely and reported in Hanford Site environmental reports. All these radionuclides were associated with plutonium production and waste management of activities occurring on the site. Other sources include fallout from atmospheric testing of nuclear weapons, which ended in 1980, and the Chernobyl explosion in 1986. Uranium is also a natural component of the soil. This assessment of soil and vegetation data provides important information on the distribution of radionuclides in areas adjacent to industrial areas, established perimeter locations and buffer areas, and more offsite nearby and distant locations. The concentrations reflect a tendency for detection of some radionuclides close to where they were

Radon Progeny in Egyptian Underground Phosphate Mines

International Nuclear Information System (INIS)

El-Hady, M.A.; Mohammed, A.; El-Hussein, A.; Ali, A.E.; Ahmed, A.A.

2001-01-01

In addition to the workers in uranium mines, the staff of other underground mines, such as workers in underground phosphate mines, can be exposed to 222 Rn and its progeny. In this study the individual radon progeny concentrations were measured in three Egyptian underground phosphate mines to estimate the occupational exposure of the workers at those sites. A filter method was used to measure individual radon progeny concentrations ( 218 Po, 214 Pb and 214 Po). The reported mean values of radon progeny concentrations exceed the action levels which are recommended by ICRP 65 (1993). Based on the measured individual radon progeny concentrations ( 218 Po, 214 Pb and 214 Po) in these mines, the annual effective dose for the workers has been calculated using the lung dose model of ICRP 66 (1994). According to the obtained results, some countermeasures were recommended in this study to minimise these exposure levels. (author)

Choice of compressed air fed system of a uranium mine

International Nuclear Information System (INIS)

Li Congkui; Lei Zeyong

2006-01-01

The selection of compressed air fed system in a uranium mine is discussed. The research indicates that the movable air compressor is better than the fixed one in energy saving, once capital cost and operational cost when it is applied in an underground uranium mine. (authors)

Radiogenic cancer in underground miners

International Nuclear Information System (INIS)

Radford, E.P.

1984-01-01

Multiple studies have yielded remarkably consistent results relating radon daughter exposure to lung cancer risk in underground mining populations. The U.S. uranium miner study appears to be at variance with the other results. The primary reason is that the doses in the U.S. miner study were systematically overestimated, resulting in a risk coefficient that is lower than all the others. The significance of these findings for radiogenic lung cancer goes well beyond mining populations, because one is now aware of the implications of radon daughters detected in homes. The highest cumulative levels from radon exposures within homes have been found in Sweden, evidently because of their unusual geology with uranium-bearing ores near the surface. The Swedish authorities view this as a major public health problem that needs to be addressed

Mining and processing of uranium ores in the USSR

International Nuclear Information System (INIS)

Laskorin, B.N.; Mamilov, V.A.; Korejsho, Yu.A.

1983-01-01

Experience gained in uranium ore mining by modern methods in combination with underground and heap leaching is summarized. More intensive processing of low-grade ores has been achieved through the use of autoclave leaching, sorptive treatment of thick pulps, extractive separation of pure uranium compounds, automated continuous sorption devices of high efficiency for processing the underground- and heap-leaching liquors, natural and mine water, and recovery of molybdenum, vanadium, scandium, rare earths and phosphate fertilizers from low-grade ores. Production of ion-exchangers and extractants has been developed and processes for concomitant recovery of copper, gold, ionium, tungsten, caesium, zirconium, tantalum, nickel and cobalt have been designed. (author)

Uranium Pyrophoricity Phenomena and Prediction (FAI/00-39)

International Nuclear Information System (INIS)

PLYS, M.G.

2000-01-01

The purpose of this report is to provide a topical reference on the phenomena and prediction of uranium pyrophoricity for the Hanford Spent Nuclear Fuel (SNF) Project with specific applications to SNF Project processes and situations. Spent metallic uranium nuclear fuel is currently stored underwater at the K basins in the Hanford 100 area, and planned processing steps include: (1) At the basins, cleaning and placing fuel elements and scrap into stainless steel multi-canister overpacks (MCOs) holding about 6 MT of fuel apiece; (2) At nearby cold vacuum drying (CVD) stations, draining, vacuum drying, and mechanically sealing the MCOs; (3) Shipping the MCOs to the Canister Storage Building (CSB) on the 200 Area plateau; and (4) Welding shut and placing the MCOs for interim (40 year) dry storage in closed CSB storage tubes cooled by natural air circulation through the surrounding vault. Damaged fuel elements have exposed and corroded fuel surfaces, which can exothermically react with water vapor and oxygen during normal process steps and in off-normal situations, A key process safety concern is the rate of reaction of damaged fuel and the potential for self-sustaining or runaway reactions, also known as uranium fires or fuel ignition. Uranium metal and one of its corrosion products, uranium hydride, are potentially pyrophoric materials. Dangers of pyrophoricity of uranium and its hydride have long been known in the U.S. Department of Energy (Atomic Energy Commission/DOE) complex and will be discussed more below; it is sufficient here to note that there are numerous documented instances of uranium fires during normal operations. The motivation for this work is to place the safety of the present process in proper perspective given past operational experience. Steps in development of such a perspective are: (1) Description of underlying physical causes for runaway reactions, (2) Modeling physical processes to explain runaway reactions, (3) Validation of the method

Hanford Site groundwater monitoring for fiscal year 1996

Energy Technology Data Exchange (ETDEWEB)

Hartman, M.J.; Dresel, P.E.; Borghese, J.V. [eds.] [and others

1997-02-01

This report presents the results of groundwater and vadose-zone monitoring for fiscal year (FY) 1996 on the Hanford Site, Washington. Hanford Site operations from 1943 onward produced large quantities of radiological and chemical waste that affected groundwater quality on the site. Characterization and monitoring of the vadose zone during FY 1996 comprised primarily spectral gamma logging, soil-gas monitoring, and electrical resistivity tomography. Water-level monitoring was performed to evaluate groundwater-flow directions, to track changes in water levels, and to relate such changes to evolving disposal practices. Water levels over most of the Hanford Site continued to decline between June 1995 and June 1996. Groundwater chemistry was monitored to track the extent of contamination, to note trends, and to identify emerging groundwater-quality problems. The most widespread radiological contaminant plumes were tritium and iodine-129. Smaller plumes of strontium-90, technetium-99, and plutonium also were present at levels above the U.S. Environmental Protection Agency or State of Washington interim drinking water standards. Uranium concentrations greater than the proposed drinking water standard were also observed. Nitrate, fluoride, chromium, carbon tetrachloride, chloroform, trichloroethylene, and cis-1,2-dichlomethylene were present in groundwater samples at levels above their U.S. Environmental Protection Agency or State of Washington maximum contaminant levels. The nitrate plume is the most extensive. Three-dimensional, numerical, groundwater models were applied to the Hanford Site to predict contaminant-flow paths and the impact of operational changes on site groundwater conditions. Other models were applied to assess the performance of three separate pump-and-treat systems.

Hanford Site groundwater monitoring for fiscal year 1996

International Nuclear Information System (INIS)

Hartman, M.J.; Dresel, P.E.; Borghese, J.V.

1997-02-01

This report presents the results of groundwater and vadose-zone monitoring for fiscal year (FY) 1996 on the Hanford Site, Washington. Hanford Site operations from 1943 onward produced large quantities of radiological and chemical waste that affected groundwater quality on the site. Characterization and monitoring of the vadose zone during FY 1996 comprised primarily spectral gamma logging, soil-gas monitoring, and electrical resistivity tomography. Water-level monitoring was performed to evaluate groundwater-flow directions, to track changes in water levels, and to relate such changes to evolving disposal practices. Water levels over most of the Hanford Site continued to decline between June 1995 and June 1996. Groundwater chemistry was monitored to track the extent of contamination, to note trends, and to identify emerging groundwater-quality problems. The most widespread radiological contaminant plumes were tritium and iodine-129. Smaller plumes of strontium-90, technetium-99, and plutonium also were present at levels above the U.S. Environmental Protection Agency or State of Washington interim drinking water standards. Uranium concentrations greater than the proposed drinking water standard were also observed. Nitrate, fluoride, chromium, carbon tetrachloride, chloroform, trichloroethylene, and cis-1,2-dichlomethylene were present in groundwater samples at levels above their U.S. Environmental Protection Agency or State of Washington maximum contaminant levels. The nitrate plume is the most extensive. Three-dimensional, numerical, groundwater models were applied to the Hanford Site to predict contaminant-flow paths and the impact of operational changes on site groundwater conditions. Other models were applied to assess the performance of three separate pump-and-treat systems

Recycling of reprocessed uranium

International Nuclear Information System (INIS)

Randl, R.P.

1987-01-01

Since nuclear power was first exploited in the Federal Republic of Germany, the philosophy underlying the strategy of the nuclear fuel cycle has been to make optimum use of the resource potential of recovered uranium and plutonium within a closed fuel cycle. Apart from the weighty argument of reprocessing being an important step in the treatment and disposal of radioactive wastes, permitting their optimum ecological conditioning after the reprocessing step and subsequent storage underground, another argument that, no doubt, carried weight was the possibility of reducing the demand of power plants for natural uranium. In recent years, strategies of recycling have emerged for reprocessed uranium. If that energy potential, too, is to be exploited by thermal recycling, it is appropriate to choose a slightly different method of recycling from the one for plutonium. While the first generation of reprocessed uranium fuel recycled in the reactor cuts down natural uranium requirement by some 15%, the recycling of a second generation of reprocessed, once more enriched uranium fuel helps only to save a further three per cent of natural uranium. Uranium of the second generation already carries uranium-232 isotope, causing production disturbances, and uranium-236 isotope, causing disturbances of the neutron balance in the reactor, in such amounts as to make further fabrication of uranium fuel elements inexpedient, even after mixing with natural uranium feed. (orig./UA) [de

Identification of Mission Sensitivities with Mission Modeling from the One System Organization at Hanford - 13292

Energy Technology Data Exchange (ETDEWEB)

Belsher, Jeremy D.; Pierson, Kayla L. [Washington River Protection Solutions, LLC, Richland, WA 99352 (United States); Gimpel, Rod F. [One System - Waste Treatment Project, Richland, WA 99352 (United States)

2013-07-01

The Hanford site in southeast Washington contains approximately 207 million liters of radioactive and hazardous waste stored in 177 underground tanks. The U.S. Department of Energy's Office of River Protection is currently managing the Hanford waste treatment mission, which includes the storage, retrieval, treatment and disposal of the tank waste. Two recent studies, employing the modeling tools managed by the One System organization, have highlighted waste cleanup mission sensitivities. The Hanford Tank Waste Operations Simulator Sensitivity Study evaluated the impact that varying 21 different parameters had on the Hanford Tank Waste Operations Simulator model. It concluded that inaccuracies in the predicted phase partitioning of a few key components can result in significant changes in the waste treatment duration and in the amount of immobilized high-level waste that is produced. In addition, reducing the efficiency with which tank waste is retrieved and staged can increase mission duration. The 2012 WTP Tank Utilization Assessment concluded that flowsheet models need to include the latest low-activity waste glass algorithms or the waste treatment mission duration and the amount of low activity waste that is produced could be significantly underestimated. (authors)

A survey of existing and emerging technologies for external detection of liquid leaks at the Hanford Site

International Nuclear Information System (INIS)

Lewis, R.E.; Teel, S.S.

1994-10-01

During the history of the Hanford Site, many structures were built that stored and transported liquids used for the production mission; some of these structures are still active. Active structures include underground storage tanks retention basins, and pipes and pipelines. Many of the liquids stored and transported in these structures are potentially hazardous to human health and the environment. Any leakage of liquids from active structures, has the added potential to mobilize contaminants in the unsaturated zone. Therefore, it is beneficial to monitor these structures for leaks. The purpose of tills report is to catalog existing and emerging technologies that have potential for the external monitoring of liquid leaks. The report will focus primarily on the needs at the Hanford Site tank farms that are located in the 200 Areas, but will also be relevant to other Hanford Site facilities. Leak detection systems, both external and internal, are currently used at some Hanford facilities. This report focuses on the detection of leaks as they migrate into the soils surrounding the facilities

Heap leaching for uranium

International Nuclear Information System (INIS)

1988-01-01

Denison Mines Ltd. is using two bacterial leaching processes to combat the high cost of extracting uranium from low grade ore in thin reefs. Both processes use thiobacillus ferro-oxidans, a bacterium that employs the oxidation of ferrous iron and sulphur as its source of energy for growth. The first method is flood leaching, in which ore is subjected to successive flood, drain and rest cycles. The second, trickle leaching, uses sprinklers to douse the broken muck continuously with leaching solution. In areas where grades are too low to justify the expense of hauling the ore to the surface, the company is using this biological process underground to recover uranium. In 1987 Denison recovered 840 000 lb of uranium through bacterial heap leaching. It plans to have biological in-place leaching contribute 25% of the total uranium production by 1990. (fig.)

ELECTROCHEMICAL STUDIES OF URANIUM METAL CORROSION MECHANISM AND KINETICS IN WATER

International Nuclear Information System (INIS)

Boudanova, Natalya; Maslennikov, Alexander; Peretroukhine, Vladimir F.; Delegard, Calvin H.

2006-01-01

During long-term underwater storage of low burn-up uranium metal fuel, a corrosion product sludge forms containing uranium metal grains, uranium dioxide, uranates and, in some cases, uranium peroxide. Literature data on the corrosion of non-irradiated uranium metal and its alloys do not allow unequivocal prediction of the paragenesis of irradiated uranium in water. The goal of the present work conducted under the program 'CORROSION OF IRRADIATED URANIUM ALLOYS FUEL IN WATER' is to study the corrosion of uranium and uranium alloys and the paragenesis of the corrosion products during long-term underwater storage of uranium alloy fuel irradiated at the Hanford Site. The elucidation of the physico-chemical nature of the corrosion of irradiated uranium alloys in comparison with non-irradiated uranium metal and its alloys is one of the most important aspects of this work. Electrochemical methods are being used to study uranium metal corrosion mechanism and kinetics. The present part of work aims to examine and revise, where appropriate, the understanding of uranium metal corrosion mechanism and kinetics in water

Impact of uranyl-calcium-carbonato complexes on uranium(VI) adsorption to synthetic and natural sediments.

Science.gov (United States)

Stewart, Brandy D; Mayes, Melanie A; Fendorf, Scott

2010-02-01

Adsorption on soil and sediment solids may decrease aqueous uranium concentrations and limit its propensity for migration in natural and contaminated settings. Uranium adsorption will be controlled in large part by its aqueous speciation, with a particular dependence on the presence of dissolved calcium and carbonate. Here we quantify the impact of uranyl speciation on adsorption to both goethite and sediments from the Hanford Clastic Dike and Oak Ridge Melton Branch Ridgetop formations. Hanford sediments were preconditioned with sodium acetate and acetic acid to remove carbonate grains, and Ca and carbonate were reintroduced at defined levels to provide a range of aqueous uranyl species. U(VI) adsorption is directly linked to UO(2)(2+) speciation, with the extent of retention decreasing with formation of ternary uranyl-calcium-carbonato species. Adsorption isotherms under the conditions studied are linear, and K(d) values decrease from 48 to 17 L kg(-1) for goethite, from 64 to 29 L kg (-1) for Hanford sediments, and from 95 to 51 L kg(-1) for Melton Branch sediments as the Ca concentration increases from 0 to 1 mM at pH 7. Our observations reveal that, in carbonate-bearing waters, neutral to slightly acidic pH values ( approximately 5) and limited dissolved calcium are optimal for uranium adsorption.

The Crouzille (Haute-Vienne, France) uranium ores. Half a century of human and industrial adventure in Limousin

International Nuclear Information System (INIS)

Bavoux, B.; Guiollard, P.C.

1998-01-01

The 16 uranium deposits of the Crouzille (Haute-Vienne, France) have produced 25000 tons of uranium between 1950 and 1995. The uranium content of the ores ranges from 1 to 10/1000. The main production came from the underground exploitation up to 300 m of depth. This book presents the historical aspects of this industrial and human epopee and describes with details the underground exploitation of the ore, its processing and the rehabilitation of the site after the mines have closed down. (J.S.)

Measurement of unattached fractions in open-pit uranium mines

International Nuclear Information System (INIS)

Solomon, S.B.; Wise, K.N.

1983-01-01

A preliminary set of measurements of the unattached fraction of potential alpha energy was made at the Ranger open pit uranium uranium mine and the Nabarlek uranium mill. The measurement system, which incorporated a parallel plate diffusion battery and diffuse junction detectors, is described. Results for RaA show a wide variation in the unattached fraction. They range up to 0.76 and are higher than corresponding values for underground mining operations

Hanford Site ground-water monitoring for 1991

International Nuclear Information System (INIS)

Evans, J.C.; Bryce, R.W.; Bates, D.J.

1992-10-01

The Pacific Northwest Laboratory (PNL) monitors the distribution of radionuclides and other hazardous materials in ground water at the Hanford Site for the US Department of Energy (DOE). This work is performed through the Ground-Water Surveillance Project and is designed to meet the requirements of DOE Order 5400.1 that apply to environmental surveillance and ground-water monitoring (DOE 1988). This annual report discusses results of ground-water monitoring at the Hanford Site during 1991. In addition to the general discussion, the following topics are discussed in detail: (1) carbon tetrachloride in the 200-West Area; (2) cyanide in and north of the 200-East and the 200-West areas; (3) hexavalent chromium contamination in the 100, 200, and 600 areas; (4) trichloroethylene in the vicinity of the Solid Waste Landfill, 100-F Area, and 300 Area; (5) nitrate across the Site; (6) tritium across the Site; and (7) other radionuclide contamination throughout the Site, including gross alpha, gross beta, cobalt-60, strontium-90, technetium-99, iodine-129, cesium-137, uranium, and plutonium

Three-Dimensional Groundwater Models of the 300 Area at the Hanford Site, Washington State

Energy Technology Data Exchange (ETDEWEB)

Williams, Mark D.; Rockhold, Mark L.; Thorne, Paul D.; Chen, Yousu

2008-09-01

Researchers at Pacific Northwest National Laboratory developed field-scale groundwater flow and transport simulations of the 300 Area to support the 300-FF-5 Operable Unit Phase III Feasibility Study. The 300 Area is located in the southeast portion of the U.S. Department of Energy’s Hanford Site in Washington State. Historical operations involving uranium fuel fabrication and research activities at the 300 Area have contaminated engineered liquid-waste disposal facilities, the underlying vadose zone, and the uppermost aquifer with uranium. The main objectives of this research were to develop numerical groundwater flow and transport models to help refine the site conceptual model, and to assist assessment of proposed alternative remediation technologies focused on the 300 Area uranium plume.

Hydrogeochemical radioactive features and prospecting in granopegmatite type uranium ore district in Danfeng area

International Nuclear Information System (INIS)

Feng Zhangsheng

2011-01-01

Hydrochemical radioactive prospecting plays an important role in the all stages of grano-pegmatite type uranium deposit exploration in Danfeng area dut to its fast, simple, economic and high effective advantage. Radioactive anomalous halo in the shallow underground water has identical distribution scopes with the ore-bearing biotite granite-pegmatite, which can be used to delineate uranium ore-forming prospective area, reconnaissance area and detailed prospecting area. Deep underground water close to the ore is characterized by hydrogeochemical radioactive features with high uranium and radon content. Through prospecting engineering of radioactive hydrogeochemical, the situation of blind ore bodies can be used to guide the layout. (authors)

HANFORD TANK FARM RESOURCE CONSERVATION and RECOVERY ACT (RCRA) CORRECTIVE ACTION PROGRAM

International Nuclear Information System (INIS)

KRISTOFZSKI, J.G.

2007-01-01

As a consequence of producing special nuclear material for the nation's defense, large amounts of extremely hazardous radioactive waste was created at the US Department of Energy's (DOE) Hanford Site in south central Washington State. A little over 50 million gallons of this waste is now stored in 177 large, underground tanks on Hanford's Central Plateau in tank farms regulated under the Atomic Energy Act and the Resource, Conservation, and Recovery Act (RCRA). Over 60 tanks and associated infrastructure have released or are presumed to have released waste in the vadose zone. In 1998, DOE's Office of River Protection established the Hanford Tank Farm RCRA Corrective Action Program (RCAP) to: (1) characterize the distribution and extent of the existing vadose zone contamination; (2) determine how the contamination will move in the future; (3) estimate the impacts of this contamination on groundwater and other media; (4) develop and implement mitigative measures; and (5) develop corrective measures to be implemented as part of the final closure of the tank farm facilities. Since its creation, RCAP has made major advances in each of these areas, which will be discussed in this paper

Draft Hanford Remedial Action Environmental Impact Statement and Comprehensive Land Use Plan: Volume 2 of 4

International Nuclear Information System (INIS)

1996-08-01

This appendix discusses the scope of actions addressed in the Draft Hanford Remedial Action Environmental Impact Statement and Comprehensive Land Use Plan. To address the purpose and need for agency action identified in Chapter 2.0 of the HRA-EIS, the scope includes an evaluation of the potential environmental impacts associated with the remedial actions to be conducted by the US Department of Energy (DOE) under the provisions of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1989). These remedial actions would bring the Hanford Site into compliance with the applicable requirements of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) and the Resource Conservation and Recovery Act of 1976 (RCRA). The DOE program responsible for conducting remedial actions at the Hanford Site is referred to as the Richland Environmental Restoration (ER) Project. The Richland ER Project encompasses the following projects: radiation area remedial actions and underground storage tanks (UST); RCRA closures; single-shell tank (SST) closures; past-practice waste site operable unit (source and groundwater) remedial actions; surplus facility decommissioning; and waste storage and disposal facilities

Laboratory testing of ozone oxidation of Hanford site waste

International Nuclear Information System (INIS)

Delegard, C.H.; Stubbs, A.M.; Bolling, S.D.; Colby, S.A.

1994-01-01

Organic constituents in radioactive waste stored in underground tanks at the U.S. Department of Energy's Hanford Site provoke safety concerns arising from their low-temperature reactions with nitrate and nitrite oxidants. Destruction of the organics would eliminate both safety problems. Oxone oxidation was investigated to destroy organic species present in simulated and genuine waste from Hanford Site Tank 241-SY-101. Bench-scale tests showed high-shear mixing apparatus achieved efficient gas-to-solution mass transfer and utilization of the ozone reagent. Oxidations of nitrite (to form nitrate) and organic species were observed. The organics formed carbonate and oxalate as well as nitrate and nitrogen gas from organic nitrogen. Formate, acetate and oxalate were present both in source waste and as reaction intermediates. Metal species oxidations also were observed directly or inferred by solubilities. Chemical precipitations of metal ions such as strontium and americium occurred as the organic species were destroyed by ozone. Reaction stoichiometries were consistent with the reduction of one oxygen atom per ozone molecule

Characterization of past and present solid waste streams from the Plutonium-Uranium Extraction Plant

International Nuclear Information System (INIS)

Pottmeyer, J.A.; Weyns, M.I.; Lorenzo, D.S.; Vejvoda, E.J.; Duncan, D.R.

1993-04-01

During the next two decades the transuranic wastes, now stored in the burial trenches and storage facilities at the Hanford Site, are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Over 7% of the transuranic waste to be retrieved for shipment to the Waste Isolation Pilot Plant has been generated at the Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this report is to characterize the radioactive solid wastes generated by PUREX using process knowledge, existing records, and oral history interviews. The PUREX Plant is currently operated by the Westinghouse Hanford Company for the US Department of Energy and is now in standby status while being prepared for permanent shutdown. The PUREX Plant is a collection of facilities that has been used primarily to separate plutonium for nuclear weapons from spent fuel that had been irradiated in the Hanford Site's defense reactors. Originally designed to reprocess aluminum-clad uranium fuel, the plant was modified to reprocess zirconium alloy clad fuel elements from the Hanford Site's N Reactor. PUREX has provided plutonium for research reactor development, safety programs, and defense. In addition, the PUREX was used to recover slightly enriched uranium for recycling into fuel for use in reactors that generate electricity and plutonium. Section 2.0 provides further details of the PUREX's physical plant and its operations. The PUREX Plant functions that generate solid waste are as follows: processing operations, laboratory analyses and supporting activities. The types and estimated quantities of waste resulting from these activities are discussed in detail

Uranium in the Near-shore Aquatic Food Chain: Studies on Periphyton and Asian Clams

International Nuclear Information System (INIS)

Bunn, Amoret L.; Miley, Terri B.; Eslinger, Paul W.; Brandt, Charles A.; Napier, Bruce A.

2007-01-01

The benthic aquatic organisms in the near-shore environment of the Columbia River are the first biological receptors that can be exposed to groundwater contaminants coming from the U.S. Department of Energy's Hanford Site. The primary contaminant of concern in the former nuclear fuels processing area at the Site, known as the 300 Area, is uranium. Currently, there are no national clean up criteria for uranium and ecological receptors. This report summarizes efforts to characterize biological uptake of uranium in the food chain of the benthic aquatic organisms and provide information to be used in future assessments of uranium and the ecosystem.

Waste management in the uranium companies of Niger

International Nuclear Information System (INIS)

Hama, A.

2002-01-01

Two companies produce uranium (yellowcake) in Niger: the 'Societe des Mines de l'Air (SOMAIR)' and the 'Compagnie Miniere d'Akouta (COMINAK)'. The SOMAIR operation uses open pit mining whereas COMINAK employs underground mining. Uranium ores have been treated by SOMAIR and COMINAK since 1971 and 1978 respectively. The wastes produced by the two companies will be managed to reduce health and environment impacts. (author)

Methodology of simulation of underground working in metal mines. Application to a uranium deposit in Australia

International Nuclear Information System (INIS)

Deraisme, J.; de Fouquet, C.; Fraisse, H.

1983-01-01

For the Ben Lomond (Northern Queensland Australia) underground uranium mining project, studies were carried out to compare the feasibility of different mining methods according to their cost per ton and selectivity, i.e. cut and fill, sublevel stopping and both mixed. First, a geostatistical orebody model was built. The ore grade variability of this model results from the drillhole structural analysis. Working on two dimensional vertical cross sections, the usual hand drawing stope reserve estimate obtained with computer assisted design for each of the three different mining methods is compared with the results obtained with automatic algorithms allocated to the characteristics of each mining method. These algorithms use mathematical morphology to reproduce the geometrical constraints connected with each mining method and/or dynamic programmation. These techniques lead to fully automatic of optimal economical stope design. Comparison is positive: automatic stopes designs are in agreement with hand made drawings, but they can be defined faster through interactive questionning of the computer, and the total maximum profit obtained is a least as high as the best profit found through hand designed projects [fr

Regulatory issues associated with closure of the Hanford AX Tank Farm ancillary equipment

International Nuclear Information System (INIS)

Becker, D.L.

1998-01-01

Liquid mixed, high-level radioactive waste has been stored in underground single-shell tanks at the US Department of Energy's (DOE's) Hanford Site. After retrieval of the waste from the single-shell tanks, the DOE will proceed with closure of the tank farm. The 241-AX Tank Farm includes four one-million gallon single-shell tanks in addition to sluice lines, transfer lines, ventilation headers, risers, pits, cribs, catch tanks, buildings, well and associated buried piping. This equipment is classified as ancillary equipment. This document addresses the requirements for regulatory close of the ancillary equipment in the Hanford Site 241-AX Tank Farm. The options identified for physical closure of the ancillary equipment include disposal in place, disposal in place after treatment, excavation and disposal on site in an empty single-shell tank, and excavation and disposal outside the AX Tank Farm. The document addresses the background of the Hanford Site and ancillary equipment in the AX Tank Farm, regulations for decontamination and decommissioning of radioactively contaminated equipment, requirements for the cleanup and disposal of radioactive wastes, cleanup and disposal requirements governing hazardous and mixed waste, and regulatory requirements and issues associated with each of the four physical closure options. This investigation was conducted by the Sandia National Laboratories, Albuquerque, New Mexico, during Fiscal Year 1998 for the Hanford Tanks Initiative Project

High-level core sample x-ray imaging at the Hanford Site

International Nuclear Information System (INIS)

Weber, J.R.; Keye, J.K.

1995-01-01

Waste tank sampling of radioactive high-level waste is required for continued operations, waste characterization, and site safety. Hanford Site Tank farms consist of 28 double-shell and 149 single-shell underground storage tanks. The single shell tanks are out-of-service and no longer receive liquid waste. Core samples of salt cake and sludge waste are remotely obtained using truck-mounted, core drill platforms. Samples are recovered from tanks through a 2.25 inch (in.) drill pipe in 26-in. steel tubes, 1.5 in. diameter. Drilling parameters vary with different waste types. Because sample recovery has been marginal and inadequate at times, a system was needed to provide drill truck operators with real-time feedback about the physical conditions of the sample and the percent recovery, prior to making nuclear assay measurements and characterizations at the analytical laboratory. Westinghouse hanford Company conducted proof-of -principal radiographic testing to verify the feasibility of a proposed imaging system

Value-based performance measures for Hanford Tank Waste Remedition System (TWRS) Program

International Nuclear Information System (INIS)

Keeney, R.L.; von Winterfeldt, D.

1996-01-01

The Tank Waste Remediation Systems (TWRS) Program is responsible for the safe storage, retrieval, treatment, and preparation for disposal of high-level waste currently stored in underground storage tanks at the Hanford site in Richland. The TWRS program has adopted a logical approach to decision making that is based on systems engineering and decision analysis (Westinghouse Hanford Company, 1995). This approach involves the explicit consideration of stakeholder values and an evaluation of the TWRS alternatives in terms of these values. Such evaluations need to be consistent across decisions. Thus, an effort was undertaken to develop a consistent, quantifiable set of measures that can be used by TVVRS to assess alternatives against the stakeholder values. The measures developed also met two additional requirements: 1) the number of measure should be relatively small; and 2) performance with respect to the measures should be relatively easy to estimate

Fluor Hanford Project Focused Progress at Hanford

International Nuclear Information System (INIS)

HANSON, R.D.

2000-01-01

Fluor Hanford is making significant progress in accelerating cleanup at the Hanford site. This progress consistently aligns with a new strategic vision established by the U.S. Department of Energy's Richland Operations Office (RL)

Uranium hexafluoride packaging tiedown systems overview at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio

International Nuclear Information System (INIS)

Becker, D.L.; Green, D.J.; Lindquist, M.R.

1993-07-01

The Portsmouth Gaseous Diffusion Plant (PORTS) in Piketon, Ohio, is operated by Martin Marietta Energy Systems, Inc., through the US Department of Energy-Oak Ridge Operations Office (DOE-ORO) for the US Department of Energy-Headquarters, Office of Nuclear Energy. The PORTS conducts those operations that are necessary for the production, packaging, and shipment of uranium hexafluoride (UF 6 ). Uranium hexafluoride enriched uranium than 1.0 wt percent 235 U shall be packaged in accordance with the US Department of Transportation (DOT) regulations of Title 49 CFR Parts 173 (Reference 1) and 178 (Reference 2), or in US Nuclear Regulatory Commission (NRC) or US Department of Energy (DOE) certified package designs. Concerns have been expressed regarding the various tiedown methods and condition of the trailers being used by some shippers/carriers for international transport of the UF 6 cylinders/overpacks. Because of the concerns about international shipments, the US Department of Energy-Headquarters (DOE-HQ) Office of Nuclear Energy, through DOE-HQ Transportation Management Division, requested Westinghouse Hanford Company (Westinghouse Hanford) to review UF 6 packaging tiedown and shipping practices used by PORTS, and where possible and appropriate, provide recommendations for enhancing these practices. Consequently, a team of two individuals from Westinghouse Hanford visited PORTS on March 5 and 6, 1990, for the purpose of conducting this review. The paper provides a brief discussion of the review activities and a summary of the resulting findings and recommendations. A detailed reporting of the is documented in Reference 4

Evaluation of chemical sensors for in situ ground-water monitoring at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Murphy, E.M.; Hostetler, D.D.

1989-03-01

This report documents a preliminary review and evaluation of instrument systems and sensors that may be used to detect ground-water contaminants in situ at the Hanford Site. Three topics are covered in this report: (1) identification of a group of priority contaminants at Hanford that could be monitored in situ, (2) a review of current instrument systems and sensors for environmental monitoring, and (3) an evaluation of instrument systems that could be used to monitor Hanford contaminants. Thirteen priority contaminants were identified in Hanford ground water, including carbon tetrachloride and six related chlorinated hydrocarbons, cyanide, methyl ethyl ketone, chromium (VI), fluoride, nitrate, and uranium. Based on transduction principles, chemical sensors were divided into four classes, ten specific types of instrument systems were considered: fluorescence spectroscopy, surface-enhanced Raman spectroscopy (SERS), spark excitation-fiber optic spectrochemical emission sensor (FOSES), chemical optrodes, stripping voltammetry, catalytic surface-modified ion electrode immunoassay sensors, resistance/capacitance, quartz piezobalance and surface acoustic wave devices. Because the flow of heat is difficult to control, there are currently no environmental chemical sensors based on thermal transduction. The ability of these ten instrument systems to detect the thirteen priority contaminants at the Hanford Site at the required sensitivity was evaluated. In addition, all ten instrument systems were qualitatively evaluated for general selectivity, response time, reliability, and field operability. 45 refs., 23 figs., 7 tabs.

Evaluation of chemical sensors for in situ ground-water monitoring at the Hanford Site

International Nuclear Information System (INIS)

Murphy, E.M.; Hostetler, D.D.

1989-03-01

This report documents a preliminary review and evaluation of instrument systems and sensors that may be used to detect ground-water contaminants in situ at the Hanford Site. Three topics are covered in this report: (1) identification of a group of priority contaminants at Hanford that could be monitored in situ, (2) a review of current instrument systems and sensors for environmental monitoring, and (3) an evaluation of instrument systems that could be used to monitor Hanford contaminants. Thirteen priority contaminants were identified in Hanford ground water, including carbon tetrachloride and six related chlorinated hydrocarbons, cyanide, methyl ethyl ketone, chromium (VI), fluoride, nitrate, and uranium. Based on transduction principles, chemical sensors were divided into four classes, ten specific types of instrument systems were considered: fluorescence spectroscopy, surface-enhanced Raman spectroscopy (SERS), spark excitation-fiber optic spectrochemical emission sensor (FOSES), chemical optrodes, stripping voltammetry, catalytic surface-modified ion electrode immunoassay sensors, resistance/capacitance, quartz piezobalance and surface acoustic wave devices. Because the flow of heat is difficult to control, there are currently no environmental chemical sensors based on thermal transduction. The ability of these ten instrument systems to detect the thirteen priority contaminants at the Hanford Site at the required sensitivity was evaluated. In addition, all ten instrument systems were qualitatively evaluated for general selectivity, response time, reliability, and field operability. 45 refs., 23 figs., 7 tabs

Uranium Pyrophoricity Phenomena and Prediction (FAI/00-39)

Energy Technology Data Exchange (ETDEWEB)

PLYS, M.G.

2000-10-10

The purpose of this report is to provide a topical reference on the phenomena and prediction of uranium pyrophoricity for the Hanford Spent Nuclear Fuel (SNF) Project with specific applications to SNF Project processes and situations. Spent metallic uranium nuclear fuel is currently stored underwater at the K basins in the Hanford 100 area, and planned processing steps include: (1) At the basins, cleaning and placing fuel elements and scrap into stainless steel multi-canister overpacks (MCOs) holding about 6 MT of fuel apiece; (2) At nearby cold vacuum drying (CVD) stations, draining, vacuum drying, and mechanically sealing the MCOs; (3) Shipping the MCOs to the Canister Storage Building (CSB) on the 200 Area plateau; and (4) Welding shut and placing the MCOs for interim (40 year) dry storage in closed CSB storage tubes cooled by natural air circulation through the surrounding vault. Damaged fuel elements have exposed and corroded fuel surfaces, which can exothermically react with water vapor and oxygen during normal process steps and in off-normal situations, A key process safety concern is the rate of reaction of damaged fuel and the potential for self-sustaining or runaway reactions, also known as uranium fires or fuel ignition. Uranium metal and one of its corrosion products, uranium hydride, are potentially pyrophoric materials. Dangers of pyrophoricity of uranium and its hydride have long been known in the U.S. Department of Energy (Atomic Energy Commission/DOE) complex and will be discussed more below; it is sufficient here to note that there are numerous documented instances of uranium fires during normal operations. The motivation for this work is to place the safety of the present process in proper perspective given past operational experience. Steps in development of such a perspective are: (1) Description of underlying physical causes for runaway reactions, (2) Modeling physical processes to explain runaway reactions, (3) Validation of the method

Hanford Cleanup... Restore the Columbia River Corridor Transition the Central Plateau Prepare and Plan for the End State

International Nuclear Information System (INIS)

Klein, Keith A.

2006-01-01

The U.S. Department of Energy's (DOE) Hanford Site in southeastern Washington State was established during World War II to produce plutonium for nuclear weapons as part of the top-secret Manhattan Project. In 1989, Hanford's mission changed to cleanup and closure; today the site is engaged in one of the world's largest and most aggressive programs to clean up radioactive and hazardous wastes. The size and complexity of Hanford's environmental problems are made even more challenging by the overlapping technical, political, regulatory, financial and cultural issues associated with the cleanup. The physical challenges at the Hanford Site are daunting. More than 50 million gallons of liquid radioactive waste in 177 underground storage tanks; 2,300 tons of spent nuclear fuel;12 tons of plutonium in various forms; 25 million cubic feet of buried or stored solid waste; 270 billion gallons of groundwater contaminated above drinking-water standards spread out over about 80 square miles; more than 1,700 waste sites; and approximately 500 contaminated facilities. With a workforce of approximately 7,000 and a budget of about $1.8 billion dollars this fiscal year, Hanford cleanup operations are expected to be complete by 2035, at a cost of $60 billion dollars. (authors)

Hanford Site Groundwater Monitoring for Fiscal Year 2005

Energy Technology Data Exchange (ETDEWEB)

Hartman, Mary J.; Morasch, Launa F.; Webber, William D.

2006-02-28

This report is one of the major products and deliverables of the Groundwater Remediation and Closure Assessment Projects detailed work plan for FY 2006, and reflects the requirements of The Groundwater Performance Assessment Project Quality Assurance Plan (PNNL-15014). This report presents the results of groundwater and vadose zone monitoring and remediation for fiscal year 2005 on the U.S. Department of Energy's Hanford Site, Washington. The most extensive contaminant plumes in groundwater are tritium, iodine-129, and nitrate, which all had multiple sources and are very mobile in groundwater. The largest portions of these plumes are migrating from the central Hanford Site to the southeast, toward the Columbia River. Carbon tetrachloride and associated organic constituents form a relatively large plume beneath the west-central part of the Hanford Site. Hexavalent chromium is present in plumes beneath the reactor areas along the river and beneath the central part of the site. Strontium-90 exceeds standards beneath all but one of the reactor areas. Technetium-99 and uranium plumes exceeding standards are present in the 200 Areas. A uranium plume underlies the 300 Area. Minor contaminant plumes with concentrations greater than standards include carbon-14, cesium-137, cis-1,2-dichloroethene, cyanide, fluoride, plutonium, and trichloroethene. Monitoring for the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 is conducted in 11 groundwater operable units. The purpose of this monitoring is to define and track plumes and to monitor the effectiveness of interim remedial actions. Interim groundwater remediation in the 100 Areas continued with the goal of reducing the amount of chromium (100-K, 100-D, and 100-H) and strontium-90 (100-N) reaching the Columbia River. The objective of two interim remediation systems in the 200 West Area is to prevent the spread of carbon tetrachloride and technetium-99/uranium plumes. Resource Conservation and

Short-term radon activity concentration changes along the Underground Educational Tourist Route in the Old Uranium Mine in Kletno (Sudety Mts., SW Poland).

Science.gov (United States)

Fijałkowska-Lichwa, Lidia

2014-09-01

Short-term (222)Rn activity concentration changes along the Underground Educational Tourist Route in the Old Uranium Mine in Kletno were studied, based on continuous measurements conducted between 16 May 2008 and 15 May 2010. The results were analysed in the context of numbers of visitors arriving at the facility in particular seasons and the time per day spent inside by staff and visitors. This choice was based on partially published earlier findings (Fijałkowska-Lichwa and Przylibski, 2011). Results for the year 2009 were analysed in depth, because it is the only period of observation covering a full calendar year. The year 2009 was also chosen for detailed analysis of short-term radon concentration changes, because in each period of this year (hour, month, season) fluctuations of noted values were the most visible. Attention has been paid to three crucial issues linked to the occurrence and behaviour of radon and to the radiological protection of workers and visitors at the tourist route in Kletno. The object of study is a complex of workings in a former uranium mine situated within a metamorphic rock complex in the most radon-prone area in Poland. The facility has been equipped with a mechanical ventilation system, which is turned on after the closing time and at the end of the working day for the visitor service staff, i.e. after 6 p.m. Short-term radon activity concentration changes along the Underground Educational Tourist Route in the Old Uranium Mine in Kletno are related to the activity of the facility's mechanical ventilation. Its inactivity in the daytime results in the fact that the highest values of (222)Rn activity concentration are observed at the time when the facility is open to visitors, i.e. between 10 a.m. and 6 p.m. The improper usage of the mechanical ventilation system is responsible for the extremely unfavourable working conditions, which persist in the facility for practically all year. The absence of appropriate radiological protection

Closure of the condensed-phase organic-nitrate reaction unreviewed safety question at Hanford site

International Nuclear Information System (INIS)

COWLEY, W.L.

1999-01-01

A discovery Unreviewed Safety Question (USQ) was declared on the underground waste storage tanks at the Hanford Site in May 1996. The USQ was for condensed-phase organic-nitrate reactions (sometimes called organic complexant reactions) in the tanks. This paper outlines the steps taken to close the USQ, and resolve the related safety issue. Several processes were used at the Hanford Site to extract and/or process plutonium. These processes resulted in organic complexants (for chelating multivalent cations) and organic extraction solvents being sent to the underground waste storage tanks. This paper addresses the organic complexant hazard. The organic complexants are in waste matrices that include inert material, diluents, and potential oxidizers. In the presence of oxidizing material, the complexant salts can be made to react exothermically by heating to high temperatures or by applying an external ignition source of sufficient energy. The first organic complexant hazard assessments focused on determining whether a hulk runaway reaction could occur, similar to the 1957 accident at Kyshtm (a reprocessing plant in the former U.S.S.R.). Early analyses (1977 through 1994) examined organic-nitrate reaction onset temperatures and concluded that a bulk runaway reaction could not occur at the Hanford Site because tank temperatures were well below that necessary for bulk runaway. Therefore, it was believed that organic-nitrate reactions were adequately described in the then current Authorization Basis (AB). Subsequent studies examined a different accident scenario, propagation resulting from an external ignition source (e.g., lightning or welding slag) that initiates a combustion front that propagates through the organic waste. A USQ evaluation determined that localized high energy ignition sources were credible, and that point source ignition of organic complexant waste was not adequately addressed i n the then existing AB. Consequently, the USQ was declared on the

Kinetic and thermodynamic bases to resolve issues regarding conditioning of uranium metal fuels

International Nuclear Information System (INIS)

Johnson, A.B.; Ballinger, R.G.; Simpson, K.A.

1994-12-01

Numerous uranium - bearing fuels are corroding in fuel storage pools in several countries. At facilities where reprocessing is no longer available, dry storage is being evaluated to preclude aqueous corrosion that is ongoing. It is essential that thermodynamic and kinetic factors are accounted for in transitions of corroding uranium-bearing fuels to dry storage. This paper addresses a process that has been proposed to move Hanford N-Reactor fuel from wet storage to dry storage

Groundwater and vadose Zone Integration Project Nuclear Material Mass Flow and Accountability on the Hanford Site

International Nuclear Information System (INIS)

GRASHER, A.A.

2001-01-01

The purpose of this report is to provide a discussion of the accountable inventory of Hanford Site nuclear material (NM) over the operating period. This report does not provide judgments on impacts to the Hanford Site environs by the reported waste streams or inventory. The focus of this report is on the processes, facilities, and process streams that constituted the flow primarily of plutonium and uranium through the Hanford Site. The material balance reports (MBRS) are the basis of the NM accountable inventory maintained by each of the various contractors used by the U.S. Department of Energy (DOE) and its predecessors to operate the Hanford Site. The inventory was tracked in terms of a starting inventory, receipts, transfers, and ending inventory. The various components of the inventory are discussed as well as the uncertainty in the measurement values used to establish plant inventory and material transfers. The accountable NM inventory does not report all the NM on the Hanford Site and this difference is discussed relative to some representative nuclides. The composition and location of the current accountable inventory are provided, as well as the latest approved set (2000) of flow diagrams of the proposed disposition of the excess accountable NM inventory listed on the Idaho National Engineering and Environmental Laboratory (INEEL) web page

High radon exposure in a Brazilian underground coal mine

International Nuclear Information System (INIS)

Veiga, L H S; Melo, V; Koifman, S; Amaral, E C S

2004-01-01

The main source of radiation exposure in most underground mining operations is radon and radon decay products. The situation of radon exposure in underground mining in Brazil is still unknown, since there has been no national regulation regarding this exposure. A preliminary radiological survey in non-uranium mines in Brazil indicated that an underground coal mine in the south of Brazil had high radon concentration and needed to be better evaluated. This paper intends to present an assessment of radon and radon decay product exposure in the underground environment of this coal mining industry and to estimate the annual exposure to the workers. As a product of this assessment, it was found that average radon concentrations at all sampling campaign and excavation sites were above the action level range for workplaces of 500-1500 Bq m -3 recommended by the International Commission on Radiological Protection-ICRP 65. The average effective dose estimated for the workers was almost 30 times higher than the world average dose for coal miners

Rethinking the Hanford Tank Waste Program

International Nuclear Information System (INIS)

Parker, F. L.; Clark, D. E.; Morcos, N.

2002-01-01

The program to treat and dispose of the highly radioactive wastes stored in underground tanks at the U.S. Department of Energy's Hanford site has been studied. A strategy/management approach to achieve an acceptable (technically sound) end state for these wastes has been developed in this study. This approach is based on assessment of the actual risks and costs to the public, workers, and the environment associated with the wastes and storage tanks. Close attention should be given to the technical merits of available waste treatment and stabilization methodologies, and application of realistic risk reduction goals and methodologies to establish appropriate tank farm cleanup milestones. Increased research and development to reduce the mass of non-radioactive materials in the tanks requiring sophisticated treatment is highly desirable. The actual cleanup activities and milestones, while maintaining acceptable safety standards, could be more focused on a risk-to-benefit cost effectiveness, as agreed to by the involved stakeholders and in accordance with existing regulatory requirements. If existing safety standards can be maintained at significant cost savings under alternative plans but with a change in the Tri-Party Agreement (a regulatory requirement), those plans should be carried out. The proposed strategy would also take advantage of the lessons learned from the activities and efforts in the first phase of the two-phased cleanup of the Hanford waste tank farms

Study of underground radon transport

International Nuclear Information System (INIS)

Csige, I.; Hakl, J.; Lenart, L.

1990-01-01

The soil gas radon content measurements with solid state nuclear track detectors (SSNTDs) are widely used in geoscience, for instance in uranium exploration and earthquake prediction. In these applications the radon frequently is used as a natural tracer of underground fluid transport processes. Obviously, to get the soil radon measuring method more and more effective the study of these transport processes in deeper part of the Earth is fundamental. The Track Detector Group in the Institute of Nuclear Research of the Hungarian Academy of Sciences in Debrecen has been performing environmental radon activity concentration measurements since 1977 with alpha sensitive SSNTDs. These types of measurements were initiated and widely used by the late head of the group Dr. G. Somogyi, who devoted his life to better understanding of the nature. The measurements in caves, springs and drilled wells proved to be effective to study these underground radon transport processes. We are glad to present some results of our investigations. 7 refs, 7 figs

Radionuclide concentrations in agricultural products near the Hanford Site, 1982 through 1992

International Nuclear Information System (INIS)

Antonio, E.J.

1994-06-01

The Pacific Northwest Laboratory reviewed monitoring data for agricultural products collected from 1982 through 1992 near the Hanford Site to determine radionuclide concentration trends. While samples were collected and analyzed, and results reported annual in Hanford Site environmental reports, an 11-year data set was reviewed for this report to increase the ability to assess trends and potential Hanford effects. Products reviewed included milk, chicken, eggs, beef, vegetables, fruit, wine, wheat, and alfalfa. To determine which radionuclides were detected sufficiently often to permit analysis for trends and effects, each radionuclide concentration and its associated uncertainty were ratioed. Radionuclides were considered routinely detectable if more than 50% of the ratios were between zero and one. Data for these radionuclides were then analyzed statistically, using analyses of variance. The statistical analyses indicated the following: for the most part, there were no measurable effects for Hanford operations; radionuclide concentrations in all products reviewed remained relatively low when compared to concentrations that would result in a 1-mrem effective dose equivalent to an individual; radionuclide concentrations are decreasing in general; however, 90 Sr concentrations in all media and 129 I in milk increased from 1982 to 1986, then decreased gradually for the remainder of the review period. The 129 I concentrations may be correlated with processing of irradiated reactor fuel at the Plutonium-Uranium Extraction (PUREX) Plant

Uranium in the Near-shore Aquatic Food Chain: Studies on Periphyton and Asian Clams

Energy Technology Data Exchange (ETDEWEB)

Bunn, Amoret L.; Miley, Terri B.; Eslinger, Paul W.; Brandt, Charles A.; Napier, Bruce A.

2007-12-31

The benthic aquatic organisms in the near-shore environment of the Columbia River are the first biological receptors that can be exposed to groundwater contaminants coming from the U.S. Department of Energy's Hanford Site. The primary contaminant of concern in the former nuclear fuels processing area at the Site, known as the 300 Area, is uranium. Currently, there are no national clean up criteria for uranium and ecological receptors. This report summarizes efforts to characterize biological uptake of uranium in the food chain of the benthic aquatic organisms and provide information to be used in future assessments of uranium and the ecosystem.

Assessment of the underground disposal of tailings

Energy Technology Data Exchange (ETDEWEB)

Hutt, N M [Morwijk Enterprises Ltd., (Canada); Morin, K A [Normar Enterprises, (Canada)

1995-06-01

The Atomic Energy Control Board (AECB) of Canada is facing the issue of long-term disposal of uranium tailings. One option that has not been examined in sufficient detail for the AECB is the retrieval of tailings from surface impoundments and subsequent placement of those tailings in underground workings of mines. This report is structured like a catalogue of facts and information, with each paragraph presenting some concept, concern, theory, or case study involving the retrieval or placement of tailings. All relevant information, findings, interpretations, conclusions, and recommendations gathered during the course of this study are included. The Table of Contents illustrates the striking number of relevant topics and acts like a flowchart or checklist to ensure that an underground-disposal submission by a mining company has addressed relevant topics. This report explains in detail the implications of disturbing surface-impounded tailings for the purpose of placing only some of the volume underground. The cumulative environmental, safety, and monetary liabilities of such a partial scheme can be discouraging in some cases. (author). 244 refs., 47 tabs., 17 figs.

Assessment of the underground disposal of tailings

International Nuclear Information System (INIS)

Hutt, N.M.; Morin, K.A.

1995-06-01

The Atomic Energy Control Board (AECB) of Canada is facing the issue of long-term disposal of uranium tailings. One option that has not been examined in sufficient detail for the AECB is the retrieval of tailings from surface impoundments and subsequent placement of those tailings in underground workings of mines. This report is structured like a catalogue of facts and information, with each paragraph presenting some concept, concern, theory, or case study involving the retrieval or placement of tailings. All relevant information, findings, interpretations, conclusions, and recommendations gathered during the course of this study are included. The Table of Contents illustrates the striking number of relevant topics and acts like a flowchart or checklist to ensure that an underground-disposal submission by a mining company has addressed relevant topics. This report explains in detail the implications of disturbing surface-impounded tailings for the purpose of placing only some of the volume underground. The cumulative environmental, safety, and monetary liabilities of such a partial scheme can be discouraging in some cases. (author). 244 refs., 47 tabs., 17 figs

Close out of the Malargue site: Underground draining system

International Nuclear Information System (INIS)

Giordano, Nolberto N.; Liseno, Aldo

2000-01-01

An industrial uranium production facility stopped working in Malargue city, Mendoza province. Nowadays, in that place there are 700,000 tons of solid tailings piles from the uranium minerals concentration process. They must be treated inside the site through engineering works included in the final closeout project. This paper describes the project technical details of an underground drainage system, designed to depress the groundwater level and to be sure about the isolation of the solids to be treated from the groundwater. The work was done by a private company, after public bidding process. At the moment the drainage system is in operation control stage. (author)

Hydrochemical uranium mining at the Straz ore deposit and its hydrogeological consequences

International Nuclear Information System (INIS)

Hanzlik, J.; Moravec, J.; Macak, P.

1992-01-01

The uranium ore deposit at Straz is situated in the North Bohemian Cretaceous Massif. Uranium is extracted from the deposit by underground chemical leaching by means of drills from the ground. Relevant to this kind of extraction, from the hydrogeological and environmental aspects, are the hydrogeological location of the deposit, the kind and amounts of the leaching solution and ways of its injection. The following amounts, in thousand tons, have been injected underground throughout the entire period of practicing chemical extraction of uranium (till 1990): sulfuric acid 3700, nitric acid 270, ammonia 100, hydrofluoric acid 25. The overall area of the leaching fields is 630 hectares, which accommodate 9300 technological boreholes. The environmental burden of the Cenomanian rocks and Turonian water reservoir was analyzed, and significantly elevated heavy metal contents from the recirculation of the technological solutions were found. The solutions expand beyond the leaching fields, causing a contamination of underground water within wider surroundings. The volume of contaminated water in the Turonian reservoir is currently estimated at 2 - 20 million m 3 . Uranium extraction by leaching is harmful at this deposit, having far-reaching impacts on the hydrosphere and ecosystem (increased dust, deforestation of slopes of the Ralsko hill, contamination of water and soil, etc.). Abandoning the ore extraction appears to be the sole feasible approach to this problem. (Z.S.). 2 tabs., 3 figs

Hanford Site Groundwater Monitoring for Fiscal Year 2000

Energy Technology Data Exchange (ETDEWEB)

Hartman, Mary J.; Morasch, Launa F.; Webber, William D.

2001-03-01

This report presents the results of groundwater and vadose zone monitoring and remediation for fiscal year 2000 on the U.S. Department of Energy's Hanford Site, Washington. The most extensive contaminant plumes are tritium, iodine-129, and nitrate, which all had multiple sources and are very mobile in groundwater. Carbon tetrachloride and associated organic constituents form a relatively large plume beneath the central part of the Site. Hexavalent chromium is present in smaller plumes beneath the reactor areas along the river and beneath the central part of the site. Strontium-90 exceeds standards beneath each of the reactor areas, and technetium-99 and uranium are present in the 200 Areas. RCRA groundwater monitoring continued during fiscal year 2000. Vadose zone monitoring, characterization, remediation, and several technical demonstrations were conducted in fiscal year 2000. Soil gas monitoring at the 618-11 burial ground provided a preliminary indication of the location of tritium in the vadose zone and in groundwater. Groundwater modeling efforts focused on 1) identifying and characterizing major uncertainties in the current conceptual model and 2) performing a transient inverse calibration of the existing site-wide model. Specific model applications were conducted in support of the Hanford Site carbon tetrachloride Innovative Treatment Remediation Technology; to support the performance assessment of the Immobilized Low-Activity Waste Disposal Facility; and in development of the System Assessment Capability, which is intended to predict cumulative site-wide effects from all significant Hanford Site contaminants.

Melter system technology testing for Hanford Site low-level tank waste vitrification

International Nuclear Information System (INIS)

Wilson, C.N.

1996-01-01

Following revisions to the Tri-Party Agreement for Hanford Site cleanup, which specified vitrification for Complete melter feasibility and system operability immobilization of the low-level waste (LLW) tests, select reference melter(s), and establish reference derived from retrieval and pretreatment of the radioactive LLW glass formulation that meets complete systems defense wastes stored in 177 underground tanks, commercial requirements (June 1996). Available melter technologies were tested during 1994 to 1995 as part of a multiphase program to select reference Submit conceptual design and initiate definitive design technologies for the new LLW vitrification mission

Potential dust exposures in underground mines of the former Wismut Ltd. during the early phase of uranium mining after the second world war

International Nuclear Information System (INIS)

Bauer, H.D.

1997-01-01

We performed dust measurements in several underground mines of Wismut Ltd. during dry drilling and ore mining with pneumatic hammers. The purpose was to reproduce operational conditions typical of the early phase of uranium mining after the second world war. Since do dust measurements were performed, data or information on exposures in that period of time are not available. Our investigations were intended to fill this gap. The decisive step to reduce exposures in mining areas and in regions to be opened up and prepared was the conversion from dry drilling with air flushing to wet drilling with water flushing resulting in a decrease of fine dust concentrations by more than 97%. (orig./SR) [de

An Initial Evaluation of Characterization and Closure Options for Underground Pipelines within a Hanford Site Single-Shell Tank Farm - 13210

Energy Technology Data Exchange (ETDEWEB)

Badden, Janet W.; Connelly, Michael P. [Washington River Protection Services, P.O. Box 850, Richland, Washington, 99352 (United States); Seeley, Paul N. [Cenibark International, Inc., 104318 Nicole Drive, Kennewick, Washington, 99338-7596 (United States); Hendrickson, Michelle L. [Washington State Department of Ecology, 3100 Port of Benton Blvd, Richland, Washington, 99354 (United States)

2013-07-01

The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies

An Initial Evaluation Of Characterization And Closure Options For Underground Pipelines Within A Hanford Site Single-Shell Tank Farm-13210

International Nuclear Information System (INIS)

Badden, Janet W.; Connelly, Michael P.; Seeley, Paul N.; Hendrickson, Michelle L.

2013-01-01

The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies and

129I, 60Co, and 106Ru measurements on water samples from the Hanford project environs

International Nuclear Information System (INIS)

Brauer, F.P.; Rieck, H.G. Jr.

1973-01-01

Groundwater flow and contamination patterns beneath the Hanford project reservation have been studied since the early days of the project. The measurement of radioactive materials at concentrations much below those required for radiation protection are useful for tracing groundwater movement and detection of potential contamination problems before they are apt to occur. Groundwater samples from a number of wells on or near the Hanford reservation have been analyzed for 129 I by neutron activation analysis and for gamma radioactivity by low-level coincidence gamma-ray spectrometry. The major radionuclides in addition to natural radioactivity detected in the underground waters by gamma-ray spectrometry were 106 Ru and 60 Co. Local river and rain water samples were also analyzed for 129 I and long-lived radionuclides. Special sample collection methods were developed to prevent contamination of the water samples during collection. Anions travel farther than cations in underground water systems since soils are primarily cation exchangers and retain the cations. Anion exchange techniques were used in the field and the laboratory to recover the desired radionuclides. Sample sizes ranged up to several thousand liters. This paper discusses the sample collection methods,analysis methods, and results obtained. The methods used were found to provide high sensitivity for groundwater studies. (auth)

Status of outdoor radioactive contamination at the Hanford Site

International Nuclear Information System (INIS)

McKinney, S.M.; Markes, B.M.

1994-12-01

This document summarizes the status of outdoor radioactive contamination near Hanford Site facilities and disposal sites. It defines the nature and areal extend of the radioactively contaminated areas and describes the historical, ongoing, and planned radiological monitoring and control activities. Radioactive waste has been disposed of to the soil column since shortly after the reactors and production facilities began operating. Radioactive liquid wastes were placed directly into the ground via liquid discharges to cribs, ponds, ditches, and reverse wells. Solid wastes were placed in trenches, burial vaults, and caissons. Although the Hanford Site covers 1,450 km 2 , the radioactively contaminated area is only about 36 km 2 or 2.5% of the original site. Over time, contamination has migrated from some of the waste management sites through various vectors (e.g., burrowing animals, deep-rooted vegetation, erosion, containment system failure) or has been deposited to the surface soil via spills and unplanned releases (e.g., line leaks/breaks, tank leaks, and stack discharges) and created areas of outdoor radioactivity both on and below the surface. Currently 26 km 2 are posted as surface contamination and 10 km 2 are posted as underground contamination

Acoustic imaging of underground storage tank wastes

International Nuclear Information System (INIS)

Mech, S.J.

1995-09-01

Acoustics is a potential tool to determine the properties of high level wastes stored in Underground Storage Tanks. Some acoustic properties were successfully measured by a limited demonstration conducted in 114-TX. This accomplishment provides the basis for expanded efforts to qualify techniques which depend on the acoustic properties of tank wastes. This work is being sponsored by the Department of Energy under the Office of Science and Technology. In FY-1994, limited Tank Waste Remediation Systems EM-30 support was available at Hanford and Los Alamos National Laboratory. The Massachusetts Institute of Technology (MIT) and Earth Resources Laboratory (ERL) were engaged for analysis support, and Elohi Geophysics, Inc. for seismic testing services. Westinghouse-Hanford Company provided the testing and training, supplied the special engineering and safety analysis equipment and procedures, and provided the trained operators for the actual tank operations. On 11/9/94, limited in-tank tests were successfully conducted in tank 114-TX. This stabilized Single Shell Tank was reported as containing 16.8 feet of waste, the lower 6.28 feet of which contained interstitial liquid. Testing was conducted over the lower 12 feet, between two Liquid Observation Wells thirty feet apart. The ''quick-look'' data was reviewed on-site by MIT and Elohi

Mining and milling of uranium ore: Indian scenario

International Nuclear Information System (INIS)

Bhasin, J.L.

2001-01-01

The occurrence of uranium minerals in Singhbhum Thrust belt of Eastern India has been known since 1937. In 1950, a team of geologists of the Atomic Minerals Division was assigned to closely examine this 160 km long belt. Since then, several occurrences of uranium have been found and a few of them have sufficient grade and tonnage for commercial exploitation. In 1967, the Government of India formed Uranium Corporation of India Ltd., under the administrative control of the Department of Atomic Energy, with the specific objective of mining and processing of uranium ore and produce uranium concentrates. At present the Corporation operates three underground uranium mines, one ore processing plant with expanded capacity, and two uranium recovery plants. Continuing investigations by the Atomic Mineral Division has discovered several new deposits and favourable areas. The most notable is the large Domiasiat deposit of the sandstone type found in the State of Meghalaya. This deposit is now being considered for commercial exploitation using the in-situ leaching technology. (author)

Hanford immobilized low-activity tank waste performance assessment

International Nuclear Information System (INIS)

Mann, F.M.

1998-01-01

The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis

Hanford immobilized low-activity tank waste performance assessment

Energy Technology Data Exchange (ETDEWEB)

Mann, F.M.

1998-03-26

The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis

GTS Duratek, Phase I Hanford low-level waste melter tests: 100-kg melter offgas report

International Nuclear Information System (INIS)

Eaton, W.C.

1995-11-01

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the 100-kg melter offgas report on testing performed by GTS Duratek, Inc., in Columbia, Maryland. GTS Duratek (one of the seven vendors selected) was chosen to demonstrate Joule heated melter technology under WHC subcontract number MMI-SVV-384215. The document contains the complete offgas report on the 100-kg melter as prepared by Parsons Engineering Science, Inc. A summary of this report is also contained in the GTS Duratek, Phase I Hanford Low-Level Waste Melter Tests: Final Report (WHC-SD-WM-VI-027)

Control system design for robotic underground storage tank inspection systems

International Nuclear Information System (INIS)

Kiebel, G.R.

1994-09-01

Control and data acquisition systems for robotic inspection and surveillance systems used in nuclear waste applications must be capable, versatile, and adaptable to changing conditions. The nuclear waste remediation application is dynamic -- requirements change as public policy is constantly re-examined and refocused, and as technology in this area advances. Control and data acquisition systems must adapt to these changing conditions and be able to accommodate future missions, both predictable and unexpected. This paper describes the control and data acquisition system for the Light Duty Utility Arm (LDUA) System that is being developed for remote surveillance and inspection of underground storage tanks at the Hanford Site and other US Department of Energy (DOE) sites. It is a high-performance system which has been designed for future growth. The priority mission at the Hanford site is to retrieve the waste generated by 50 years of production from its present storage and process it for final disposal. The LDUA will help to gather information about the waste and the tanks it is stored in to better plan and execute the cleanup mission

Uranium mining in Saskatchewan

International Nuclear Information System (INIS)

Scales, M.

2006-01-01

The mines of northern Saskatchewan make Canada the worlds leading uranium producer in Canada supplied 29% of global demand, or 11.60 million tonnes of the metal in 2004. Here are two bright ideas - how to mine an orebody by neither pit nor underground method, and how to mine high-grade ore without miners - that Cogema and Cameco are pursuing in the Athabasca Basin

Problems of radiation safety at mined out uranium properties in Uzbekistan

International Nuclear Information System (INIS)

Gorlov, I.G.; Goldshtein, R.I.

2002-01-01

Republic of Uzbekistan was one of the main uranium production areas in former Soviet Union for more than 40 years. About 150 uranium production facilities have been constructed for that time in connection with hydrothermal and sedimentary-metamorphic deposits of the fold basement and stratal-infiltration deposits of the sedimentary cover. 18 of these facilities are located in Tadzhikistan and Kyrgyzstan along the boundary with Uzbekistan. Exploration and operation activities in the deposits located in the fold basement were in general in form of mining. It was resulted in essential violation of landscape, development of various underground excavations, damps, tailing impoundments, lower grade stockpiles. All these need large volume of radioactive decontamination and restoration activities. 54 sites from 67 (80%) located in the territory of Uzbekistan need radioactive decontamination and restoration now. Very serious radiation settings have occurred in some of these sites nowadays. Radioactive dumps of Cherkesar-I and Cherkesar-II mined out uranium deposits are out of any control in Fergana valley in Pap region of Namangan province. The radioactive materials are collected in dumps covered with neutral ground. The cover is washed out in some places by rains. Intensity of gamma radiation is 300 to 450 μr/h, radon exhalation is up to 7 Bk/m 2 *sec (while the normal level is up to 1 Bk/m 2 *sec). Water runs out from mothballed mines and its microelement composition is close to the composition of the technological solution. The water contains a number of very toxic elements (beryllium, manganese, iron, and aluminum). Water concentration of radionuclides is uranium - 23.4 Bk/1 (the normal level is 9.6), radon - 1433 (80), radium - 15.9 (0.94). The same set of the toxicants has been found in bottom sediment of a stream, its total alpha-activity reaches 35 to 81 KBk/kg. The spring water runs to a small valley and then to a village where the water is used for cattle

Elkon - development of new world class uranium mining center (v.2)

Energy Technology Data Exchange (ETDEWEB)

Boytsov, A., E-mail: boytsov@armz.ru [Atomredmetzoloto (ARMZ), Moscow (Russian Federation)

2010-07-01

The uranium deposits of Elkon district are located in the south of Republic of Sakha Yakutia. Deposits contain about 6% of the world known uranium resources: 342,409 tonnes of in situ or 288,768 tonnes of recoverable RAR + Inferred resources. Most significant uranium resources of Elkon district (261,768 tonnes) were identified within five deposits of Yuzhnaya zone. The uranium grade averages 0.15 %. Gold, silver and molybdenum are by-products. Principal resources are proposed to be mined by conventional underground method. Location, shape and dimensions of uranium orebodies are primarily controlled by NW-SE oriented and steeply SW dipping faults of Mesozoic age and surrounding pyrite-carbonate- potassium feldspar alteration zones. Country rocks are Archean gneisses. Deposits are of metasomatic geological type. Principal mineralization is represented by brannerite. The Yuzhnaya zone is about 20 km long. It was explored by underground workings and drill holes. Upper limit of orebodies is at a depth of between 200 m and 500 m. Depth persistence exceeds 2,000 m. Uranium mining enterprise Elkon was established in November 2007. It is a 100% Atomredmetzoloto (ARMZ) subsidiary. The planned producing capacity is up to 5,000 Mt U/year. It will perform the entire works related to uranium mining, milling, ore sorting, processing and uranium dioxide production. Technology of ore processing assumes primary radiometric sorting, thickening, sulphide flotation for gold concentrate extraction, subsequent autoclave sulphuric-acid uranium leaching from flotation tails and uranium adsorption onto resin, roasting and heap leaching for uranium from low grade ores, cyanide leaching of gold. Due to a considerable abundance of brannerite, the ore is classified as refractory. Elkon development include 4 main stages: feasibility study and infrastructure development (2009-2011), mine and mill construction (2012- 2015), pilot production (2013-2015), mine development and achieving full capacity

Elkon - development of new world class uranium mining center (v.1)

Energy Technology Data Exchange (ETDEWEB)

Boytsov, A., E-mail: boytsov@armz.ru [Atomredmetzoloto (ARMZ), Moscow (Russian Federation)

2010-07-01

'Full text:' The uranium deposits of Elkon district are located in the south of Republic of Sakha Yakutia. Deposits contain about 6% of the world known uranium resources: 342 409 tonnes of in situ or 288 768 tonnes of recoverable RAR + Inferred resources. Most significant uranium resources of Elkon district (261 768 tonnes) were identified within five deposits of Yuzhnaya zone. The uranium grade averages 0.15 %. Gold, silver and molybdenum are by-products. Principal resources are proposed to be mined by conventional underground method. Location, shape and dimensions of uranium orebodies are primarily controlled by NW-SE oriented and steeply SW dipping faults of Mesozoic age and surrounding pyrite-carbonate- potassium feldspar alteration zones. Country rocks are Archean gneisses. Deposits are of metasomatic geological type. Principal mineralization is represented by brannerite. The Yuzhnaya zone is about 20 km long. It was explored by underground workings and drill holes. Upper limit of orebodies is at a depth of between 200 m and 500 m. Depth persistence exceeds 2,000 m. Uranium mining enterprise Elkon was established in November 2007. It is a 100% Atomredmetzoloto (ARMZ) subsidiary. The planned producing capacity is up to 5000 Mt U/year. It will perform the entire works related to uranium mining, milling, ore sorting, processing and uranium dioxide production. Technology of ore processing assumes primary radiometric sorting, thickening, sulphide flotation for gold concentrate extraction, subsequent autoclave sulphuric-acid uranium leaching from flotation tails and uranium adsorption onto resin, roasting and heap leaching for uranium from low grade ores, cyanide leaching of gold. Due to a considerable abundance of brannerite, the ore is classified as refractory. Elkon development include 4 main stages: feasibility study and infrastructure development (2009-2011), mine and mill construction (2012- 2015), pilot production (2013-2015), mine development and

Elkon - development of new world class uranium mining center (v.1)

International Nuclear Information System (INIS)

Boytsov, A.

2010-01-01

'Full text:' The uranium deposits of Elkon district are located in the south of Republic of Sakha Yakutia. Deposits contain about 6% of the world known uranium resources: 342 409 tonnes of in situ or 288 768 tonnes of recoverable RAR + Inferred resources. Most significant uranium resources of Elkon district (261 768 tonnes) were identified within five deposits of Yuzhnaya zone. The uranium grade averages 0.15 %. Gold, silver and molybdenum are by-products. Principal resources are proposed to be mined by conventional underground method. Location, shape and dimensions of uranium orebodies are primarily controlled by NW-SE oriented and steeply SW dipping faults of Mesozoic age and surrounding pyrite-carbonate- potassium feldspar alteration zones. Country rocks are Archean gneisses. Deposits are of metasomatic geological type. Principal mineralization is represented by brannerite. The Yuzhnaya zone is about 20 km long. It was explored by underground workings and drill holes. Upper limit of orebodies is at a depth of between 200 m and 500 m. Depth persistence exceeds 2,000 m. Uranium mining enterprise Elkon was established in November 2007. It is a 100% Atomredmetzoloto (ARMZ) subsidiary. The planned producing capacity is up to 5000 Mt U/year. It will perform the entire works related to uranium mining, milling, ore sorting, processing and uranium dioxide production. Technology of ore processing assumes primary radiometric sorting, thickening, sulphide flotation for gold concentrate extraction, subsequent autoclave sulphuric-acid uranium leaching from flotation tails and uranium adsorption onto resin, roasting and heap leaching for uranium from low grade ores, cyanide leaching of gold. Due to a considerable abundance of brannerite, the ore is classified as refractory. Elkon development include 4 main stages: feasibility study and infrastructure development (2009-2011), mine and mill construction (2012- 2015), pilot production (2013-2015), mine development and achieving

Elkon - development of new world class uranium mining center (v.2)

International Nuclear Information System (INIS)

Boytsov, A.

2010-01-01

The uranium deposits of Elkon district are located in the south of Republic of Sakha Yakutia. Deposits contain about 6% of the world known uranium resources: 342,409 tonnes of in situ or 288,768 tonnes of recoverable RAR + Inferred resources. Most significant uranium resources of Elkon district (261,768 tonnes) were identified within five deposits of Yuzhnaya zone. The uranium grade averages 0.15 %. Gold, silver and molybdenum are by-products. Principal resources are proposed to be mined by conventional underground method. Location, shape and dimensions of uranium orebodies are primarily controlled by NW-SE oriented and steeply SW dipping faults of Mesozoic age and surrounding pyrite-carbonate- potassium feldspar alteration zones. Country rocks are Archean gneisses. Deposits are of metasomatic geological type. Principal mineralization is represented by brannerite. The Yuzhnaya zone is about 20 km long. It was explored by underground workings and drill holes. Upper limit of orebodies is at a depth of between 200 m and 500 m. Depth persistence exceeds 2,000 m. Uranium mining enterprise Elkon was established in November 2007. It is a 100% Atomredmetzoloto (ARMZ) subsidiary. The planned producing capacity is up to 5,000 Mt U/year. It will perform the entire works related to uranium mining, milling, ore sorting, processing and uranium dioxide production. Technology of ore processing assumes primary radiometric sorting, thickening, sulphide flotation for gold concentrate extraction, subsequent autoclave sulphuric-acid uranium leaching from flotation tails and uranium adsorption onto resin, roasting and heap leaching for uranium from low grade ores, cyanide leaching of gold. Due to a considerable abundance of brannerite, the ore is classified as refractory. Elkon development include 4 main stages: feasibility study and infrastructure development (2009-2011), mine and mill construction (2012- 2015), pilot production (2013-2015), mine development and achieving full capacity

Mechanisms of gas bubble retention and release: results for Hanford Waste Tanks 241-S-102 and 241-SY-103 and single-shell tank simulants

Energy Technology Data Exchange (ETDEWEB)

Gauglitz, P.A.; Rassat, S.D.; Bredt, P.R.; Konynenbelt, J.H.; Tingey, S.M.; Mendoza, D.P.

1996-09-01

Research at Pacific Northwest National Laboratory (PNNL) has probed the physical mechanisms and waste properties that contribute to the retention and release of flammable gases from radioactive waste stored in underground tanks at Hanford. This study was conducted for Westinghouse Hanford Company as part of the PNNL Flammable Gas Project. The wastes contained in the tanks are mixes of radioactive and chemical products, and some of these wastes are known to generate mixtures of flammable gases, including hydrogen, nitrous oxide, and ammonia. Because these gases are flammable, their retention and episodic release pose a number of safety concerns.

Mechanisms of gas bubble retention and release: results for Hanford Waste Tanks 241-S-102 and 241-SY-103 and single-shell tank simulants

International Nuclear Information System (INIS)

Gauglitz, P.A.; Rassat, S.D.; Bredt, P.R.; Konynenbelt, J.H.; Tingey, S.M.; Mendoza, D.P.

1996-09-01

Research at Pacific Northwest National Laboratory (PNNL) has probed the physical mechanisms and waste properties that contribute to the retention and release of flammable gases from radioactive waste stored in underground tanks at Hanford. This study was conducted for Westinghouse Hanford Company as part of the PNNL Flammable Gas Project. The wastes contained in the tanks are mixes of radioactive and chemical products, and some of these wastes are known to generate mixtures of flammable gases, including hydrogen, nitrous oxide, and ammonia. Because these gases are flammable, their retention and episodic release pose a number of safety concerns

Low temperature hydrothermal processing of organic contaminants in Hanford tank waste

International Nuclear Information System (INIS)

Jones, E.O.; Pederson, L.R.; Freeman, H.D.; Schmidt, A.J.; Babad, H.

1993-02-01

Batch and continuous flow reactor tests at Pacific Northwest Laboratory (PNL) have shown that organics similar to those present in the single-shell and double-shell underground storage tanks at Hanford can be decomposed in the liquid phase at relatively mild temperatures of 150 degree C to 350 degree C in an aqueous process known as hydrothermal processing (HTP). The organics will react with the abundant oxidants such s nitrite already present in the Hanford tank waste to form hydrogen, carbon dioxide, methane, and ammonia. No air or oxygen needs to be added to the system. Ferrocyanides and free cyanide will hydrolyze at similar temperatures to produce formate and ammonia and may also react with nitrates or other oxides. During testing, the organic carbon was transformed first to oxalate at∼310 degree C and completely oxidized to carbonate at ∼350 degree C accompanied by hydroxide consumption. Solids were formed at higher temperatures, causing a small-diameter outlet tube to plug. The propensity for plugging was reduced by diluting the feed with concentrated hydroxide

DOE management of high-level waste at the Hanford Site

International Nuclear Information System (INIS)

1993-01-01

Approximately 60 million gallons of high-level radioactive waste--caustic liquids, slurries, saltcakes, and sludges--are stored in underground tanks at the Department of Energy's Hanford Site. At least one-third of the tanks are known to have leaked waste into the enviroranent, and there are many unresolved tank safety issues. In order to resolve the environmental and safety concerns, the Department plans to retrieve the waste, immobilize it, and dispose of it in a permanent geologic repository. Processing all of the tank waste in this manner could cost $40 billion, including $1.2 billion to construct the Hanford Waste Vitrification Plant. The purpose of our audit was to examine the reasons for cost estimate increases and schedule delays on the Hanford vitrification program. We also wanted to report on outstanding technical, safety, and environmental issues that could make the project even more costly and further delay its completion. We found that the Department managed the Hanford remediation system as a number of separate projects not fully integrated into one major system acquisition. Total costs have, therefore, been obscured, and the Department has not yet clearly defined system requirements or developed overall cost and schedule baselines. This lack of visibility could result in additional cost growth and schedule delays. We also noted a vast array of technical uncertainties, including tank safety and inadequate information about the makeup of tank waste, that could significantly affect the program's cost and ultimate success. To increase visibility of program cost and schedule, we are recommending that all separate projects relating to tank waste be included in a single major system acquisition, and that the Department complete its ongoing baselining effort to the extent practical before making major funding commitments. Management concurred with our finding and recommendations

Screening the Hanford tanks for trapped gas

International Nuclear Information System (INIS)

Whitney, P.

1995-10-01

The Hanford Site is home to 177 large, underground nuclear waste storage tanks. Hydrogen gas is generated within the waste in these tanks. This document presents the results of a screening of Hanford's nuclear waste storage tanks for the presence of gas trapped in the waste. The method used for the screening is to look for an inverse correlation between waste level measurements and ambient atmospheric pressure. If the waste level in a tank decreases with an increase in ambient atmospheric pressure, then the compressibility may be attributed to gas trapped within the waste. In this report, this methodology is not used to estimate the volume of gas trapped in the waste. The waste level measurements used in this study were made primarily to monitor the tanks for leaks and intrusions. Four measurement devices are widely used in these tanks. Three of these measure the level of the waste surface. The remaining device measures from within a well embedded in the waste, thereby monitoring the liquid level even if the liquid level is below a dry waste crust. In the past, a steady rise in waste level has been taken as an indicator of trapped gas. This indicator is not part of the screening calculation described in this report; however, a possible explanation for the rise is given by the mathematical relation between atmospheric pressure and waste level used to support the screening calculation. The screening was applied to data from each measurement device in each tank. If any of these data for a single tank indicated trapped gas, that tank was flagged by this screening process. A total of 58 of the 177 Hanford tanks were flagged as containing trapped gas, including 21 of the 25 tanks currently on the flammable gas watch list

Disposal of Hanford site tank wastes

International Nuclear Information System (INIS)

Kupfer, M.J.

1993-09-01

Between 1943 and 1986, 149 single-shell tanks (SSTs) and 28 double-shell tanks (DSTs) were built and used to store radioactive wastes generated during reprocessing of irradiated uranium metal fuel elements at the U.S. Department of Energy (DOE) Hanford Site in Southeastern Washington state. The 149 SSTs, located in 12 separate areas (tank farms) in the 200 East and 200 West areas, currently contain about 1.4 x 10 5 m 3 of solid and liquid wastes. Wastes in the SSTs contain about 5.7 x 10 18 Bq (170 MCi) of various radionuclides including 90 Sr, 99 Tc, 137 Cs, and transuranium (TRU) elements. The 28 DSTs also located in the 200 East and West areas contain about 9 x 10 4 m 3 of liquid (mainly) and solid wastes; approximately 4 x 10 18 Bq (90 MCi) of radionuclides are stored in the DSTs. Important characteristics and features of the various types of SST and DST wastes are described in this paper. However, the principal focus of this paper is on the evolving strategy for final disposal of both the SST and DST wastes. Also provided is a chronology which lists key events and dates in the development of strategies for disposal of Hanford Site tank wastes. One of these strategies involves pretreatment of retrieved tank wastes to separate them into a small volume of high-level radioactive waste requiring, after vitrification, disposal in a deep geologic repository and a large volume of low-level radioactive waste which can be safely disposed of in near-surface facilities at the Hanford Site. The last section of this paper lists and describes some of the pretreatment procedures and processes being considered for removal of important radionuclides from retrieved tank wastes

Historical tank content estimate for the southeast quadrant of the Hanford 200 Areas

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

This document provides historical evaluations of the radioactive and mixed waste stored in the Hanford site underground double-shell tanks. A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy and Department of Defense contractors. The historical data will supplement information that is currently being gathered from core sampling. Historical waste transfer and level data, tank physical information, temperature data, and sampling data have been compiled for this report and supporting documents.

Historical tank content estimate for the southeast quadrant of the Hanford 200 Areas

International Nuclear Information System (INIS)

1995-06-01

This document provides historical evaluations of the radioactive and mixed waste stored in the Hanford site underground double-shell tanks. A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy and Department of Defense contractors. The historical data will supplement information that is currently being gathered from core sampling. Historical waste transfer and level data, tank physical information, temperature data, and sampling data have been compiled for this report and supporting documents

Hanford External Dosimetry Program

International Nuclear Information System (INIS)

Fix, J.J.

1990-10-01

This document describes the Hanford External Dosimetry Program as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy (DOE) and its Hanford contractors. Program services include administrating the Hanford personnel dosimeter processing program and ensuring that the related dosimeter data accurately reflect occupational dose received by Hanford personnel or visitors. Specific chapters of this report deal with the following subjects: personnel dosimetry organizations at Hanford and the associated DOE and contractor exposure guidelines; types, characteristics, and procurement of personnel dosimeters used at Hanford; personnel dosimeter identification, acceptance testing, accountability, and exchange; dosimeter processing and data recording practices; standard sources, calibration factors, and calibration processes (including algorithms) used for calibrating Hanford personnel dosimeters; system operating parameters required for assurance of dosimeter processing quality control; special dose evaluation methods applied for individuals under abnormal circumstances (i.e., lost results, etc.); and methods for evaluating personnel doses from nuclear accidents. 1 ref., 14 figs., 5 tabs

Discussion for management of ventilation system in uranium mines

International Nuclear Information System (INIS)

Li Xianjie; Ren Jianjun; Hu Penghua

2014-01-01

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

Advancing the US Department of Energy's Technologies through the Underground Storage Tank: Integrated Demonstration Program

International Nuclear Information System (INIS)

Gates, T.E.

1993-01-01

The principal objective of the Underground Storage Tank -- Integrated Demonstration Program is the demonstration and continued development of technologies suitable for the remediation of waste stored in underground storage tanks. The Underground Storage Tank Integrated Demonstration Program is the most complex of the integrated demonstration programs established under the management of the Office of Technology Development. The Program has the following five participating sites: Oak Ridge, Idaho, Fernald, Savannah River, and Hanford. Activities included within the Underground Storage Tank -- Integrated Demonstration are (1) characterizating radioactive and hazardous waste constituents, (2) determining the need and methodology for improving the stability of the waste form, (3) determining the performance requirements, (4) demonstrating barrier performance by instrumented field tests, natural analog studies, and modeling, (5) determining the need and method for destroying and stabilizing hazardous waste constituents, (6) developing and evaluating methods for retrieving, processing (pretreatment and treatment), and storing the waste on an interim basis, and (7) defining and evaluating waste packages, transportation options, and ultimate closure techniques including site restoration. The eventual objective is the transfer of new technologies as a system to full-scale remediation at the US Department of Energy complexes and sites in the private sector

HANFORD TANK CLEANUP UPDATE MAY 2009

International Nuclear Information System (INIS)

Holloway, J.N.

2009-01-01

Retrieval of waste from single-shell tank C-110 resumed in January making it the first waste retrieval operation for WRPS since taking over Hanford's Tank Operations Contract last October. Now, with approximately 90 percent of the waste removed, WRPS believes that modified sluicing has reached the limits of the technology to remove any further waste and is preparing documentation for use in decision making about any future retrieval actions. Tank C-110 is located in C Fann near the center of the Hanford Site. It is a 530,000 gallon tank, built in 1946, and held approximately 126,000 gallons of sludge and other radioactive and chemical waste materials when retrieval resumed. Modified sluicing technology uses liquid waste from a nearby double-shell tank to break up, dissolve and mobilize the solid material so it can be pumped. Because of the variety of waste fon11S, sluicing is often not able to remove all of the waste. The remaining waste will next be sampled for analysis, and results will be used to guide decisions regarding future actions. Work is moving rapidly in preparation to retrieve waste from a second single-shell tank this summer and transfer it to safer double-shell tank storage. Construction activities necessary to retrieve waste from Tank C-104, a 530,000 gallon tank built in 1943, are approximately 60 percent complete as WRPS maintains its focus on reducing the risk posed by Hanford's aging single-shell waste tanks. C-104 is one of Hanford's oldest radioactive and chemical waste storage tanks, containing approximately 263,000 gallons of wet sludge with a top layer that is dry and powdery. This will be the largest sludge volume retrieval ever attempted using modified sluicing technology. Modified sluicing uses high pressure water or liquid radioactive waste sprayed from nozzles above the waste. The liquid dissolves and/or mobilizes the waste so it can be pumped. In addition to other challenges, tank C-104 contains a significant amount of plutonium and

Preliminary survey of separations technology applicable to the pretreatment of Hanford tank waste (1992--1993)

International Nuclear Information System (INIS)

Lawrence, W.E.; Kurath, D.E.

1994-04-01

The US Department of Energy has established the Tank Waste Remediation System (TWRS) to manage and dispose of radioactive wastes stored at the Hanford Site. Within this program are evaluations of pretreatment system alternatives through literature reviews. The information in this report was collected as part of this project at Pacific Northwest Laboratory. A preliminary survey of literature on separations recently entered into the Hanford electronic databases (1992--1993) that have the potential for pretreatment of Hanford tank waste was conducted. Separation processes that can assist in the removal of actinides (uranium, plutonium, americium), lanthanides, barium, 137 Cs, 90 Sr, 129 I, 63 Ni, and 99 Tc were evaluated. Separation processes of interest were identified through literature searches, journal reviews, and participation in separation technology conferences. This report contains brief descriptions of the potential separation processes, the extent and/or selectivity of the separation, the experimental conditions, and observations. Information was collected on both national and international separation studies to provide a global perspective on recent research efforts

Estimation of radon daughter levels in the ventilation planning of an underground uranium mine

International Nuclear Information System (INIS)

Gan, T.H.; Wise, K.N.; Leach, V.A.

1981-01-01

Diffusion parameters determined by laboratory measurements can be utilized for predictions of radon daughter exposures in underground mining environments, as well as providing data for ventilation planning purposes. Wherever possible field measured data for the various diffusion parameters should be used. Underground mining methods, the tunnel model and diffusion theory are considered

Report for Treating Hanford LAW and WTP SW Simulants: Pilot Plant Mineralizing Flowsheet

International Nuclear Information System (INIS)

Olson, Arlin

2012-01-01

The US Department of Energy is responsible for managing the disposal of radioactive liquid waste in underground storage tanks at the Hanford site in Washington State. The Hanford waste treatment and immobilization plant (WPT) will separate the waste into a small volume of high level waste (HLW), containing most of the radioactive constituents, and a larger volume of low activity waste (LAW), containing most of the non-radioactive chemical and hazardous constituents. The HLW and LAW will be converted into immobilized waste forms for disposal. Currently there is inadequate LAW vitrification capacity planned at the WTP to complete the mission within the required timeframe. Therefore additional LAW capacity is required. One candidate supplemental treatment technology is the fluidized bed steam reformer process (FBSR). This report describes the demonstration testing of the FBSR process using a mineralizing flowsheet for treating simulated Hanford LAW and secondary waste from the WTP (WTP SW). The FBSR testing project produced leach-resistant solid products and environmentally compliant gaseous effluents. The solid products incorporated normally soluble ions into an alkali alumino-silicate (NaS) mineral matrix. Gaseous emissions were found to be within regulatory limits. Cesium and rhenium were captured in the mineralized products with system removal efficiencies of 99.999% and 99.998 respectively. The durability and leach performance of the FBSR granular solid were superior to the low activity reference material (LMR) glass standards. Normalized product consistency test (PCT) release rates for constituents of concern were approximately 2 orders of magnitude less than that of sodium in the Hanford glass [standard].

Report for Treating Hanford LAW and WTP SW Simulants: Pilot Plant Mineralizing Flowsheet

Energy Technology Data Exchange (ETDEWEB)

Arlin Olson

2012-02-28

The US Department of Energy is responsible for managing the disposal of radioactive liquid waste in underground storage tanks at the Hanford site in Washington State. The Hanford waste treatment and immobilization plant (WPT) will separate the waste into a small volume of high level waste (HLW), containing most of the radioactive constituents, and a larger volume of low activity waste (LAW), containing most of the non-radioactive chemical and hazardous constituents. The HLW and LAW will be converted into immobilized waste forms for disposal. Currently there is inadequate LAW vitrification capacity planned at the WTP to complete the mission within the required timeframe. Therefore additional LAW capacity is required. One candidate supplemental treatment technology is the fluidized bed steam reformer process (FBSR). This report describes the demonstration testing of the FBSR process using a mineralizing flowsheet for treating simulated Hanford LAW and secondary waste from the WTP (WTP SW). The FBSR testing project produced leach-resistant solid products and environmentally compliant gaseous effluents. The solid products incorporated normally soluble ions into an alkali alumino-silicate (NaS) mineral matrix. Gaseous emissions were found to be within regulatory limits. Cesium and rhenium were captured in the mineralized products with system removal efficiencies of 99.999% and 99.998 respectively. The durability and leach performance of the FBSR granular solid were superior to the low activity reference material (LMR) glass standards. Normalized product consistency test (PCT) release rates for constituents of concern were approximately 2 orders of magnitude less than that of sodium in the Hanford glass [standard].

Hanford Site Groundwater Monitoring for Fiscal Year 2003

Energy Technology Data Exchange (ETDEWEB)

Hartman, Mary J.; Morasch, Launa F.; Webber, William D.

2004-04-12

This report presents the results of groundwater and vadose zone monitoring and remediation for fiscal year 2003 (October 2002 through September 2003) on the U.S. Department of Energy's Hanford Site, Washington. The most extensive contaminant plumes in groundwater are tritium, iodine-129, and nitrate, which all had multiple sources and are very mobile in groundwater. The largest portions of these plumes are migrating from the central Hanford Site to the southeast, toward the Columbia River. Concentrations of tritium, nitrate, and some other contaminants continued to exceed drinking water standards in groundwater discharging to the river in some locations. However, contaminant concentrations in river water remained low and were far below standards. Carbon tetrachloride and associated organic constituents form a relatively large plume beneath the central part of the Hanford Site. Hexavalent chromium is present in smaller plumes beneath the reactor areas along the river and beneath the central part of the site. Strontium-90 exceeds standards beneath all but one of the reactor areas, and technetium-99 and uranium are present in the 200 Areas. Uranium exceeds standards in the 300 Area in the south part of the Hanford Site. Minor contaminant plumes with concentrations greater than standards include carbon-14, cesium-137, cis-1,2-dichloroethene, cyanide, fluoride, plutonium, and trichloroethene. Monitoring for the ''Comprehensive Environmental Response, Compensation, and Liability Act'' is conducted in 11 groundwater operable units. The purpose of this monitoring is to define and track plumes and to monitor the effectiveness of interim remedial actions. Interim groundwater remediation in the 100 Areas continued with the goal of reducing the amount of chromium (100-K, 100-D, and 100-H) and strontium-90 (100-N) reaching the Columbia River. The objective of two interim remediation systems in the 200 West Area is to prevent the spread of carbon

Further new activities at uranium deposit Rozna, Czech Republic

International Nuclear Information System (INIS)

Toman, F.; Pavel, V.

2014-01-01

Mining of uranium ore has been running at Rozna deposit for 56 years, since 1957. Extraction of uranium ore is currently performed in the mining field of blind shaft R7S. Top slicing and caving under the artificial roof method is used for the extraction. Uranium ore mined in the Rozna deposit is treated at a chemical treatment plant (a mill) situated in the close vicinity of the Rozna mine. In the mill, uranium is extracted from the crushed and ground ore by alkaline leaching. The uranium is then removed from the solution by sorption on resin; the next steps are precipitation and drying. Alkaline leaching is applied at the atmospheric pressure and the temperature of 80 °C. The final product of the milling is ammonium diuranate (NH 4 ) 2 U 2 O 7 , which is further treated into a fuel for nuclear power plants in conversion facilities abroad. The milling is carried on under the condition of the closed cycle of technology water. Due to the positive annual precipitation balance, the over balance of mill water in tailings pond has to be purified before discharging into a river. Forced evaporation and membrane processes (electrodialysis and reverse osmosis) are used to purify the water. New activities are searched and carried out with consequence of gradual decreasing of the uranium production. The main target and also benefit of this is the using of skilled human resources in the mine Rozna I and entry able underground spaces. Geological exploration works for a construction of the underground gas storage were started on 21st level of shaft R7S three years ago. New horizontal galleries with profile 9 m 2 were driven during geological exploration works. Exploratory holes with length 100m were drilled. Sampling of rocks for geochemical, geomechanical and petrographic tests were carried out. So far 1264.9 m of exploration galleries and 1130 m exploration drill holes have been made. Geological exploration works for construction of underground research workplace on 12th level

Hanford Site groundwater monitoring for Fiscal Year 1997

Energy Technology Data Exchange (ETDEWEB)

Hartman, M.J.; Dresel, P.E. [eds.] [and others

1998-02-01

This report presents the results of groundwater and vadose-zone monitoring for fiscal year (FY) 1997 on the Hanford Site, Washington. Soil-vapor extraction continued in the 200-West Area to remove carbon tetrachloride from the vadose zone. Characterization and monitoring of the vadose zone comprised primarily spectral gamma logging, soil-vapor monitoring, and analysis and characterization of sediments sampled below a vadose-zone monitoring well. Source-term analyses for strontium-90 in 100-N Area vadose-zone sediments were performed using recent groundwater-monitoring data and knowledge of strontium`s ion-exchange properties. Water-level monitoring was performed to evaluate groundwater-flow directions, to track changes in water levels, and to relate such changes to evolving disposal practices. Water levels over most of the Hanford Site continued to decline between June 1996 and June 1997. Water levels near the Columbia River increased during this period because the river stage was unusually high. Groundwater chemistry was monitored to track the extent of contamination, to note trends, and to identify emerging groundwater-quality problems. The most widespread radiological contaminant plumes were tritium and iodine-129. Concentrations of technetium-99, uranium, strontium-90, and carbon-14 also exceeded drinking water standards in smaller plumes. Plutonium and cesium-137 exceeded standards only near the 216-B-5 injection well. Derived concentration guide levels specified in U.S. Department of Energy Order 5400.5 were exceeded for tritium, uranium, strontium-90, and plutonium in small plumes or single wells. Nitrate is the most extensive chemical contaminant. Carbon tetrachloride, chloroform, chromium, cis-1,2-dichloroethylene, fluoride, and trichloroethylene also were present in smaller areas at levels above their maximum contaminant levels. Cyanide concentrations were elevated in one area but were below the maximum contaminant level.

Hanford Site groundwater monitoring for Fiscal Year 1997

International Nuclear Information System (INIS)

Hartman, M.J.; Dresel, P.E.

1998-02-01

This report presents the results of groundwater and vadose-zone monitoring for fiscal year (FY) 1997 on the Hanford Site, Washington. Soil-vapor extraction continued in the 200-West Area to remove carbon tetrachloride from the vadose zone. Characterization and monitoring of the vadose zone comprised primarily spectral gamma logging, soil-vapor monitoring, and analysis and characterization of sediments sampled below a vadose-zone monitoring well. Source-term analyses for strontium-90 in 100-N Area vadose-zone sediments were performed using recent groundwater-monitoring data and knowledge of strontium's ion-exchange properties. Water-level monitoring was performed to evaluate groundwater-flow directions, to track changes in water levels, and to relate such changes to evolving disposal practices. Water levels over most of the Hanford Site continued to decline between June 1996 and June 1997. Water levels near the Columbia River increased during this period because the river stage was unusually high. Groundwater chemistry was monitored to track the extent of contamination, to note trends, and to identify emerging groundwater-quality problems. The most widespread radiological contaminant plumes were tritium and iodine-129. Concentrations of technetium-99, uranium, strontium-90, and carbon-14 also exceeded drinking water standards in smaller plumes. Plutonium and cesium-137 exceeded standards only near the 216-B-5 injection well. Derived concentration guide levels specified in U.S. Department of Energy Order 5400.5 were exceeded for tritium, uranium, strontium-90, and plutonium in small plumes or single wells. Nitrate is the most extensive chemical contaminant. Carbon tetrachloride, chloroform, chromium, cis-1,2-dichloroethylene, fluoride, and trichloroethylene also were present in smaller areas at levels above their maximum contaminant levels. Cyanide concentrations were elevated in one area but were below the maximum contaminant level

Hanford wells

International Nuclear Information System (INIS)

Chamness, M.A.; Merz, J.K.

1993-08-01

Records describing wells located on or near the Hanford Site have been maintained by Pacific Northwest Laboratory and the operating contractor, Westinghouse Hanford Company. In support of the Ground-Water Surveillance Project, portions of the data contained in these records have been compiled into the following report, which is intended to be used by those needing a condensed, tabular summary of well location and basic construction information. The wells listed in this report were constructed over a period of time spanning almost 70 years. Data included in this report were retrieved from the Hanford Envirorunental Information System (HEIS) database and supplemented with information not yet entered into HEIS. While considerable effort has been made to obtain the most accurate and complete tabulations possible of the Hanford Site wells, omissions and errors may exist. This document does not include data on lithologic logs, ground-water analyses, or specific well completion details

Hanford Site Development Plan

International Nuclear Information System (INIS)

Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

1993-05-01

The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides an existing and future land use plan for the Hanford Site. The HSDP is updated annually in accordance with DOE Order 4320.1B, Site Development Planning, to reflect the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

A Geophysical Characterization & Monitoring Strategy for Determining Hydrologic Processes in the Hyporheic Corridor at the Hanford 300-Area

Energy Technology Data Exchange (ETDEWEB)

Slater, Lee; Day-Lewis, Frederick; Lane, John; Versteeg, Roelof; Ward, Anderson; Binley, Andrew; Johnson, Timothy; Ntarlagiannis, Dimitrios

2011-08-31

The primary objective of this research was to advance the prediction of solute transport between the Uranium contaminated Hanford aquifer and the Columbia River at the Hanford 300 Area by improving understanding of how fluctuations in river stage, combined with subsurface heterogeneity, impart spatiotemporal complexity to solute exchange along the Columbia River corridor. Our work explored the use of continuous waterborne electrical imaging (CWEI), in conjunction with fiber-optic distributed temperature sensor (FO-DTS) and time-lapse resistivity monitoring, to improve the conceptual model for how groundwater/surface water exchange regulates uranium transport. We also investigated how resistivity and induced polarization can be used to generate spatially rich estimates of the variation in depth to the Hanford-Ringold (H-R) contact between the river and the 300 Area Integrated Field Research Challenge (IFRC) site. Inversion of the CWEI datasets (a data rich survey containing {approx}60,000 measurements) provided predictions of the distributions of electrical resistivity and polarizability, from which the spatial complexity of the primary hydrogeologic units along the river corridor was reconstructed. Variation in the depth to the interface between the overlying coarse-grained, high permeability Hanford Formation and the underlying finer-grained, less permeable Ringold Formation, an important contact that limits vertical migration of contaminants, has been resolved along {approx}3 km of the river corridor centered on the IFRC site in the Hanford 300 Area. Spatial variability in the thickness of the Hanford Formation captured in the CWEI datasets indicates that previous studies based on borehole projections and drive-point and multi-level sampling likely overestimate the contributing area for uranium exchange within the Columbia River at the Hanford 300 Area. Resistivity and induced polarization imaging between the river and the 300 Area IFRC further imaged spatial

Environmental status of the Hanford Site for CY 1983

International Nuclear Information System (INIS)

Price, K.R.; Blumer, P.J.; Carlile, J.M.V.; Dirkes, R.L.; Trevathan, M.S.

1984-08-01

Samples of air, surface water, soil, vegetation, and wildlife were collected and external penetrating radiation dose measurements were made in the vicinity of the major operating areas on the Hanford Site. Most samples were analyzed for radioactive constituents including 3 H, 14 C, 85 Kr, 90 Sr, 241 Am, plutonium isotopes, natural uranium, and gamma-emitting radionuclides. In addition, site roads, railroad tracks, and burial ground were surveyed periodically to detect any abnormal conditions or unusual levels of radioactivity. Radioactive and nonradioactive waste discharges and environmentally-related unusual occurrences reported for the major operating areas were reviewed and summarized. 14 references, 10 figures, 22 tables

REE geochemistry and genesis of Daxin uranium deposit

International Nuclear Information System (INIS)

Li Zhixing; Qi Fucheng; He Zhongbo; Zhang Zilong

2011-01-01

Through the analysis on typical REE parameters,chondrite-normalized REE patterns and hierarchical cluster analysis of rocks in the structural-geochemical zonation in Daxin uranium deposit, the paper discusses the uranium source and genesis. The study shows that the uranium source mainly came from Cambrian System. The Devonian System is maily as the favorable room for saving ores in addition to pre-concentrated room for uranium. Underground water resulted from early and late Yanshanian movement and the heating of volcanic rock was turned into geothermal water and it was moved upward by the force of tectonic movement. The geothermal water mainly extracted active uranium from the Cambrian rocks, then moved upward along main regional fault (F2) connecting the Cambrian rocks and the Devonian rocks until it arrived in structural fracture zone which was controlled by secondary faults (F13, F23, F33). At last, the uranium element in geothermal water was precipitated and concentrated into the uranium deposit in reducing environment of enriched organic material and pyrite. (authors)

Methods and Models of the Hanford Internal Dosimetry Program, PNNL-MA-860

Energy Technology Data Exchange (ETDEWEB)

Carbaugh, Eugene H.; Bihl, Donald E.; Maclellan, Jay A.; Antonio, Cheryl L.; Hill, Robin L.

2009-09-30

The Hanford Internal Dosimetry Program (HIDP) provides internal dosimetry support services for operations at the Hanford Site. The HIDP is staffed and managed by the Radiation and Health Technology group, within the Pacific Northwest National Laboratory (PNNL). Operations supported by the HIDP include research and development, the decontamination and decommissioning of facilities formerly used to produce and purify plutonium, and waste management activities. Radioelements of particular interest are plutonium, uranium, americium, tritium, and the fission and activation product radionuclides 137Cs, 90Sr, and 60Co. This manual describes the technical basis for the design of the routine bioassay monitoring program and for assessment of internal dose. The purposes of the manual are as follows: • Provide assurance that the HIDP derives from a sound technical base. • Promote the consistency and continuity of routine program activities. • Provide a historical record. • Serve as a technical reference for radiation protection personnel. • Aid in identifying and planning for future needs.

Analysis of genomic instability in bronchial cells from uranium miners

International Nuclear Information System (INIS)

Neft, R.E.; Belinsky, S.A.; Gilliland, F.D.; Lechner, J.F.

1994-01-01

Epidemiological studies show that underground uranium miners have a radon progeny exposure-dependent increased risk for developing lung cancer. The odds ratio for lung cancer in uranium miners increase for all cumulative exposures above 99 Working Level Months. In addition, there is a strong multiplicative effect of cigarette smoking on the development of lung cancer in uranium miners. The purpose of this investigation was to determine whether or not early genetic changes, as indicated by genomic instability, can be detected in bronchial cells from uranium miners. Investigations of this nature may serve as a means of discovering sub-clinical disease and could lead to earlier detection of lung cancer and a better prognosis for the patient

Radiometric surveys in underground environment

Science.gov (United States)

Bochiolo, Massimo; Chiozzi, Paolo; Verdoya, Massimo; Pasquale, Vincenzo

2010-05-01

Due to their ability to travel through the air for several metres, gamma-rays emitted from natural radioactive elements can be successfully used in surveys carried out both with airborne and ground equipments. Besides the concentration of the radio-elements contained in rocks and soils and the intrinsic characteristics of the gamma-ray detector, the detected count rate depends on the solid angle around the spectrometer. On a flat outcrop, ground spectrometry detects the radiation ideally produced by a cylindrical mass of rock of about two metres in diameter and thickness of about half a meter. Under these geometrical conditions, the natural radioactivity can be easily evaluated. With operating conditions different from the standard ones, such as at the edge of an escarpment, the count rate halves because of the missing material, whereas in the vicinity of a rock wall the count rate will increase. In underground environment, the recorded count rate may even double and the in situ assessment of the concentration of radio-elements may be rather difficult, even if the ratios between the different radio-elements may not be affected. We tested the applicability of gamma-ray spectrometry for rapid assessment of the potential hazard levels related to radon and radiation dose rate in underground environment. A mine shaft, located in a zone of uranium enrichment in Liguria (Italy), has been investigated. A preliminary ground radiometric survey was carried out to define the extent of the ore deposit. Then, the radiometric investigation was focussed on the mine shaft. Due to rock mass above the shaft vault, the background gamma radiation can be considered of negligible influence on measurements. In underground surveys, besides deviations from a flat geometry, factors controlling radon exhalation, emanation and stagnation, such as fractures, water leakage and the presence of ventilation, should be carefully examined. We attempted to evaluate these control factors and collected

International uranium production. An eastern Canadian perspective

International Nuclear Information System (INIS)

Albino, G.R.

1984-01-01

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

Decision and systems analysis for underground storage tank waste retrieval systems and tank waste remediation system

International Nuclear Information System (INIS)

Bitz, D.A.; Berry, D.L.; Jardine, L.J.

1994-03-01

Hanford's underground tanks (USTs) pose one of the most challenging hazardous and radioactive waste problems for the Department of Energy (DOE). Numerous schemes have been proposed for removing the waste from the USTs, but the technology options for doing this are largely unproven. To help assess the options, an Independent Review Group (IRG) was established to conduct a broad review of retrieval systems and the tank waste remediation system. The IRG consisted of the authors of this report

Chemical compatibility study of Cooley L18KU, Herculite, and Elephant Mat with Hanford tank waste

International Nuclear Information System (INIS)

Mercado, J.E.

1998-01-01

An independent chemical compatibility review of various wrapping and absorbent/padding materials was conducted to evaluate resistance to chemicals and constituents present in liquid waste from the Hanford underground tanks. These materials will be used to wrap long-length contaminated equipment when such equipment is removed from the tanks and prepared for transportation and subsequent disposal or storage. The materials studied were Cooley L18KU, Herculite, and Elephant Mat. The study concludes that these materials are appropriate for use in this application

Retrospective chromosome aberration analysis of former uranium miners

International Nuclear Information System (INIS)

Meszaros, G.; Bognar, G.; Koeteles, G. J.

2003-01-01

In this paper we present our data collected in the period of 1981-1985 on 165 persons exposed by different radon concentrations expressed in working level month (WLM) units from 100 up to 600. Following the decommissioning of the uranium mine in Hungary in 1997 cytogenetic status of 131 persons were within a follow-up-study of their health conditions initiated by the Hungarian Academy of Science. The persons have terminated their underground activities 5 to 20 years before testing. The comparison of the two datasets suggest a long-term persistence of cytogenetic alterations above the population average values in large percentages of persons investigated. The frequency of chromosome aberrations of uranium miners was found increased in function of their exposure to radon. The comparison of the miner's categories 20 years ago and in the recent years demonstrated the long-term existence of aberrations for many years after completion of underground mining activities. (authors)

Evaluation of Soil Flushing for Application to the Deep Vadose Zone in the Hanford Central Plateau

Energy Technology Data Exchange (ETDEWEB)

Truex, Michael J.; Oostrom, Martinus; Zhang, Z. F.; Carroll, Kenneth C.; Schramke, Janet A.; Wietsma, Thomas W.; Tartakovsky, Guzel D.; Gordon, Kathryn A.; Last, George V.

2010-11-01

Soil flushing was included in the Deep Vadose Zone Treatability Test Plan for the Hanford Central Plateau as a technology with the potential to remove contaminants from the vadose zone. Soil flushing operates through the addition of water, and if necessary an appropriate mobilizing agent, to mobilize contaminants and flush them from the vadose zone and into the groundwater where they are subsequently captured by a pump-and-treat system. There are uncertainties associated with applying soil flushing technology to contaminants in the deep vadose zone at the Hanford Central Plateau. The modeling and laboratory efforts reported herein are intended to provide a quantitative assessment of factors that impact water infiltration and contaminant flushing through the vadose zone and into the underlying groundwater. Once in the groundwater, capture of the contaminants would be necessary, but this aspect of implementing soil flushing was not evaluated in this effort. Soil flushing was evaluated primarily with respect to applications for technetium and uranium contaminants in the deep vadose zone of the Hanford Central Plateau.

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

International Nuclear Information System (INIS)

Zhang Jianguo; Meng Jin

2006-01-01

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

Vacuum evaporator-crystallizer process development for Hanford defense waste

International Nuclear Information System (INIS)

Tanaka, K.H.

1978-04-01

One of the major programs in the Department of Energy (DOE) waste management operations at Hanford is the volume reduction and solidification of Hanford Defense Residual Liquor (HDRL) wastes. These wastes are neutralized radioactive wastes that have been concentrated and stored in single-shell underground tanks. Two production vacuum evaporator-crystallizers were built and are operating to reduce the liquid volume and solidify these wastes. The process involves evaporating water under vacuum and thus concentrating and crystallizing the salt waste. The high caustic residual liquor is composed primarily of nitrate, nitrite, aluminate, and carbonate salts. Past evaporator-crystallizer operation was limited to crystallizing nitrate, nitrite, and carbonate salts. These salts formed a drainable salt cake that was acceptable for storage in the original single-shell tanks. The need for additional volume reduction and further concentration necessitated this process development work. Further concentration forms aluminate salts which pose unique processing problems. The aluminate salts are very fine crystals, non-drainable, and suitable only for storage in new double-shell tanks where the fluid waste can be continuously monitored. A pilot scale vacuum evaporator-crystallizer system was built and operated by Rockwell Hanford Operations to support flowsheet development for the production evaporator-crystallizers. The process developed was the concentration of residual liquor to form aluminate salts. The pilot plant tests demonstrated that residual liquors with high aluminum concentrations could be concentrated and handled in a vacuum evaporator-crystallizer system. The dense slurry with high solids content and concentrated liquor was successfully pumped in the insulated heated piping system. The most frequent problem encountered in the pilot plant was the failure of mechanical pump seals due to the abrasive slurry

Organic Tank Safety Project: development of a method to measure the equilibrium water content of Hanford organic tank wastes and demonstration of method on actual waste

Energy Technology Data Exchange (ETDEWEB)

Scheele, R.D.; Bredt, P.R.; Sell, R.L.

1996-09-01

Some of Hanford`s underground waste storage tanks contain Organic- bearing high level wastes that are high priority safety issues because of potentially hazardous chemical reactions of organics with inorganic oxidants in these wastes such as nitrates and nitrites. To ensure continued safe storage of these wastes, Westinghouse Hanford Company has placed affected tanks on the Organic Watch List and manages them under special rules. Because water content has been identified as the most efficient agent for preventing a propagating reaction and is an integral part of the criteria developed to ensure continued safe storage of Hanford`s organic-bearing radioactive tank wastes, as part of the Organic Tank Safety Program the Pacific Northwest National Laboratory developed and demonstrated a simple and easily implemented procedure to determine the equilibrium water content of these potentially reactive wastes exposed to the range of water vapor pressures that might be experienced during the wastes` future storage. This work focused on the equilibrium water content and did not investigate the various factors such as @ ventilation, tank surface area, and waste porosity that control the rate that the waste would come into equilibrium, with either the average Hanford water partial pressure 5.5 torr or other possible water partial pressures.

Study on underground-water restoration of acid in-situ leaching process with electrodialytic desalination

International Nuclear Information System (INIS)

Huang Chongyuan; Meng Jin; Li Weicai

2003-01-01

The study focus undergrounder water restoration of acid in-situ leaching process with electrodialysis desalination in Yining Uranium Mine. It is shown in field test that electrodialysis desalination is an effective method for underground water restoration of acid in-situ leaching process. When TDS of underground-water at the decommissioning scope is 10-12 g/L, and TDS will be less than 1 g/L after the desalination process, the desalination rate is more than 90%, freshwater recovery 60%-70%, power consumption for freshwater recovery 5 kW·h/m 3 , the distance of the desalination flow 12-13 m, current efficiency 80%, and the throughput of the twin membrane 0.22-0.24 m 3 /(m 2 ·d)

Jabiluka gold-uranium project

International Nuclear Information System (INIS)

1988-01-01

The Jabiluka gold-uranium deposit, 230km east of Darwin in the Alligator Rivers Region of the Northern Territory, was discovered by Pancontinental Mining Limited in 1971. Jabiluka, with reserves in excess of 200,000 tonnes of contained U 3 O 8 in two deposits 500 metres apart, is the world's largest high grade uranium deposit and also contains nearly 12 tonnes of gold. It is proposed that only the larger deposit, Jabiluka II will be mined - by underground extraction methods, and that 275,000 tonnes of ore per year will be mined and processed to produce 1,500 tonnes of U 3 O 8 and up to 30,000 oz of gold. The revenue from the uranium sales is estimated to be of the order of A$100 million per year at A$30/lb. By the end of 1982 all necessary mining and environmental approvals had been obtained and significant marketing progress made. With the Australian Labor Party winning Commonwealth Government in the 1983 election, Pancontinental's permission to seek sales contracts was withdrawn and development of the Jabiluka deposit ceased. Jabiluka remains undeveloped - awaiting a change in Australian Government policy on uranium. figs., maps

Estimation of uranium in some edible and commercial plants

International Nuclear Information System (INIS)

Choudhury, S.; Goswami, T.D.

1992-01-01

The trace contents of uranium have been estimated in some edible and commercial plants by PTA (particle track analysis) method. The groups of food plants studied are cereals, pulses, underground vegetables, leafy vegetables, and fruit vegetables. The commercial plants and ingredients taken are betel leaves, tobacco leaves, areca nuts, and lime. Among the different samples studied, the average uranium content, in general, is found to vary from 0.25 to 2.67 ppm. (author). 10 refs., 2 tabs., 1 fig

Radiating toxicological and ecological consequences of extraction of uranium

International Nuclear Information System (INIS)

Svambaev, Z.A.; Svambaev, E.A.; Sultanbekov, G.A; Tusupbekova, S.T.

2010-01-01

In scientific work researchers take up questions of radiation, toxicity and ecological danger at extraction of natural uranium. In work it is resulted results of gauging of radiation in separate parts of a cycle, and also as a whole at underground extractions of uranium. The level of ionization actions of photon radiation in a radiating field with a productive solution which represents the big radiating, toxicological and ecological danger to Wednesday is shown on the average on cycles of feature of work.

Reengineering Hanford

International Nuclear Information System (INIS)

Badalamente, R.V.; Carson, M.L.; Rhoads, R.E.

1995-03-01

The Department of Energy Richland Operations Office is in the process of reengineering its Hanford Site operations. There is a need to fundamentally rethink and redesign environmental restoration and waste management processes to achieve dramatic improvements in the quality, cost-effectiveness, and timeliness of the environmental services and products that make cleanup possible. Hanford is facing the challenge of reengineering in a complex environment in which major processes cuts across multiple government and contractor organizations and a variety of stakeholders and regulators have a great influence on cleanup activities. By doing the upfront work necessary to allow effective reengineering, Hanford is increasing the probability of its success

Reengineering Hanford

Energy Technology Data Exchange (ETDEWEB)

Badalamente, R.V.; Carson, M.L.; Rhoads, R.E.

1995-03-01

The Department of Energy Richland Operations Office is in the process of reengineering its Hanford Site operations. There is a need to fundamentally rethink and redesign environmental restoration and waste management processes to achieve dramatic improvements in the quality, cost-effectiveness, and timeliness of the environmental services and products that make cleanup possible. Hanford is facing the challenge of reengineering in a complex environment in which major processes cuts across multiple government and contractor organizations and a variety of stakeholders and regulators have a great influence on cleanup activities. By doing the upfront work necessary to allow effective reengineering, Hanford is increasing the probability of its success.

US uranium mining industry: background information on economics and emissions

Energy Technology Data Exchange (ETDEWEB)

Bruno, G.A.; Dirks, J.A.; Jackson, P.O.; Young, J.K.

1984-03-01

A review of the US uranium mining industry has revealed a generally depressed industry situation. The 1982 U/sub 3/O/sub 8/ production from both open-pit and underground mines declined to 3800 and 6300 tons respectively with the underground portion representing 46% of total production. US exploration and development has continued downward in 1982. Employment in the mining and milling sectors has dropped 31% and 17% respectively in 1982. Representative forecasts were developed for reactor fuel demand and U/sub 3/O/sub 8/ production for the years 1983 and 1990. Reactor fuel demand is estimated to increase from 15,900 tons to 21,300 tons U/sub 3/O/sub 8/ respectively. U/sub 3/O/sub 8/ production, however, is estimated to decrease from 10,600 tons to 9600 tons respectively. A field examination was conducted of 29 selected underground uranium mines that represent 84% of the 1982 underground production. Data was gathered regarding population, land ownership and private property valuation. An analysis of the increased cost to production resulting from the installation of 20-meter high exhaust borehole vent stacks was conducted. An assessment was made of the current and future /sup 222/Rn emission levels for a group of 27 uranium mines. It is shown that /sup 222/Rn emission rates are increasing from 10 individual operating mines through 1990 by 1.2 to 3.8 times. But for the group of 27 mines as a whole, a reduction of total /sup 222/Rn emissions is predicted due to 17 of the mines being shutdown and sealed. The estimated total /sup 222/Rn emission rate for this group of mines will be 105 Ci/yr by year end 1983 or 70% of the 1978-79 measured rate and 124 Ci/yr by year end 1990 or 83% of the 1978-79 measured rate.

US uranium mining industry: background information on economics and emissions

International Nuclear Information System (INIS)

Bruno, G.A.; Dirks, J.A.; Jackson, P.O.; Young, J.K.

1984-03-01

A review of the US uranium mining industry has revealed a generally depressed industry situation. The 1982 U 3 O 8 production from both open-pit and underground mines declined to 3800 and 6300 tons respectively with the underground portion representing 46% of total production. US exploration and development has continued downward in 1982. Employment in the mining and milling sectors has dropped 31% and 17% respectively in 1982. Representative forecasts were developed for reactor fuel demand and U 3 O 8 production for the years 1983 and 1990. Reactor fuel demand is estimated to increase from 15,900 tons to 21,300 tons U 3 O 8 respectively. U 3 O 8 production, however, is estimated to decrease from 10,600 tons to 9600 tons respectively. A field examination was conducted of 29 selected underground uranium mines that represent 84% of the 1982 underground production. Data was gathered regarding population, land ownership and private property valuation. An analysis of the increased cost to production resulting from the installation of 20-meter high exhaust borehole vent stacks was conducted. An assessment was made of the current and future 222 Rn emission levels for a group of 27 uranium mines. It is shown that 222 Rn emission rates are increasing from 10 individual operating mines through 1990 by 1.2 to 3.8 times. But for the group of 27 mines as a whole, a reduction of total 222 Rn emissions is predicted due to 17 of the mines being shutdown and sealed. The estimated total 222 Rn emission rate for this group of mines will be 105 Ci/yr by year end 1983 or 70% of the 1978-79 measured rate and 124 Ci/yr by year end 1990 or 83% of the 1978-79 measured rate

Resolution of the Hanford site ferrocyanide safety issue

International Nuclear Information System (INIS)

Cash, R.J.; Lilga, M.A.; Babad, H.

1997-01-01

The Ferrocyanide Safety Issue at the Hanford Site was officially resolved in December 1996. This paper summarizes the key activities that led to final resolution of this safety hazard, a process that began in 1990 after it and other safety concerns were identified for the underground high-level waste storage tanks at the Hanford Site. At the time little was known about ferrocyanide-nitrate/nitrite reactions and their potential to cause offsite releases of radioactivity. The ferrocyanide hazard was a perceived problem, but it took six years of intense studies and analyses of tank samples to prove that the problem no longer exists. The issue revolved around the fact that ferrocyanide and nitrate mixtures can be made to explode violently if concentrated, dry, and heated to temperatures of at least 250 degrees C. The studies conducted over the last six years have shown that the combined effects of temperature, radiation, and pH during 40 or more years of storage have destroyed almost all of the ferrocyanide originally added to tanks. This was shown in laboratory experiments using simulant wastes and confirmed by actual samples taken from the ferrocyanide tanks. The tank waste sludges are now too dilute to support a sustained exothermic reaction, even if dried out and heated to high temperatures. 2 tabs., 18 refs

Hanford Site Development Plan

International Nuclear Information System (INIS)

Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

1992-05-01

The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides a land use plan for the Hanford Site and presents a picture of what is currently known and anticipated in accordance with DOE Order 4320.1B. Site Development Planning. The HSDP wig be updated annually as future decisions further shape the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

Non-destructive in situ measurement of radiological distributions in Hanford Site waste tanks

International Nuclear Information System (INIS)

Troyer, G.L.

1996-01-01

Measurement of radiological materials in defense nuclear waste stored in underground tanks at the Hanford Site is being used to indicate material distributions. Both safety assessment and future processing challenges are dependent on knowledge of the distribution kinds, and quantities of various key components. Data from CdTe and neutron detector measurements are shown and correlated with physical sampling and laboratory results. The multiple assay approach is shown to increase the confidence about the material distributions. As a result, costs of physical sampling and destructive analyses can be controlled while not severely limiting the uncertainty of results

Summary of radiological monitoring of Columbia River water along the Hanford Reach, 1980 through 1989

International Nuclear Information System (INIS)

Dirkes, R.L.

1994-02-01

The Surface Environmental Surveillance Project (SESP) is conducted by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) at the Hanford Site in southeastern Washington State. The Columbia River monitoring program, conducted as part of the SESP, provides a historical record of contaminant concentrations in the river attributable to natural causes, worldwide fallout, and operations conducted at the Hanford Site. In addition to ongoing monitoring, special studies are conducted periodically to enhance the understanding of the transport and fate of contaminants in the river. The Columbia River monitoring program includes sampling of river water, river sediment, river-bank springs entering the river, and various types of aquatic biota found in or along the river. These samples are analyzed for radiological constituents and a wide range of chemical parameters. This report describes the water sampling component of the overall Columbia River monitoring program conducted during the years 1980 through 1989 and summarizes the radiological results generated through the program during this time period. The only radionuclides found in the river that were consistently influenced by Hanford were tritium and iodine-129. Strontium-90 and uranium, also attributable to Hanford operations, were present in localized areas within the river near ground-water discharge points; however, these contaminants are quickly dispersed within the river to concentrations similar to background

Packaging and transportation of radioactive liquid at the U.S. Department of Energy Hanford Site

International Nuclear Information System (INIS)

Smith, R.J.

1995-02-01

Beginning in the 1940's, radioactive liquid waste has been generated at the US Department of Energy (DOE) Hanford Site as a result of defense material production. The liquid waste is currently stored in 177 underground storage tanks. As part of the tank remediation efforts, Type B quantity packagings for the transport of large volumes of radioactive liquids are required. There are very few Type B liquid packagings in existence because of the rarity of large-volume radioactive liquid payloads in the commercial nuclear industry. Development of aboveground transport systems for large volumes of radioactive liquids involves institutional, economic, and technical issues. Although liquid shipments have taken place under DOE-approved controlled conditions within the boundaries of the Hanford Site for many years, offsite shipment requires compliance with DOE, US Nuclear Regulatory Commission (NRC), and US Department of Transportation (DOT) directives and regulations. At the present time, no domestic DOE nor NRC-certified Type B packagings with the appropriate level of shielding are available for DOT-compliant transport of radioactive liquids in bulk volumes. This paper will provide technical details regarding current methods used to transport such liquids on and off the Hanford Site, and will provide a status of packaging development programs for future liquid shipments

Hanford wells

International Nuclear Information System (INIS)

McGhan, V.L.; Myers, D.A.; Damschen, D.W.

1976-03-01

The Hanford Reservation contains about 2100 wells constructed from pre-Hanford Works to the present. As of Jan. 1976, about 1800 wells still exist, 850 of which were drilled to the groundwater table; 700 still contain water. This report provides the most complete documentation of these wells and supersedes all previous compilations, including BNWL-1739

Use of Polyphosphate to Decrease Uranium Leaching in Hanford 300 Area Smear Zone Sediments

Energy Technology Data Exchange (ETDEWEB)

Szecsody, James E.; Zhong, Lirong; Oostrom, Martinus; Vermeul, Vincent R.; Fruchter, Jonathan S.; Williams, Mark D.

2012-09-30

The primary objective of this study is to summarize the laboratory investigations performed to evaluate short- and long-term effects of phosphate treatment on uranium leaching from 300 area smear zone sediments. Column studies were used to compare uranium leaching in phosphate-treated to untreated sediments over a year with multiple stop flow events to evaluate longevity of the uranium leaching rate and mass. A secondary objective was to compare polyphosphate injection, polyphosphate/xanthan injection, and polyphosphate infiltration technologies that deliver phosphate to sediment.

Consideration of disposal alternatives for tritium-contaminated wastewater streams at Hanford

International Nuclear Information System (INIS)

Waters, E.D.

1988-03-01

Small quantities of tritium are produced as an undesirable by-product of the operation of light-water reactors. At the US Department of Energy Hanford Site in Washington State, some tritium has been discharged to the environment in low-level liquid and gaseous wastes from the N Reactor plant, but more than 97% of the tritium stays typically within the irradiated fuel as it is delivered for reprocessing. During fuel reprocessing, the tritium is distributed in the process streams, and most of the tritium is presently released to the soil column with excess process condensates from the Plutonium-Uranium Extraction (PUREX) Plant. On an annual basis, approximately 1 g of tritium is discharged in more than 1 x 10 6 L of process condensate water. Principal tritium release points and quantities are presented in section 4.0. The present study is intended to identify and evaluate alternate methods of tritium control and disposal that might merit additional study or development for potential application to Hanford Site effluents. 30 refs., 15 figs., 5 tabs

Uranium mills and mines environmental restoration in Spain

International Nuclear Information System (INIS)

Perez Estevez, C.; Lozano Martinez, F.

2000-01-01

ENRESA and ENUSA have dismantled and restored a uranium mill in Andujar (Andalucia), a uranium facility based on open pit mining and plant in La Haba (Extremadura) and 19 old uranium mines in Andalucia and Extremadura. The Andujar Uranium Mill was operated from 1959 to 1981 and has been restorated between 1991 and 1994. The site included the tailings pile and the processing plant. The Haba Uranium Site included the Plant (operating from 1976 to 1999), four open-pit mines (operating from 1966 to 1990), the heaps leaching and the tailings dam and has been restorated between 1992 and 1997. The 19 abandoned uranium mines were developed by underground mining with the exception of two sites, which were operated by open pit mining. Mining operations started around 1959 and were shutdown in 1981. There was a great diversity among the mines, in terms of site conditions. Whereas in some sites there was little trace of the mining works, in other sites large excavations, mining debris piles, abandoned shafs and galeries and remaining surface structures and equipment were encountered. (author)

Uranium in surficial deposits and waters at Palmottu

International Nuclear Information System (INIS)

Ahonen, L.; Blomqvist, R.; Ervanne, H.; Suksi, J.; Jaakkola, T.

1994-01-01

Occurrence of uranium in surficial formations in the vicinity of an underground U deposit was studied. Several water samples from the Lake Palmottu and nearby springs, three lake sediment cores and three peat cores were collected for the study. Uranium concentrations in the water samples varied from 1.4 to 6.9 mBq/l, reflecting the average concentration of near-surface waters in Finland. In some samples, however, the 234 U/ 238 U activity ratio and water chemistry suggest a partial mixing with deeper groundwaters. In the lake sediments, uranium concentrations increases from 53 Bq/kg in surface layer to five fold in the bottom layers deposited 9000 years ago. In peat cores large variations in uranium concentrations can be observed: from tens of Bq/kg to over 20 kBq/kg of peat ash. The large variation also in the 234 U/ 238 U activity ratio, from 0.79 to l.91, tends to indicate uranium migration to the peat from more than one uranium source. (orig.) (19 refs., 5 figs., 1 tab.)

Estimating retained gas volumes in the Hanford tanks using waste level measurements

International Nuclear Information System (INIS)

Whitney, P.D.; Chen, G.; Gauglitz, P.A.; Meyer, P.A.; Miller, N.E.

1997-09-01

The Hanford site is home to 177 large, underground nuclear waste storage tanks. Safety and environmental concerns surround these tanks and their contents. One such concern is the propensity for the waste in these tanks to generate and trap flammable gases. This report focuses on understanding and improving the quality of retained gas volume estimates derived from tank waste level measurements. While direct measurements of gas volume are available for a small number of the Hanford tanks, the increasingly wide availability of tank waste level measurements provides an opportunity for less expensive (than direct gas volume measurement) assessment of gas hazard for the Hanford tanks. Retained gas in the tank waste is inferred from level measurements -- either long-term increase in the tank waste level, or fluctuations in tank waste level with atmospheric pressure changes. This report concentrates on the latter phenomena. As atmospheric pressure increases, the pressure on the gas in the tank waste increases, resulting in a level decrease (as long as the tank waste is open-quotes softclose quotes enough). Tanks with waste levels exhibiting fluctuations inversely correlated with atmospheric pressure fluctuations were catalogued in an earlier study. Additionally, models incorporating ideal-gas law behavior and waste material properties have been proposed. These models explicitly relate the retained gas volume in the tank with the magnitude of the waste level fluctuations, dL/dP. This report describes how these models compare with the tank waste level measurements

Maximum surface level and temperature histories for Hanford waste tanks

International Nuclear Information System (INIS)

Flanagan, B.D.; Ha, N.D.; Huisingh, J.S.

1994-01-01

Radioactive defense waste resulting from the chemical processing of spent nuclear fuel has been accumulating at the Hanford Site since 1944. This waste is stored in underground waste-storage tanks. The Hanford Site Tank Farm Facilities Interim Safety Basis (ISB) provides a ready reference to the safety envelope for applicable tank farm facilities and installations. During preparation of the ISB, tank structural integrity concerns were identified as a key element in defining the safety envelope. These concerns, along with several deficiencies in the technical bases associated with the structural integrity issues and the corresponding operational limits/controls specified for conduct of normal tank farm operations are documented in the ISB. Consequently, a plan was initiated to upgrade the safety envelope technical bases by conducting Accelerated Safety Analyses-Phase 1 (ASA-Phase 1) sensitivity studies and additional structural evaluations. The purpose of this report is to facilitate the ASA-Phase 1 studies and future analyses of the single-shell tanks (SSTs) and double-shell tanks (DSTs) by compiling a quantitative summary of some of the past operating conditions the tanks have experienced during their existence. This report documents the available summaries of recorded maximum surface levels and maximum waste temperatures and references other sources for more specific data

Assessment of (222)Rn emanation from ore body and backfill tailings in low-grade underground uranium mine.

Science.gov (United States)

Mishra, Devi Prasad; Sahu, Patitapaban; Panigrahi, Durga Charan; Jha, Vivekanand; Patnaik, R Lokeswara

2014-02-01

This paper presents a comparative study of (222)Rn emanation from the ore and backfill tailings in an underground uranium mine located at Jaduguda, India. The effects of surface area, porosity, (226)Ra and moisture contents on (222)Rn emanation rate were examined. The study revealed that the bulk porosity of backfill tailings is more than two orders of magnitude than that of the ore. The geometric mean radon emanation rates from the ore body and backfill tailings were found to be 10.01 × 10(-3) and 1.03 Bq m(-2) s(-1), respectively. Significant positive linear correlations between (222)Rn emanation rate and the (226)Ra content of ore and tailings were observed. For normalised (226)Ra content, the (222)Rn emanation rate from tailings was found to be 283 times higher than the ore due to higher bulk porosity and surface area. The relative radon emanation from the tailings with moisture fraction of 0.14 was found to be 2.4 times higher than the oven-dried tailings. The study suggested that the mill tailings used as a backfill material significantly contributes to radon emanation as compared to the ore body itself and the (226)Ra content and bulk porosity are the dominant factors for radon emanation into the mine atmosphere.

Historical tank content estimate for the northwest quadrant of the Hanford 200 west area

International Nuclear Information System (INIS)

Brevick, C.H.; Stroup, J.L.; Funk, J.W.

1997-01-01

The Historical Tank Content Estimate for the Quadrant provides historical information on a tank-by-tank basis of the radioactive mixed wastes stored in the underground single-shell tanks for the Hanford 200 West Area. This report summarized historical information such as waste history, level history, temperature history, riser configuration, tank integrity, and inventory estimates on a tank-by-tank basis. Tank farm aerial photographs and interior tank montages are also provided for each tank. A description of the development of data for the document of the inventory estimates provided by Los Alamos National Laboratory are also given in this report

Historical genesis of Hanford Site wastes

International Nuclear Information System (INIS)

Gerber, M.S.

1991-01-01

This paper acquaints the audience with historical waste practices and policies as they changed over the years at the Hanford Site, and with the generation of the major waste streams of concern in Hanford Site clean-up today. The paper also describes the founding and basic operating history of the Hanford Site, including World War 11 construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), and some past suggestions and efforts to chemically treat, open-quotes fractionate,close quotes and/or immobilize Hanford's wastes. Recent events, including the designation of the Hanford Site as the open-quotes flagshipclose quotes of Department of Energy (DOE) waste remediation efforts and the signing of the landmark Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), have generated new interest in Hanford's history. Clean-up milestones dictated in this agreement demand information about how, when, in what quantities and mixtures, and under what conditions, Hanford Site wastes were generated and released. This paper presents original, primary-source research into the waste history of the Hanford Site. The earliest, 1940s knowledge base, assumptions and calculations about radioactive and chemical discharges, as discussed in the memos, correspondence and reports of the original Hanford Site (then Hanford Engineer Works) builders and operators, are reviewed. The growth of knowledge, research efforts, and subsequent changes in Site waste disposal policies and practices are traced. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history

Hanford site environment

International Nuclear Information System (INIS)

Isaacson, R.E.

1976-01-01

A synopsis is given of the detailed characterization of the existing environment at Hanford. The following aspects are covered: demography, land use, meteorology, geology, hydrology, and seismology. It is concluded that Hanford is one of the most extensively characterized nuclear sites

Managing risk at Hanford

International Nuclear Information System (INIS)

Hesser, W.A.; Stillwell, W.G.; Rutherford, W.A.

1994-01-01

Clearly, there is sufficient motivation from Washington for the Hanford community to pay particular attention to the risks associated with the substantial volumes of radiological, hazardous, and mixed waste at Hanford. But there is also another reason for emphasizing risk: Hanford leaders have come to realize that their decisions must consider risk and risk reduction if those decisions are to be technically sound, financially affordable, and publicly acceptable. The 560-square miles of desert land is worth only a few thousand dollars an acre (if that) -- hardly enough to justify the almost two billion dollars that will be spent at Hanford this year. The benefit of cleaning up the Hanford Site is not the land but the reduction of potential risk to the public and the environment for future generations. If risk reduction is our ultimate goal, decisions about priority of effort and resource allocation must consider those risks, now and in the future. The purpose of this paper is to describe how Hanford is addressing the issues of risk assessment, risk management, and risk-based decision making and to share some of our experiences in these areas

Process chemistry for the pretreatment of Hanford tank wastes

International Nuclear Information System (INIS)

Lumetta, G.J.; Swanson, J.L.; Barker, S.A.

1992-08-01

Current guidelines for disposing radioactive wastes stored in underground tanks at the US Department of Energy's Hanford Site call for the vitrification of high-level waste in borosilicate glass and disposal of the glass canisters in a deep geologic repository. Low-level waste is to be cast in grout and disposed of on site in shallow burial vaults. Because of the high cost of vitrification and geologic disposal, methods are currently being developed to minimize the volume of high-level waste requiring disposal. Two approaches are being considered for pretreating radioactive tank sludges: (1) leaching of selected components from the sludge and (2) acid dissolution of the sludge followed by separation of key radionuclides. The leaching approach offers the advantage of simplicity, but the acid dissolution/radionuclide extraction approach has the potential to produce the least number of glass canisters. Four critical components (Cr, P, S, and Al) were leached from an actual Hanford tank waste-Plutonium Finishing Plant sludge. The Al, P, and S were removed from the sludge by digestion of the sludge with 0.1 M NaOH at 100 degrees C. The Cr was leached by treating the sludge with alkaline KMnO 4 at 100 degrees C. Removing these four components from the sludge will dramatically lower the number of glass canisters required to dispose of this waste. The transuranic extraction (TRUEX) solvent extraction process has been demonstrated at a bench scale using an actual Hanford tank waste. The process, which involves extraction of the transuranic elements with octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO), separated 99.9% of the transuranic elements from the bulk components of the waste. Several problems associated with the TRUEX processing of this waste have been addressed and solved

U.S. Bureau of Mines, phase I Hanford low-level waste melter tests: Melter offgas report

International Nuclear Information System (INIS)

Eaton, W.C.

1995-01-01

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the melter offgas report on testing performed by the U.S. Department of the Interior, Bureau of Mines, Albany Research Center in Albany, Oregon. The Bureau of Mines (one of the seven vendors selected) was chosen to demonstrate carbon electrode melter technology (also called carbon arc or electric arc) under WHC subcontract number MMI-SVV-384216. The document contains the complete offgas report for the first 24-hour melter test (WHC-1) as prepared by Entropy Inc. A summary of this report is also contained in the''U.S. Bureau of Mines, Phase 1 Hanford Low-Level Waste Melter Tests: Final Report'' (WHC-SD-WM-VI-030)

Solid secondary waste testing for maintenance of the Hanford Integrated Disposal Facility Performance Assessment - FY 2017

Energy Technology Data Exchange (ETDEWEB)

Nichols, Ralph L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Seitz, Roger R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, Kenneth L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-08-01

The Waste Treatment and Immobilization Plant (WTP) at Hanford is being constructed to treat 56 million gallons of radioactive waste currently stored in underground tanks at the Hanford site. Operation of the WTP will generate several solid secondary waste (SSW) streams including used process equipment, contaminated tools and instruments, decontamination wastes, high-efficiency particulate air filters (HEPA), carbon adsorption beds, silver mordenite iodine sorbent beds, and spent ion exchange resins (IXr) all of which are to be disposed in the Integrated Disposal Facility (IDF). An applied research and development program was developed using a phased approach to incrementally develop the information necessary to support the IDF PA with each phase of the testing building on results from the previous set of tests and considering new information from the IDF PA calculations. This report contains the results from the exploratory phase, Phase 1 and preliminary results from Phase 2. Phase 3 is expected to begin in the fourth quarter of FY17.

MICROSCALE METABOLIC, REDOX AND ABIOTIC REACTIONS IN HANFORD 300 AREA SUBSURFACE SEDIMENTS

Energy Technology Data Exchange (ETDEWEB)

Beyenal, Haluk [WSU; McLEan, Jeff [JCVI; Majors, Paul [PNNL; Fredrickson, Jim [PNNL

2013-11-14

The Hanford 300 Area is a unique site due to periodic hydrologic influence of river water resulting in changes in groundwater elevation and flow direction. This area is also highly subject to uranium remobilization, the source of which is currently believed to be the region at the base of the vadose zone that is subject to period saturation due to the changes in the water levels in the Columbia River. We found that microbial processes and redox and abiotic reactions which operate at the microscale were critical to understanding factors controlling the macroscopic fate and transport of contaminants in the subsurface. The combined laboratory and field research showed how microscale conditions control uranium mobility and how biotic, abiotic and redox reactions relate to each other. Our findings extended the current knowledge to examine U(VI) reduction and immobilization using natural 300 Area communities as well as selected model organisms on redox-sensitive and redox-insensitive minerals. Using innovative techniques developed specifically to probe biogeochemical processes at the microscale, our research expanded our current understanding of the roles played by mineral surfaces, bacterial competition, and local biotic, abiotic and redox reaction rates on the reduction and immobilization of uranium.

Uranium Oxide Rate Summary for the Spent Nuclear Fuel (SNF) Project (OCRWM)

Energy Technology Data Exchange (ETDEWEB)

PAJUNEN, A.L.

2000-09-20

The purpose of this document is to summarize the uranium oxidation reaction rate information developed by the Hanford Spent Nuclear Fuel (SNF) Project and describe the basis for selecting reaction rate correlations used in system design. The selection basis considers the conditions of practical interest to the fuel removal processes and the reaction rate application during design studies. Since the reaction rate correlations are potentially used over a range of conditions, depending of the type of evaluation being performed, a method for transitioning between oxidation reactions is also documented. The document scope is limited to uranium oxidation reactions of primary interest to the SNF Project processes. The reactions influencing fuel removal processes, and supporting accident analyses, are: uranium-water vapor, uranium-liquid water, uranium-moist air, and uranium-dry air. The correlation selection basis will consider input from all available sources that indicate the oxidation rate of uranium fuel, including the literature data, confirmatory experimental studies, and fuel element observations. Trimble (2000) summarizes literature data and the results of laboratory scale experimental studies. This document combines the information in Trimble (2000) with larger scale reaction observations to describe uranium oxidation rate correlations applicable to conditions of interest to the SNF Project.

Uranium Oxide Rate Summary for the Spent Nuclear Fuel (SNF) Project (OCRWM)

International Nuclear Information System (INIS)

PAJUNEN, A.L.

2000-01-01

The purpose of this document is to summarize the uranium oxidation reaction rate information developed by the Hanford Spent Nuclear Fuel (SNF) Project and describe the basis for selecting reaction rate correlations used in system design. The selection basis considers the conditions of practical interest to the fuel removal processes and the reaction rate application during design studies. Since the reaction rate correlations are potentially used over a range of conditions, depending of the type of evaluation being performed, a method for transitioning between oxidation reactions is also documented. The document scope is limited to uranium oxidation reactions of primary interest to the SNF Project processes. The reactions influencing fuel removal processes, and supporting accident analyses, are: uranium-water vapor, uranium-liquid water, uranium-moist air, and uranium-dry air. The correlation selection basis will consider input from all available sources that indicate the oxidation rate of uranium fuel, including the literature data, confirmatory experimental studies, and fuel element observations. Trimble (2000) summarizes literature data and the results of laboratory scale experimental studies. This document combines the information in Trimble (2000) with larger scale reaction observations to describe uranium oxidation rate correlations applicable to conditions of interest to the SNF Project

Uranium uptake and accumulation in plants from soil contaminated with uranium in different concentrations

International Nuclear Information System (INIS)

Zhao Luxue; Tang Yongjin; Luo Xuegang

2014-01-01

The plants of Medicago sativa L., Hibiscus esulentus L, Waterspinach, Amaranthus retroflexus and Abutilon theophrasti Medic were employed as the indicator to investigate the uranium uptake and accumulation from soils contaminated with uranium (UO_2 (CH_3COO)_2 · 2H_2O) of 25 mg · kg"-"l, 75 mg · kg"-"1, 125 mg · kg"-"l, 175 mg · kg"-"l respectively, in a pot experiment. The result shows that, U concentration in the aerial part and underground part of the whole plant increased with the rise of uranium concentration in the soils. In the contaminated soils with 25∼125 mg · kg"-"l concentrations of uranium, U content of Medicago sativa L is the highset (6.78 mg · kg"-"l, 61.53 mg · kg"-"l, 74.06 mg · kg"-"l separately). While in the 175 mg · kg"-"l concentration of uranium contaminated soils, U content of Hibiscus esulentus L is the highest (86.72 mg · kg"-"1), which is mainly because of U concentration in its roots have higher level of uranium (388.16 mg · kg"-"l). Comprehensive analysis shows that Medicago sativa L. is a good plant for phytoextraction and Hibiscus esulentus L is a good immobilizing plant for phytoremediation. The results can provide some theoretical basis and technical support for remedying U-contaminated soils in different areas of our country. (authors)

TECHNICAL ASSESSMENT OF FRACTIONAL CRYSTALLIZATION FOR TANK WASTE PRETREATMENT AT THE DOE HANFORD SITE

International Nuclear Information System (INIS)

HAMILTON, D.W.

2006-01-01

Radioactive wastes from one hundred seventy-seven underground storage tanks in the 200 Area of the Department of Energy (DOE) Hanford Site in Washington State will be retrieved, treated and stored either on site or at an approved off-site repository. DOE is currently planning to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions, which would be treated and permanently disposed in separate facilities. A significant volume of the wastes in the Hanford tanks is currently classified as medium Curie waste, which will require separation and treatment at the Waste Treatment Plant (WTP). Because of the specific challenges associated with treating this waste stream, DOE EM-21 funded a project to investigate the feasibility of using fractional crystallization as a supplemental pretreatment technology. The two process requirements for fractional crystallization to be successfully applied to Hanford waste include: (1) evaporation of water from the aqueous solution to enrich the activity of soluble 137 Cs, resulting in a higher activity stream to be sent to the WTP, and (2) separation of the crystalline salts that are enriched in sodium, carbonate, sulfate, and phosphate and sufficiently depleted in 137 Cs, to produce a second stream to be sent to Bulk Vitrification. Phase I of this project has just been completed by COGEMA/Georgia Institute of Technology. The purpose of this report is to document an independent expert review of the Phase I results with recommendations for future testing. A team of experts with significant experience at both the Hanford and Savannah River Sites was convened to conduct the review at Richland, Washington the week of November 14, 2005

TECHNICAL ASSESSMENT OF FRACTIONAL CRYSTALLIZATION FOR TANK WASTE PRETREATMENT AT THE DOE HANFORD SITE

Energy Technology Data Exchange (ETDEWEB)

HAMILTON, D.W.

2006-01-03

Radioactive wastes from one hundred seventy-seven underground storage tanks in the 200 Area of the Department of Energy (DOE) Hanford Site in Washington State will be retrieved, treated and stored either on site or at an approved off-site repository. DOE is currently planning to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions, which would be treated and permanently disposed in separate facilities. A significant volume of the wastes in the Hanford tanks is currently classified as medium Curie waste, which will require separation and treatment at the Waste Treatment Plant (WTP). Because of the specific challenges associated with treating this waste stream, DOE EM-21 funded a project to investigate the feasibility of using fractional crystallization as a supplemental pretreatment technology. The two process requirements for fractional crystallization to be successfully applied to Hanford waste include: (1) evaporation of water from the aqueous solution to enrich the activity of soluble {sup 137}Cs, resulting in a higher activity stream to be sent to the WTP, and (2) separation of the crystalline salts that are enriched in sodium, carbonate, sulfate, and phosphate and sufficiently depleted in {sup 137}Cs, to produce a second stream to be sent to Bulk Vitrification. Phase I of this project has just been completed by COGEMA/Georgia Institute of Technology. The purpose of this report is to document an independent expert review of the Phase I results with recommendations for future testing. A team of experts with significant experience at both the Hanford and Savannah River Sites was convened to conduct the review at Richland, Washington the week of November 14, 2005.

Contemporary Pollution Due Old Uranium Tails

International Nuclear Information System (INIS)

Hadjamberdiev, I.

2007-01-01

The areas of our study are uranium mining areas (with tails and dumps) Min-Kush, Kadji-Sai, Mailuu-Suu. These areas situated in different parts of Tien-Shan region. We study the content (and correlations among): level of uranium in environment, immune function and level, level in human teeth. It has been found: content of uranium in river water under tails about 2,0x10-5 gm/litter, and high level in drinking water too 2,0-4,0. Drying grass and flowers uranium content was 0,04-0,51x10-5 gm/gm, most high content were in Tacniatherum crinitum and Atgilops triuncialis. Lams tissues contain 0,005-2,44 mg/g in Min-Kush, 0,03-0,107, in Mailuu-Suu, and 0,001-0,048 mg/g in Kadji-Sai. Human teeth uranium content (Mailuu-Suu): in milk-teeth 0,481x10-6 gm/gm, in former miners 0,7684x10-6 gm/gm. Inhabitants of the area, which not working in uranium industry have 0,6876x10-6 gm/gm. There was low level of immune function (lymphocytes, IgI globulin, etc) in all three regions (in child, in adults, in uranium-mining worked people). There is no doubt of the positive correlations of uranium pollution of water (by underground infiltration from tails) on one hand and, on the other hand - a) grass, b) lambs body, c) human teeth, d) human immune function. Levels of uranium in teeth strictly depend on time of mining contact. (author)

Uranium and radium activities in samples of aquifers of the main cities of the Estado de Chihuahua

International Nuclear Information System (INIS)

Villalba, L.; Colmenero S, L.; Montero C, M.E.

2003-01-01

The natural uranium is in four valence states +3, +4, +5 and +6 being the hexavalent state the more soluble, which plays an important role in the transport of the uranium in the environment. The high concentrations of uranium in water not only in near waters to uranium mines, but also are in some mineral waters or in waters that are extracted of deep wells as it happens in the State of Chihuahua, where the underground waters are the fundamental source of consumption. The radium is a disintegration product of the uranium, the radio content in water is considered the second source of natural radioactivity. The distribution of radium in water is in function of the uranium content present in the aquifer. It was determined the uranium and radium content in samples of underground water of the main cities of the State of Chihuahua according to their number of inhabitants. The extraction methods for uranium and sulfates precipitation of Ba-Ra by means of the addition of barium carriers for the radium were used. The measures of the activities of uranium and radium were carried out by means of a portable liquid scintillation detector trade mark Thiathler-OY HIDEX. The obtained results have demonstrated that the content of uranium and radium in dissolution are in most of the sampling wells above the permissible maximum levels that manage the Mexican regulations. The high contents of uranium and radio can be attributed since to the influence of the geologic substrate characteristic of the zone in the State of Chihuahua they exist but of 50 uranium deposits. (Author)

FINAL PROJECT REPORT: A Geophysical Characterization & Monitoring Strategy for Determining Hydrologic Processes in the Hyporheic Corridor at the Hanford 300-Area

Energy Technology Data Exchange (ETDEWEB)

Lee Slater

2011-08-15

The primary objective of this research was to advance the prediction of solute transport between the Uranium contaminated Hanford aquifer and the Columbia River at the Hanford 300 Area by improving understanding of how fluctuations in river stage, combined with subsurface heterogeneity, impart spatiotemporal complexity to solute exchange along the Columbia River corridor. Our work explored the use of continuous waterborne electrical imaging (CWEI), in conjunction with fiber-optic distributed temperature sensor (FO-DTS) and time-lapse resistivity monitoring, to improve the conceptual model for how groundwater/surface water exchange regulates uranium transport. We also investigated how resistivity and induced polarization can be used to generate spatially rich estimates of the variation in depth to the Hanford-Ringold (H-R) contact between the river and the 300 Area Integrated Field Research Challenge (IFRC) site. Inversion of the CWEI datasets (a data rich survey containing ~60,000 measurements) provided predictions of the distributions of electrical resistivity and polarizability, from which the spatial complexity of the primary hydrogeologic units along the river corridor was reconstructed. Variation in the depth to the interface between the overlying coarse-grained, high permeability Hanford Formation and the underlying finer-grained, less permeable Ringold Formation, an important contact that limits vertical migration of contaminants, has been resolved along ~3 km of the river corridor centered on the IFRC site in the Hanford 300 Area. Spatial variability in the thickness of the Hanford Formation captured in the CWEI datasets indicates that previous studies based on borehole projections and drive-point and multi-level sampling likely overestimate the contributing area for uranium exchange within the Columbia River at the Hanford 300 Area. Resistivity and induced polarization imaging between the river and the 300 Area IFRC further imaged spatial variability in

Polymers for subterranean containment barriers for underground storage tanks (USTs)

International Nuclear Information System (INIS)

Heiser, J.H.; Colombo, P.; Clinton, J.

1992-12-01

The US Department of Energy (DOE) set up the Underground Storage Tank Integrated Demonstration Program (USTID) to demonstrate technologies for the retrieval and treatment of tank waste, and closure of underground storage tanks (USTs). There are more than 250 underground storage tanks throughout the DOE complex. These tanks contain a wide variety of wastes including high level, low level, transuranic, mixed and hazardous wastes. Many of the tanks have performed beyond the designed lifetime resulting in leakage and contamination of the local geologic media and groundwater. To mitigate this problem it has been proposed that an interim subterranean containment barrier be placed around the tanks. This would minimize or prevent future contamination of soil and groundwater in the event that further tank leakages occur before or during remediation. Use of interim subterranean barriers can also provide sufficient time to evaluate and select appropriate remediation alternatives. The DOE Hanford site was chosen as the demonstration site for containment barrier technologies. A panel of experts for the USTID was convened in February, 1992, to identify technologies for placement of subterranean barriers. The selection was based on the ability of candidate grouts to withstand high radiation doses, high temperatures and aggressive tank waste leachates. The group identified and ranked nine grouting technologies that have potential to place vertical barriers and five for horizontal barriers around the tank. The panel also endorsed placement technologies that require minimal excavation of soil surrounding the tanks

Hanford Site Infrastructure Plan

International Nuclear Information System (INIS)

1990-01-01

The Hanford Site Infrastructure Plan (HIP) has been prepared as an overview of the facilities, utilities, systems, and services that support all activities on the Hanford Site. Its purpose is three-fold: to examine in detail the existing condition of the Hanford Site's aging utility systems, transportation systems, Site services and general-purpose facilities; to evaluate the ability of these systems to meet present and forecasted Site missions; to identify maintenance and upgrade projects necessary to ensure continued safe and cost-effective support to Hanford Site programs well into the twenty-first century. The HIP is intended to be a dynamic document that will be updated accordingly as Site activities, conditions, and requirements change. 35 figs., 25 tabs

Review of Hanford international activities

International Nuclear Information System (INIS)

Panther, D.G.

1993-01-01

Hanford initiated a review of international activities to collect, review, and summarize information on international environmental restoration and waste management initiatives considered for use at Hanford. This effort focused on Hanford activities and accomplishments, especially international technical exchanges and/or the implementation of foreign-developed technologies

Final Hanford Comprehensive Land-Use Plan Environmental Impact Statement, Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

N/A

1999-10-01

This Final ''Hanford Comprehensive Land-Use Plan Environmental Impact Statement'' (HCP EIS) is being used by the Department of Energy (DOE) and its nine cooperating and consulting agencies to develop a comprehensive land-use plan (CLUP) for the Hanford Site. The DOE will use the Final HCP EIS as a basis for a Record of Decision (ROD) on a CLUP for the Hanford Site. While development of the CLUP will be complete with release of the HCP EIS ROD, full implementation of the CLUP is expected to take at least 50 years. Implementation of the CLUP would begin a more detailed planning process for land-use and facility-use decisions at the Hanford Site. The DOE would use the CLUP to screen proposals. Eventually, management of Hanford Site areas would move toward the CLUP land-use goals. This CLUP process could take more than 50 years to fully achieve the land-use goals.

Strategy and perspective for uranium exploration in Egypt

International Nuclear Information System (INIS)

Hassan, M.A.; Salman, A.B.; Assaf, H.S.; Mahdy, M.M.

1995-01-01

Uranium exploration started in Egypt about three decades ago. This was performed by applying integrated airborne and ground radiometric prospecting. The latter was conducted upon selected areas having rather favorable geological criteria. These activities resulted in the discovery of great numbers of radiometric anomalies, with several uranium occurrences in various geologic environments in granitic and sedimentary rocks. Some of these uranium occurrences show good potential for developing into workable uranium deposits. Small-scale exploratory tunnelling and drilling works have been carried out at some of these occurrences. Leaching studies and pilot experiments were carried out on technological samples to evaluate ore's suitability for uranium extraction. However, no assured reserves of uranium have been reached yet. The demands for uranium to satisfy the near future Egyptian nuclear power generation necessitates some development in the national strategy for uranium exploration. This will be achieved through intense programmes for ground geophysics and drilling from surface and underground mining works, in addition to radon emanometry and logging of oil and gas wells. Moreover, non conventional procedures for uranium extraction such as heap-leaching may be followed to exploit small-scale uranium deposits. In this developed strategy, the present uranium occurrences are modellized and categorized following the IAEA classification. The characteristics of the present uranium occurrences will be utilized in prospecting new areas. Subsidiary resources in phosphorites, black sands and rare metal deposits could supply additional quantities of uranium, in addition to thorium and rare earth elements. (author). 34 refs, 4 figs, 1 tab

Tank 241-C-106 past-practice sluicing waste retrieval, Hanford Site, Richland, Washington. Environmental Assessment

International Nuclear Information System (INIS)

1995-02-01

The US Department of Energy (DOE) needs to take action to eliminate safety concerns with storage of the high-heat waste in Tank 241-C-106 (Tank C-106), and demonstrate a tank waste retrieval technology. This Environmental Assessment (EA) was prepared to analyze the potential impacts associated with the proposed action, past-practice sluicing of Tank C-106, an underground single-shell tank (SST). Past-practice sluicing is defined as the mode of waste retrieval used extensively in the past at the Hanford Site on the large underground waste tanks, and involves introducing a high-volume, low-pressure stream of liquid to mobilize sludge waste prior to pumping. It is proposed to retrieve the waste from Tank C-106 because this waste is classified not only as transuranic and high-level, but also as high-heat, which is caused by the radioactive decay of strontium. This waste characteristic has led DOE to place Tank C-106 on the safety ''Watchlist.''

Spectral Induced Polarization Response of Biofilm Formation in Hanford Vadose Zone Sediment

Science.gov (United States)

Garcia, A.; Katsenovich, Y.; Lee, B.; Whitman, D.

2017-12-01

As a result of the U.S. Nuclear weapons program during the second world war and the cold war, there now exists a significant amount of uranium contamination at the U.S. Department of Energy Hanford site located in Washington state. In-situ immobilization of mobile uranium via injections of a soluble sodium tripolyphosphate amendment may prove effective in the formation of insoluble uranyl phosphate mineral, autunite. However, the injected polyphosphate undergoes hydrolysis in aqueous solutions to form orthophosphate, which serves as a readily available nutrient for the various microorganisms in the sediment. Sediment-filled column experiments conducted under saturated oxygen restricted conditions using geophysical Spectral Induced Polarization technique have shown the impact of microbes on the dissolution of autunite, a calcium uranyl phosphate mineral. Spectral Induced Polarization may be an effective way to track changes indicative of bacterial activities on the surrounding environment. This method can be a cost-effective alternative to the drilling of boreholes at a field scale.

Toward petascale computing in geosciences: application to the Hanford 300 area

International Nuclear Information System (INIS)

Hammond, G E; Lichtner, P C; Mills, R T; Lu, C

2008-01-01

Modeling uranium transport at the Hanford 300 Area presents new challenges for high performance computing. A field-scale three-dimensional domain with an hourly fluctuating Columbia river stage coupled to flow in highly permeable sediments results in fast groundwater flow rates requiring small time steps. In this work, high-performance computing has been applied to simulate variably saturated groundwater flow and tracer transport at the 300 Area using PFLOTRAN. Simulation results are presented for discretizations up to 10.8 million degrees of freedom, while PFLOTRAN performance was assessed on up to one billion degrees of freedom and 12,000 processor cores on Jaguar, the Cray XT4 supercomputer at ORNL

Assessment of the rock burst potential in basalt at the Hanford Site

International Nuclear Information System (INIS)

Blake, W.

1984-01-01

The phenomenon of rock bursting has been reviewed and specific case histories have been presented, along with the measures most commonly taken to minimize their occurrence and effects. A combination of high stresses and brittle rock types is necessary to initiate bursting but is not sufficient to do so unless other parameters are present (i.e. an extensive mined-out area, a high extraction ratio, and geologic structures, or discontinuities). Since none of these parameters will result from the construction of a deep underground nuclear waste repository in basalt at the Hanford Site in Southeastern Washington, rock bursting should not occur either during or after this construction. 75 refs., 35 figs., 2 tabs

Soil weight (lbf/ft3) at Hanford waste storage locations (2 volumes)

International Nuclear Information System (INIS)

Pianka, E.W.

1994-12-01

Hanford Reservation waste storage tanks are fabricated in accordance with approved construction specifications. After an underground tank has been constructed in the excavation prepared for it, soil is place around the tank and compacted by an approved compaction procedure. To ensure compliance with the construction specifications, measurements of the soil compaction are taken by QA inspectors using test methods based on American Society for the Testing and Materials (ASTM) standards. Soil compaction tests data taken for the 241AP, 241AN, and 241AW tank farms constructed between 1978 and 1986 are included. The individual data values have been numerically processed to obtain average soil density values for each of these tank farms

Work plan for defining a standard inventory estimate for wastes stored in Hanford Site underground tanks

International Nuclear Information System (INIS)

Hodgson, K.M.

1996-01-01

This work plan addresses the Standard Inventory task scope, deliverables, budget, and schedule for fiscal year 1997. The goal of the Standard Inventory task is to resolve differences among the many reported Hanford Site tank waste inventory values and to provide inventory estimates that will serve as Standard Inventory values for all waste management and disposal activities. These best-basis estimates of chemicals and radionuclides will be reported on both a global and tank-specific basis and will be published in the Tank Characterization Database

Hanford Emergency Response Plan

International Nuclear Information System (INIS)

Wagoner, J.D.

1994-04-01

The Hanford Emergency Response Plan for the US Department of Energy (DOE), Richland Operations Office (RL), incorporates into one document an overview of the emergency management program for the Hanford Site. The program has been developed in accordance with DOE orders, and state and federal regulations to protect worker and public health and safety and the environment in the event of an emergency at or affecting the Hanford Site. This plan provides a description of how the Hanford Site will implement the provisions of DOE 5500 series and other applicable Orders in terms of overall policies and concept of operations. It should be used as the basis, along with DOE Orders, for the development of specific contractor and RL implementing procedures

Hanford Emergency Response Plan

Energy Technology Data Exchange (ETDEWEB)

Wagoner, J.D.

1994-04-01

The Hanford Emergency Response Plan for the US Department of Energy (DOE), Richland Operations Office (RL), incorporates into one document an overview of the emergency management program for the Hanford Site. The program has been developed in accordance with DOE orders, and state and federal regulations to protect worker and public health and safety and the environment in the event of an emergency at or affecting the Hanford Site. This plan provides a description of how the Hanford Site will implement the provisions of DOE 5500 series and other applicable Orders in terms of overall policies and concept of operations. It should be used as the basis, along with DOE Orders, for the development of specific contractor and RL implementing procedures.

Glass optimization for vitrification of Hanford Site low-level tank waste

International Nuclear Information System (INIS)

Feng, X.; Hrma, P.R.; Westsik, J.H. Jr.

1996-03-01

The radioactive defense wastes stored in 177 underground single-shell tanks (SST) and double-shell tanks (DST) at the Hanford Site will be separated into low-level and high-level fractions. One technology activity underway at PNNL is the development of glass formulations for the immobilization of the low-level tank wastes. A glass formulation strategy has been developed that describes development approaches to optimize glass compositions prior to the projected LLW vitrification facility start-up in 2005. Implementation of this strategy requires testing of glass formulations spanning a number of waste loadings, compositions, and additives over the range of expected waste compositions. The resulting glasses will then be characterized and compared to processing and performance specifications yet to be developed. This report documents the glass formulation work conducted at PNL in fiscal years 1994 and 1995 including glass formulation optimization, minor component impacts evaluation, Phase 1 and Phase 2 melter vendor glass development, liquidus temperature and crystallization kinetics determination. This report also summarizes relevant work at PNNL on high-iron glasses for Hanford tank wastes conducted through the Mixed Waste Integrated Program and work at Savannah River Technology Center to optimize glass formulations using a Plackett-Burnam experimental design

Hanford Integrated Planning Process: 1993 Hanford Site-specific science and technology plan

International Nuclear Information System (INIS)

1993-12-01

This document is the FY 1993 report on Hanford Site-specific science and technology (S ampersand T) needs for cleanup of the Site as developed via the Hanford Integrated Planning Process (HIPP). It identifies cleanup problems that lack demonstrated technology solutions and technologies that require additional development. Recommendations are provided regarding allocation of funding to address Hanford's highest-priority technology improvement needs, technology development needs, and scientific research needs, all compiled from a Sitewide perspective. In the past, the S ampersand T agenda for Hanford Site cleanup was sometimes driven by scientists and technologists, with minimal input from the ''problem owners'' (i.e., Westinghouse Hanford Company [WHC] staff who are responsible for cleanup activities). At other times, the problem-owners made decisions to proceed with cleanup without adequate scientific and technological inputs. Under both of these scenarios, there was no significant stakeholder involvement in the decision-making process. One of the key objectives of HIPP is to develop an understanding of the integrated S ampersand T requirements to support the cleanup mission, (a) as defined by the needs of the problem owners, the values of the stakeholders, and the technology development expertise that exists at Hanford and elsewhere. This requires a periodic, systematic assessment of these needs and values to appropriately define a comprehensive technology development program and a complementary scientific research program. Basic to our success is a methodology that is defensible from a technical perspective and acceptable to the stakeholders

Risk assessment methodology for Hanford high-level waste tanks

International Nuclear Information System (INIS)

Bott, T.F.; Mac Farlane, D.R.; Stack, D.W.; Kindinger, J.

1992-01-01

A methodology is presented for applying Probabilistic Safety Assessment techniques to quantification of the health risks posed by the high-level waste (HLW) underground tanks at the Department of Energy's Hanford reservation. This methodology includes hazard screening development of a list of potential accident initiators, systems fault trees development and quantification, definition of source terms for various release categories, and estimation of health consequences from the releases. Both airborne and liquid pathway releases to the environment, arising from aerosol and spill/leak releases from the tanks, are included in the release categories. The proposed methodology is intended to be applied to a representative subset of the total of 177 tanks, thereby providing a baseline risk profile for the HLW tank farm that can be used for setting clean-up/remediation priorities. Some preliminary results are presented for Tank 101-SY

Application of supported liquid membranes for removal of uranium from groundwater

International Nuclear Information System (INIS)

Chiarizia, R.; Horwitz, E.P.; Rickert, P.G.; Hodgson, K.M.

1989-01-01

The separation of uranium from Hanford site groundwater as studied by hollow-fiber supported liquid membranes, SLM. The carrier bis(2,4,4-trimethylpentyl)phosphinic acid, H[DTMPep], contained in the commercial extractant Cyanex trademark 272 was used as a membrane carrier, because of its selectivity for U over calcium and magnesium. The water soluble complexing agent, 1-hydroxyethane-1,1-diphosphonic acid, HEDPA, was used as stripping agent. Polypropylene hollow-fibers and n-dodecane were used as polymeric support and diluent, respectively. Laboratory scale hollow-fiber modules were employed in a recycling mode, using as feed synthetic groundwater at pH 2, to confirm the capability of the proposed SLM system to separate and concentrate U(VI) in the strip solution. Information was obtained on the U(VI) concentration factor and on the long-term performance of the SLMs. Encouraging results were obtained both with a conventional module and with a module containing a carrier solution reservoir. Industrial scale modules were used at Hanford to test the SLM separation of U(VI) from real contaminated groundwater. The uranium concentration was reduced from approximately 3500 ppB to about 1 ppB in a few hours. 9 refs., 8 figs., 4 tabs

Study of the total uranium in underground water in the city of Jimenez, Chihuahua

International Nuclear Information System (INIS)

Renteria V, M.

2004-01-01

Samples of water of wells in the city of Jimenez, Chihuahua were analyzed, and its were determined the content of total uranium. It was used the technique of extraction of uranium from water adding Bis ( 2- ethylexyl) phosphate and scintillating Beta plate Hi safe, and the measures of the activities were carried out in the portable scintillation detector Thiathler- O Y HIDEX. The obtained interval of concentrations was 0.12 to 0.26 Bq/l that it is finds below the maximum permissible limits that it manages the Mexican regulation. It was found a significant correlation among the concentration of uranium and those total solid dissolved present in the samples. (Author)

Hydrothermal treatment of Hanford waste constituents

International Nuclear Information System (INIS)

Dell'Orco, P.C.

1992-01-01

The destruction of nitrates, organics, and ferrocyanides contained in underground storage tanks at the Department of Energy Hanford site in Washington state would significantly reduce the volume, hazard, and toxicity of the waste, while meeting pretreatment requirements for vitrification and grouting. The purpose of this study was to investigate the applicability of supercritical water oxidation for the destruction of nitrates organics, and ferrocyanides. Laboratory studies were performed studying oxidation/reduction reactions of nitrate with a simple organic compound, methanol, and with ammonia. Additional studies examined the reaction of nitrate with ferrocyanide. When reacted with methanol above 500 degrees C, greater than 99% of the nitrate was destroyed at the shortest residence times (< 6 seconds). At the same conditions, greater than 80% of the methanol was converted to bicarbonate and carbon dioxide. Studies involving the reaction of nitrate and nitrite with ammonia indicated that the reaction proceeds to completion in short residence times at temperatures above the critical point of water (374.2 degrees C). Ferrocyanide to also reacted rapidly with nitrate above the critical point, to produce carbon dioxide and ammonia

Radon and radon daughters in South African underground mines

International Nuclear Information System (INIS)

Rolle, R.

1980-01-01

Radon and the radon daughters are the radionuclides which primarily determine the level of the radiation hazard in underground uranium mines and to a smaller extent in non-uranium mines. Radon is a gas, and its daughters adsorb on aerosol particles which are of respirable size. The hazard thus arises from the alpha decay of radon and its daughters in contact with lung tissue. Radon is itself part of the uranium decay chain. The major radionuclide, 238 U, decays successively through thirteen shorter-lived radionuclides to 206 Pb. Radon is the only gaseous decay product at room temperature; the other twelve are solids. The main hazard presented by the uranium decay chain is normally determined by the radon concentration because gaseous transport can bring alpha emitters close to sensitive tissue. There is no such transport route for the other alpha emitters, and the level of beta and gamma radiation caused by the uranium decay chain generally presents a far lower external radiation hazard. Radon itself is the heaviest of the noble gases, which are He, Ne, Ar, Kr, Xe and Rn. Its chemical reactions are of no concern in regard to its potential hazard in mines as it may be considered inert. It does, however, have a solubility ten times higher than oxygen in water, and this can play a significant part in assisting the movement of the gas from the rock into airways. Radon continuously emanates into mine workings from uranium ores and from the uranium present at low concentrations in practically any rock. It has been found that the control of the exposure level is most effectively achieved by sound ventilation practices. In South African mines the standard of ventilation is generally high and exposure to radon and radon daughters is at acceptably low levels

Remediation of Uranium in the Hanford Vadose Zone Using Ammonia Gas: FY 2010 Laboratory-Scale Experiments

Energy Technology Data Exchange (ETDEWEB)

Szecsody, James E.; Truex, Michael J.; Zhong, Lirong; Qafoku, Nikolla; Williams, Mark D.; McKinley, James P.; Wang, Zheming; Bargar, John; Faurie, Danielle K.; Resch, Charles T.; Phillips, Jerry L.

2010-12-01

This investigation is focused on refining an in situ technology for vadose zone remediation of uranium by the addition of ammonia (NH3) gas. Objectives are to: a) refine the technique of ammonia gas treatment of low water content sediments to minimize uranium mobility by changing uranium surface phases (or coat surface phases), b) identify the geochemical changes in uranium surface phases during ammonia gas treatment, c) identify broader geochemical changes that occur in sediment during ammonia gas treatment, and d) predict and test injection of ammonia gas for intermediate-scale systems to identify process interactions that occur at a larger scale and could impact field scale implementation.Overall, NH3 gas treatment of low-water content sediments appears quite effective at decreasing aqueous, adsorbed uranium concentrations. The NH3 gas treatment is also fairly effective for decreasing the mobility of U-carbonate coprecipitates, but shows mixed success for U present in Na-boltwoodite. There are some changes in U-carbonate surface phases that were identified by surface phase analysis, but no changes observed for Na-boltwoodite. It is likely that dissolution of sediment minerals (predominantly montmorillonite, muscovite, kaolinite) under the alkaline conditions created and subsequent precipitation as the pH returns to natural conditions coat some of the uranium surface phases, although a greater understanding of these processes is needed to predict the long term impact on uranium mobility. Injection of NH3 gas into sediments at low water content (1% to 16% water content) can effectively treat a large area without water addition, so there is little uranium mobilization (i.e., transport over cm or larger scale) during the injection phase.

Remediation of Uranium in the Hanford Vadose Zone Using Ammonia Gas: FY 2010 Laboratory-Scale Experiments

International Nuclear Information System (INIS)

Szecsody, James E.; Truex, Michael J.; Zhong, Lirong; Qafoku, Nikolla; Williams, Mark D.; McKinley, James P.; Wang, Zheming; Bargar, John; Faurie, Danielle K.; Resch, Charles T.; Phillips, Jerry L.

2010-01-01

This investigation is focused on refining an in situ technology for vadose zone remediation of uranium by the addition of ammonia (NH3) gas. Objectives are to: (a) refine the technique of ammonia gas treatment of low water content sediments to minimize uranium mobility by changing uranium surface phases (or coat surface phases), (b) identify the geochemical changes in uranium surface phases during ammonia gas treatment, (c) identify broader geochemical changes that occur in sediment during ammonia gas treatment, and (d) predict and test injection of ammonia gas for intermediate-scale systems to identify process interactions that occur at a larger scale and could impact field scale implementation. Overall, NH3 gas treatment of low-water content sediments appears quite effective at decreasing aqueous, adsorbed uranium concentrations. The NH3 gas treatment is also fairly effective for decreasing the mobility of U-carbonate coprecipitates, but shows mixed success for U present in Na-boltwoodite. There are some changes in U-carbonate surface phases that were identified by surface phase analysis, but no changes observed for Na-boltwoodite. It is likely that dissolution of sediment minerals (predominantly montmorillonite, muscovite, kaolinite) under the alkaline conditions created and subsequent precipitation as the pH returns to natural conditions coat some of the uranium surface phases, although a greater understanding of these processes is needed to predict the long term impact on uranium mobility. Injection of NH3 gas into sediments at low water content (1% to 16% water content) can effectively treat a large area without water addition, so there is little uranium mobilization (i.e., transport over cm or larger scale) during the injection phase.

Quantifying and Predicting Reactive Transport of Uranium in Waste Plumes: Are Colloids and Nanoparticles Important?

International Nuclear Information System (INIS)

Jiamin Wan; Tetsu Tokunaga; Carl Steefel; Peter Burns

2006-01-01

The Hanford Site is the DOE's largest legacy waste site, with uranium (U) from plutonium processing being a major contaminant in its subsurface. Accidental release of highly concentrated high-level wastes left large quantities of U in the vadose zone under tank farms. The U contamination has been found in groundwater beneath the tank farms, indicating U is mobile

Uranium in the Wyoming Landscape Conservation Initiative study area, southwestern Wyoming

Science.gov (United States)

Wilson, Anna B.

2015-10-20

Wyoming has led the nation as the producer of uranium ore since 1995 and contains the largest reserves of any state. Approximately one third of Wyoming’s total production came from deposits in, or immediately adjacent to, the Wyoming Landscape Conservation Initiative (WLCI) study area in the southwestern corner of the state including all of Carbon, Lincoln, Sublette, Sweetwater, Uinta, and parts of southern Fremont Counties. Conventional open-pit and underground mining methods were employed in the study area until the early 1990s. Since the early 1990s, all uranium mining has been by in-situ recovery (also called in-situ leach). It is estimated that statewide remaining resources of 141,000 tonnes of uranium are about twice the 84,000 tonnes of uranium that the state has already produced.

The Field Lysimeter Test Facility (FLTF) at the Hanford Site: Installation and initial tests

International Nuclear Information System (INIS)

Gee, G.W.; Kirkham, R.R.; Downs, J.L.; Campbell, M.D.

1989-02-01

The objectives of this program are to test barrier design concepts and to demonstrate a barrier design that meets established performance criteria for use in isolating wastes disposed of near-surface at the Hanford Site. Specifically, the program is designed to assess how well the barriers perform in controlling biointrusion, water infiltration, and erosion, as well as evaluating interactions between environmental variables and design factors of the barriers. To assess barrier performance and design with respect to infiltration control, field lysimeters and small- and large-scale field plots are planned to test the performance of specific barrier designs under actual and modified (enhanced precipitation) climatic conditions. The Field Lysimeter Test Facility (FLTF) is located in the 600 Area of the Hanford Site just east of the 200 West Area and adjacent to the Hanford Meteorological Station. The FLTF data will be used to assess the effectiveness of selected protective barrier configurations in controlling water infiltration. The facility consists of 14 drainage lysimeters (2 m dia x 3 m deep) and four precision weighing lysimeters (1.5 m x 1.5 m x 1.7 m deep). The lysimeters are buried at grade and aligned in a parallel configuration, with nine lysimeters on each side of an underground instrument chamber. The lysimeters were filled with materials to simulate a multilayer protective barrier system. Data gathered from the FLTF will be used to compare key barrier components and to calibrate and test models for predicting long-term barrier performance

Two uranium mines in Niger: Somair Cominak

International Nuclear Information System (INIS)

Caleix, C.; Renardet, P.

1987-01-01

The research work undertaken by the Atomic Energy Commission on the territory of the Republic of the Niger has led to the discovery of two major uranium deposits, Arlit and Akouta, which are situated at the of the Sahara to the West of the massif of l'Air at approximately 850 km from Niamey. These deposits are exploited by two firms according to Nigerian law with a head office at Niamey. The firm Somair acts for Arlit and operates an open pit; the mining company Akouta works the Akouta deposit which is deeper and entails an underground operation. The production capacities are 2300 t and 2000 t of uranium metal per year, respectively [fr

Hanford Site technical baseline database. Revision 1

International Nuclear Information System (INIS)

Porter, P.E.

1995-01-01

This report lists the Hanford specific files (Table 1) that make up the Hanford Site Technical Baseline Database. Table 2 includes the delta files that delineate the differences between this revision and revision 0 of the Hanford Site Technical Baseline Database. This information is being managed and maintained on the Hanford RDD-100 System, which uses the capabilities of RDD-100, a systems engineering software system of Ascent Logic Corporation (ALC). This revision of the Hanford Site Technical Baseline Database uses RDD-100 version 3.0.2.2 (see Table 3). Directories reflect those controlled by the Hanford RDD-100 System Administrator. Table 4 provides information regarding the platform. A cassette tape containing the Hanford Site Technical Baseline Database is available

Uranium hexafluoride packaging tiedown systems overview at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio

International Nuclear Information System (INIS)

Becker, D.L.; Lindquist, M.R.

1993-01-01

The Portsmouth Gaseous Diffusion Plant (PORTS) in Piketon, Ohio, is operated by Martin Marietta Energy Systems, Inc., through the US Department of Energy-Oak Ridge Operations Office (DOE-ORO) for the US Department of Energy-Headquarters, Office of Nuclear Energy. The PORTS conducts those operations that are necessary for the production, packaging, and shipment of enriched uranium hexafluoride (UF 6 ). Uranium hexafluoride enriched greater than 1.0 wt percent 235 U shall be packaged in accordance with the US Department of Transportation (DOT) regulations of Title 49 CFR Parts 173 and 178, or in US Nuclear Regulatory Commission (NRC) or US Department of Energy (DOE) certified package designs. Concerns have been expressed regarding the various tiedown methods and condition of the trailers being used by some shippers/carriers for international transport of the UF 6 cylinders/overpacks. International shipments typically are not made using dedicated trailers, and numerous trailers have been received at PORTS with improperly and potentially dangerously secured overpacks. Because of the concerns about international shipments, the US Department of Energy-Headquarters (DOE-HQ) Office of Nuclear Energy, through DOE-HQ Transportation Management Division, requested Westinghouse Hanford Company (Westinghouse Hanford) to review UF 6 packaging tiedown and shipping practices used by PORTS; and where possible and appropriate, provide recommendations for enhancing these practices. Consequently, a team of two individuals from Westinghouse Hanford visited PORTS on March 5 and 6, 1990, for the purpose of conducting this review. The paper provides a brief discussion of the review activities and a summary of the resulting findings and recommendations

Environmental Assessment: Waste Tank Safety Program, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1994-02-01

The US Department of Energy (DOE) needs to take action in the near-term, to accelerate resolution of waste tank safety issues at the Hanford Site near the City of Richland, Washington, and reduce the risks associated with operations and management of the waste tanks. The DOE has conducted nuclear waste management operations at the Hanford Site for nearly 50 years. Operations have included storage of high-level nuclear waste in 177 underground storage tanks (UST), both in single-shell tank (SST) and double-shell tank configurations. Many of the tanks, and the equipment needed to operate them, are deteriorated. Sixty-seven SSTs are presumed to have leaked a total approximately 3,800,000 liters (1 million gallons) of radioactive waste to the soil. Safety issues associated with the waste have been identified, and include (1) flammable gas generation and episodic release; (2) ferrocyanide-containing wastes; (3) a floating organic solvent layer in Tank 241-C-103; (4) nuclear criticality; (5) toxic vapors; (6) infrastructure upgrades; and (7) interim stabilization of SSTs. Initial actions have been taken in all of these areas; however, much work remains before a full understanding of the tank waste behavior is achieved. The DOE needs to accelerate the resolution of tank safety concerns to reduce the risk of an unanticipated radioactive or chemical release to the environment, while continuing to manage the wastes safely

Underground storage tank soft waste dislodging and conveyance

International Nuclear Information System (INIS)

Wellner, A.F.S.

1993-01-01

The primary objective of this task is to demonstrate potential technical solutions and to acquire engineering data and information on the retrieval technologies applicable for use in retrieving waste from underground storage tanks. This task focuses on soft waste dislodging and conveyance technologies that would be used in conjunction with a manipulator-based retrieval system. This retrieval task focuses on Hanford single-shell tanks, but the results may also have applications to other waste retrieval problems. This work is part of the U.S. Department of Energy's (DOE's) Office of Technology Development, sponsored by the DOE's Richland Operations Office under the Underground Storage Tanks Integrated Demonstration (USTID) program. This task is one element of the whole waste dislodging and conveyance system in the USTID. The tank wastes contain both hazardous and radioactive constituents. This task focuses on the processes for dislodging and retrieving soft wastes, mainly sludge. Sludge consists primarily of heavy-metal, iron, and aluminum precipitates. Sludges vary greatly in their physical properties and may contain pockets of liquid. Sludges have been described as varying in consistency from thick slurry to sticky clay and as sandy with hard chunks of material. The waste is believed to have adhesive and cohesive properties. The quantitative physical properties of the wastes have yet to be measured. The waste simulants used in the testing program emulate the physical properties of the tank waste

The Hanford Site: An anthology of early histories

Energy Technology Data Exchange (ETDEWEB)

Gerber, M.S.

1993-10-01

This report discusses the following topics: Memories of War: Pearl Harbor and the Genesis of the Hanford Site; safety has always been promoted at the Hanford Site; women have an important place in Hanford Site history; the boom and bust cycle: A 50-year historical overview of the economic impacts of Hanford Site Operations on the Tri-Cities, Washington; Hanford`s early reactors were crucial to the sites`s history; T-Plant made chemical engineering history; the UO{sub 3} plant has a long history of service. PUREX Plant: the Hanford Site`s Historic Workhorse. PUREX Plant Waste Management was a complex challenge; and early Hanford Site codes and jargon.

Uranium - a challenging mining business

International Nuclear Information System (INIS)

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

2007-01-01

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

Uranium(VI) sorption on iron oxides in Hanford Site sediment: Application of a surface complexation model

International Nuclear Information System (INIS)

Um, Wooyong; Serne, R. Jeffrey; Brown, Christopher F.; Rod, Kenton A.

2008-01-01

Sorption of U(VI) on Hanford fine sand (HFS) with varying Fe-oxide (especially ferrihydrite) contents showed that U(VI) sorption increased with the incremental addition of synthetic ferrihydrite into HFS, consistent with ferrihydrite being one of the most reactive U(VI) sorbents present in natural sediments. Surface complexation model (SCM) calculations for U(VI) sorption, using only U(VI) surface-reaction constants obtained from U(VI) sorption data on freshly synthesized ferrihydrite at different pHs, were similar to the measured U(VI) sorption results on pure synthetic ferrihydrite and on HFS with high contents of ferrihydrite (5 wt%) added. However, the SCM prediction using only U(VI) sorption reactions and constants for synthetic ferrihydrite overestimated U(VI) sorption on the natural HFS or HFS with addition of low amounts of added ferrihydrite (1 wt% added). Over-predicted U(VI) sorption was attributed to reduced reactivity of natural ferrihydrite present in Hanford Site sediments, compared to freshly prepared synthetic ferrihydrite. Even though the SCM general composite (GC) approach is considered to be a semi-quantitative estimation technique for contaminant sorption, which requires systematic experimental data on the sorbent-sorbate system being studied to obtain credible SCM parameters, the general composite SCM model was still found to be a useful technique for describing U(VI) sorption on natural sediments. Based on U(VI) batch sorption results, two simple U(VI) monodentate surface species, SO U O 2 HCO 3 and SO U O 2 OH on ferrihydrite and phyllosillicate in HFS, respectively, can be successfully used to describe U(VI) sorption onto Hanford Site sediment contacting varying geochemical solutions

Analysis on present radon ventilation situation of Chinese uranium mines

International Nuclear Information System (INIS)

Li Xianjie; Hu Penghua

2010-01-01

Mine Ventilation is the most important way in lowering radon of uranium mines. At present, radon and radon daughter concentration of underground air is 3∼5 times higher than any other air concentration of foreign uranium mines, as the same input for Protective Ventilation between Chinese uranium mines with compaction methodology and international advanced uranium mines. In this passage, through the analysis of Ventilation Radon Reduction status in Chinese uranium mines and the comparison of advantages and shortcomings between variety of ventilation and radon reduction, it illuminated the reasons of higher radon and radon daughter concentration in Chinese uranium mines and put forward some problems in three aspects, which are Ventilation Radon Reduction Theory, Ventilation Radon Reduction Measures and Ventilation Management. And to above problems, this passage put forward some proposals and measures about some aspects, such as strengthen examination and verification and monitoring practical situation, making clear ventilation plan, in according to mining sequence strictly, training Ventilation technician forcefully, enhance Ventilation System management, development of Ventilation Radon Reduction technology research in uranium mines and carrying out ventilation equipments as soon as possible in further and so on. (authors)

Hanford well custodians. Revision 1

International Nuclear Information System (INIS)

Schatz, A.L.; Underwood, D.J.

1995-01-01

The Hanford Site Groundwater Protection Management Program recognized the need to integrate monitoring well activities in a centralized manner. A key factor to Hanford Site well integration was the need to clearly identify a responsible party for each of the wells. WHC was asked to identify all wells on site, the program(s) using each well, and the program ultimately responsible for the well. This report lists the custodian and user(s) for each Hanford well and supplies a comprehensive list of all decommissioned and orphaned wells on the Hanford Site. This is the first update to the original report released in December 1993

Hanford Site peak gust wind speeds

International Nuclear Information System (INIS)

Ramsdell, J.V.

1998-01-01

Peak gust wind data collected at the Hanford Site since 1945 are analyzed to estimate maximum wind speeds for use in structural design. The results are compared with design wind speeds proposed for the Hanford Site. These comparisons indicate that design wind speeds contained in a January 1998 advisory changing DOE-STD-1020-94 are excessive for the Hanford Site and that the design wind speeds in effect prior to the changes are still appropriate for the Hanford Site

A Strategy to Conduct an Analysis of the Long-Term Performance of Low-Activity Waste Glass in a Shallow Subsurface Disposal System at Hanford

Energy Technology Data Exchange (ETDEWEB)

Neeway, James J.; Pierce, Eric M.; Freedman, Vicky L.; Ryan, Joseph V.; Qafoku, Nikolla

2014-08-04

The federal facilities located on the Hanford Site in southeastern Washington State have been used extensively by the U.S. government to produce nuclear materials for the U.S. strategic defense arsenal. Currently, the Hanford Site is under the stewardship of the U.S. Department of Energy (DOE) Office of Environmental Management (EM). A large inventory of radioactive and mixed waste resulting from the production of nuclear materials has accumulated, mainly in 177 underground single- and double-shell tanks located in the central plateau of the Hanford Site (Mann et al., 2001). The DOE-EM Office of River Protection (ORP) is proceeding with plans to immobilize and permanently dispose of the low-activity waste (LAW) fraction onsite in a shallow subsurface disposal facility (the Integrated Disposal Facility [IDF]). Pacific Northwest National Laboratory (PNNL) was contracted to provide the technical basis for estimating radionuclide release from the engineered portion of the IDF (the source term) as part of an immobilized low-activity waste (ILAW) glass testing program to support future IDF performance assessments (PAs).

Hanford recycling

Energy Technology Data Exchange (ETDEWEB)

Leonard, I.M.

1996-09-01

This paper is a study of the past and present recycling efforts on the Hanford site and options for future improvements in the recycling program. Until 1996, recycling goals were voluntarily set by the waste generators: this year, DOE has imposed goals for all its sites to accomplish by 1999. Hanford is presently meeting the voluntary site goals, but may not be able to meet all the new DOE goals without changes to the program. Most of these new DOE goals are recycling goals: * Reduce the generation of radioactive (low-level) waste from routine operations 50 percent through source reduction and recycling. * Reduce the generation of low-level mixed waste from routine operations 50 percent through source reduction and recycling. * Reduce the generation of hazardous waste from routine operations 50 percent through source reduction and recycling. * Recycle 33 percent of the sanitary waste from all operations. * Increase affirmative procurement of EPA-designated recycled items to 100 percent. The Hanford recycling program has made great strides-there has been a 98 percent increase in the amount of paper recycled since its inception in 1990. Hanford recycles paper, chemicals cardboard, tires, oil, batteries, rags, lead weights, fluorescent tubes, aerosol products, concrete, office furniture, computer software, drums, toner cartridges, and scrap metal. Many other items are recycled or reused by individual groups on a one time basis without a formal contract. Several contracts are closed-loop contracts which involve all parts of the recycle loop. Considerable savings are generated from recycling, and much more is possible with increased attention and improvements to this program. General methods for improving the recycling program to ensure that the new goals can be met are: a Contract and financial changes 0 Tracking database and methods improvements 0 Expanded recycling efforts. Specifically, the Hanford recycling program would be improved by: 0 Establishing one overall

Analysis of sludge from Hanford K East Basin canisters

Energy Technology Data Exchange (ETDEWEB)

Makenas, B.J. [ed.] [comp.] [DE and S Hanford, Inc., Richland, WA (United States); Welsh, T.L. [B and W Protec, Inc. (United States); Baker, R.B. [DE and S Hanford, Inc., Richland, WA (United States); Hoppe, E.W.; Schmidt, A.J.; Abrefah, J.; Tingey, J.M.; Bredt, P.R.; Golcar, G.R. [Pacific Northwest National Lab., Richland, WA (United States)

1997-09-12

Sludge samples from the canisters in the Hanford K East Basin fuel storage pool have been retrieved and analyzed. Both chemical and physical properties have been determined. The results are to be used to determine the disposition of the bulk of the sludge and to assess the impact of residual sludge on dry storage of the associated intact metallic uranium fuel elements. This report is a summary and review of the data provided by various laboratories. Although raw chemistry data were originally reported on various bases (compositions for as-settled, centrifuged, or dry sludge) this report places all of the data on a common comparable basis. Data were evaluated for internal consistency and consistency with respect to the governing sample analysis plan. Conclusions applicable to sludge disposition and spent fuel storage are drawn where possible.

Women and the Hanford Site

Science.gov (United States)

Gerber, Michele

2014-03-01

When we study the technical and scientific history of the Manhattan Project, women's history is sometimes left out. At Hanford, a Site whose past is rich with hard science and heavy construction, it is doubly easy to leave out women's history. After all, at the World War II Hanford Engineer Works - the earliest name for the Hanford Site - only nine percent of the employees were women. None of them were involved in construction, and only one woman was actually involved in the physics and operations of a major facility - Dr. Leona Woods Marshall. She was a physicist present at the startup of B-Reactor, the world's first full-scale nuclear reactor - now a National Historic Landmark. Because her presence was so unique, a special bathroom had to be built for her in B-Reactor. At World War II Hanford, only two women were listed among the nearly 200 members of the top supervisory staff of the prime contractor, and only one regularly attended the staff meetings of the Site commander, Colonel Franklin Matthias. Overall, women comprised less than one percent of the managerial and supervisory staff of the Hanford Engineer Works, most of them were in nursing or on the Recreation Office staff. Almost all of the professional women at Hanford were nurses, and most of the other women of the Hanford Engineer Works were secretaries, clerks, food-service workers, laboratory technicians, messengers, barracks workers, and other support service employees. The one World War II recruiting film made to attract women workers to the Site, that has survived in Site archives, is entitled ``A Day in the Life of a Typical Hanford Girl.'' These historical facts are not mentioned to criticize the past - for it is never wise to apply the standards of one era to another. The Hanford Engineer Works was a 1940s organization, and it functioned by the standards of the 1940s. Just as we cannot criticize the use of asbestos in constructing Hanford (although we may wish they hadn't used so much of it), we

Full Focus Needed on Finishing Hanford's Waste Treatment Plant - 12196

Energy Technology Data Exchange (ETDEWEB)

Dahl, Suzanne; Biyani, Rabindra; Holmes, Erika [Washington State Department of Ecology, Richland, WA 99354 (United States)

2012-07-01

The United States Department of Energy's (US DOE's) Hanford Nuclear Site has 177 underground waste storage tanks located 19 to 24 km (12 to 15 miles) from the Columbia River in south-central Washington State. Hanford's tanks now hold about 212,000 cu m (56 million gallons) of highly radioactive and chemically hazardous waste. Sixty-seven tanks have leaked an estimated 3,785 cu m (1 million gallons) of this waste into the surrounding soil. Further releases to soil, groundwater, and the Columbia River are the inevitable result of the tanks continuing to age. The risk from this waste is recognized as a threat to the Northwest by both State and Federal governments. US DOE and Bechtel National, Inc., are building the Waste Treatment and Immobilization Plant (WTP) to treat and vitrify (immobilize in glass) the waste from Hanford's tanks. As is usual for any groundbreaking project, problems have arisen that must be resolved as they occur if treatment is to take place as specified in the court-enforceable Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) and the Consent Decree, entered into by US DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology (Ecology). At times, US DOE's approach to solving these critical issues seems to have caused undue wastes of time, energy, and, ultimately, public funds. Upon reviewing the history of Hanford's tank waste treatment project, Ecology hopes that constructive criticism of past failures and praise of successes will inspire US DOE to consider changing practices, be more transparent with regulatory agencies and the public, and take a 'lean production' approach to successfully completing this project. All three Tri-Party Agreement agencies share the goal of completing WTP on time, ensuring it is operational and in compliance with safety standards. To do this, Ecology believes US DOE should: - Maintain focus on the primary goal of

Introduction to the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Cushing, C.E.

1995-06-01

This section of the 1994 Hanford Site Environmental Report discusses the Site mission and provides general information about the site. The U.S. DOE has established a new mission for Hanford including: Management of stored wastes, environmental restoration, research and development, and development of new technologies. The Hanford Reservation is located in south central Washington State just north of the confluence of the Snake and Yakima Rivers with the Columbia River. The approximately 1,450 square kilometers which comprises the Hanford Site, with restricted public access, provides a buffer for the smaller areas within the site which have historically been used for the production of nuclear materials, radioactive waste storage, and radioactive waste disposal.

Hanford site waste tank characterization

International Nuclear Information System (INIS)

De Lorenzo, D.S.; Simpson, B.C.

1994-08-01

This paper describes the on-going work in the characterization of the Hanford-Site high-level waste tanks. The waste in these tanks was produced as part of the nuclear weapons materials processing mission that occupied the Hanford Site for the first 40 years of its existence. Detailed and defensible characterization of the tank wastes is required to guide retrieval, pretreatment, and disposal technology development, to address waste stability and reactivity concerns, and to satisfy the compliance criteria for the various regulatory agencies overseeing activities at the Hanford Site. The resulting Tank Characterization Reports fulfill these needs, as well as satisfy the tank waste characterization milestones in the Hanford Federal Facility Agreement and Consent Order

Hanford Surplus Facilities Program plan

International Nuclear Information System (INIS)

Hughes, M.C.; Wahlen, R.K.; Winship, R.A.

1989-09-01

The Hanford Surplus Facilities Program is responsible for the safe and cost-effective surveillance, maintenance, and decommissioning of surplus facilities at the Hanford Site. The management of these facilities requires a surveillance and maintenance program to keep them in a safe condition and development of a plan for ultimate disposition. Criteria used to evaluate each factor relative to decommissioning are based on the guidelines presented by the US Department of Energy-Richland Operations Office, Defense Facilities Decommissioning Program Office, and are consistent with the Westinghouse Hanford Company commitment to decommission the Hanford Site retired facilities in the safest and most cost-effective way achievable. This document outlines the plan for managing these facilities to the end of disposition

Introduction to the Hanford Site

International Nuclear Information System (INIS)

Cushing, C.E.

1995-01-01

This section of the 1994 Hanford Site Environmental Report discusses the Site mission and provides general information about the site. The U.S. DOE has established a new mission for Hanford including: Management of stored wastes, environmental restoration, research and development, and development of new technologies. The Hanford Reservation is located in south central Washington State just north of the confluence of the Snake and Yakima Rivers with the Columbia River. The approximately 1,450 square kilometers which comprises the Hanford Site, with restricted public access, provides a buffer for the smaller areas within the site which have historically been used for the production of nuclear materials, radioactive waste storage, and radioactive waste disposal

Hanford Site Tank 241-SY-101, damaged equipment removal

International Nuclear Information System (INIS)

Titzler, P.A.; Legare, D.E.; Barrus, H.G.

1993-11-01

Hanford Site Tank 241-SY-101 has a history of generating hydrogen-nitrous oxide gases. The gases are generated and trapped in the non-convective waste layer near the bottom of the 23-m- (75-ft-) diameter underground tank. Approximately every three months the pressure in the tank is relieved as the trapped gases are released through or around the surface crust into the tank dome. This process moves large amounts of liquid waste and crust material around in the tank. The moving waste displaced air lances and thermocouple assemblies (2-in. schedule-40 pipe) installed in four tank risers and permanently bent them to a maximum angle of 40 degrees. The bends were so severe that assemblies could not be removed from the tank using the originally designed hardware. Just after the tank releases the trapped gas, a 20-to-30-day work ''window'' opens

Analysis of queuing mine-cars affecting shaft station radon concentrations in Quzhou uranium mine, eastern China

Directory of Open Access Journals (Sweden)

Changshou Hong

2018-04-01

Full Text Available Shaft stations of underground uranium mines in China are not only utilized as waiting space for loaded mine-cars queuing to be hoisted but also as the principal channel for fresh air taken to working places. Therefore, assessment of how mine-car queuing processes affect shaft station radon concentration was carried out. Queuing network of mine-cars has been analyzed in an underground uranium mine, located in Quzhou, Zhejiang province of Eastern China. On the basis of mathematical analysis of the queue network, a MATLAB-based quasi-random number generating program utilizing Monte-Carlo methods was worked out. Extensive simulations were then implemented via MATALB operating on a DELL PC. Thereafter, theoretical calculations and field measurements of shaft station radon concentrations for several working conditions were performed. The queuing performance measures of interest, like average queuing length and waiting time, were found to be significantly affected by the utilization rate (positively correlated. However, even with respect to the “worst case”, the shaft station radon concentration was always lower than 200 Bq/m3. The model predictions were compared with the measuring results, and a satisfactory agreement was noted. Under current working conditions, queuing-induced variations of shaft station radon concentration of the study mine are not remarkable. Keywords: Hoist and Transport Systems, Mine-cars, Queuing Simulation, Radon Concentration, Underground Uranium Mine

The Hanford Site: An anthology of early histories

International Nuclear Information System (INIS)

Gerber, M.S.

1993-10-01

This report discusses the following topics: Memories of War: Pearl Harbor and the Genesis of the Hanford Site; safety has always been promoted at the Hanford Site; women have an important place in Hanford Site history; the boom and bust cycle: A 50-year historical overview of the economic impacts of Hanford Site Operations on the Tri-Cities, Washington; Hanford's early reactors were crucial to the sites's history; T-Plant made chemical engineering history; the UO 3 plant has a long history of service. PUREX Plant: the Hanford Site's Historic Workhorse. PUREX Plant Waste Management was a complex challenge; and early Hanford Site codes and jargon

French uranium mining sites remediation

International Nuclear Information System (INIS)

Roche, M.

2002-01-01

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

Determination of uranium metal concentration in irradiated fuel storage basin sludge using selective dissolution

International Nuclear Information System (INIS)

Delegard, C.H.; Sinkov, S.I.; Chenault, J.W.; Schmidt, A.J.; Pool, K.N.; Welsh, T.L.

2014-01-01

Irradiated uranium metal fuel was stored underwater in the K East and K West storage basins at the US Department of Energy Hanford Site. The uranium metal under damaged cladding reacted with water to generate hydrogen gas, uranium oxides, and spalled uranium metal particles which intermingled with other particulates to form sludge. While the fuel has been removed, uranium metal in the sludge remains hazardous. An expeditious routine method to analyze 0.03 wt% uranium metal in the presence of >30 wt% total uranium was needed to support safe sludge management and processing. A selective dissolution method was designed based on the rapid uranium oxide dissolution but very low uranium metal corrosion rates in hot concentrated phosphoric acid. The uranium metal-bearing heel from the phosphoric acid step then is rinsed before the uranium metal is dissolved in hot concentrated nitric acid for analysis. Technical underpinnings of the selective dissolution method, including the influence of sludge components, were investigated to design the steps and define the reagents, quantities, concentrations, temperatures, and times within the selective dissolution analysis. Tests with simulant sludge proved the technique feasible. Tests with genuine sludge showed a 0.0028 ± 0.0037 wt% (at one standard deviation) uranium metal analytical background, a 0.011 wt% detection limit, and a 0.030 wt% quantitation limit in settled (wet) sludge. In tests using genuine K Basin sludge spiked with uranium metal at concentrations above the 0.030 wt% ± 25 % (relative) quantitation limit, uranium metal recoveries averaged 99.5 % with a relative standard deviation of 3.5 %. (author)

Hanford Environmental Management Program implementation plan

International Nuclear Information System (INIS)

1988-08-01

The Hanford Environmental Management Program (HEMP) was established to facilitate compliance with the applicable environmental statues, regulations, and standards on the Hanford Site. The HEMP provides a structured approach to achieve environmental management objectives. The Hanford Environmental Management Program Plan (HEMP Plan) was prepared as a strategic level planning document to describe the program management, technical implementation, verification, and communications activities that guide the HEMP. Four basic program objectives are identified in the HEMP Plan as follows: establish ongoing monitoring to ensure that Hanford Site operations comply with environmental requirements; attain regulatory compliance through the modification of activities; mitigate any environmental consequences; and minimize the environmental impacts of future operations at the Hanford Site. 2 refs., 24 figs., 27 tabs

Linearity and Reversibility of Iodide Adsorption on Sediments from Hanford, Washington Under Water Saturated Conditions

International Nuclear Information System (INIS)

Um, Wooyong; Serne, R. Jeffrey; Krupka, Kenneth M.

2004-01-01

A series of adsorption and desorption experiments were completed to determine the linearity of iodide adsorption, as a function of concentration, and its reversibility onto sediment for geochemical conditions germane to the proposed disposal of low-level radioactive waste by the U.S. Department of Energy's Immobilized Low Activity Waste (ILAW) program at the Hanford Site in southeastern Washington. Iodine-129 is predicted to be one of the top three long-term risk drivers based on past performance assessment conducted for the eventual disposal of the low-level portion of radioactive wastes currently stored in underground storage tanks at Hanford, because iodide exhibits little adsorption affinity to mineral surfaces resulting in high mobility in the subsurface environment. Adsorption experiments, conducted with Hanford formation sediments and groundwater spiked with dissolved 125I (as an analog tracer for 129I), indicated that iodide adsorption was very low at pH 7.5 and could be represented by a linear isotherm up to a total concentration of 100 mg/L dissolved iodide. The linearity of iodide adsorption up to concentrations of 100 mg/L validates the use of the linear Kd construct in transport models to predict the fate and transport of 129I in subsurface systems at Hanford. The results of desorption experiments indicated that up to 60% of adsorbed iodide was readily desorbed after 14 days by the same groundwater solution. Iodide adsorption was considered to be partially reversible or weakly binding on the sediments. Even though small amount of initial iodide is retarded by adsorption reactions at mineral-water interfaces, the weak adsorption affinity results in release of iodide when iodide free pore waters and ground waters contact the contaminated sediments in the vadose zone and aquifer systems

TREATABILITY TEST PLAN FOR DEEP VADOSE ZONE REMEDIATION AT THE HANFORD'S SITE CENTRAL PLATEAU

International Nuclear Information System (INIS)

PETERSEN SW; MORSE JG; TRUEX MJ; LAST GV

2007-01-01

A treatability test plan has been prepared to address options for remediating portions of the deep vadose zone beneath a portion of the U.S. Department of Energy's (DOE's) Hanford Site. The vadose zone is the region of the subsurface that extends from the ground surface to the water table. The overriding objective of the treatability test plan is to recommend specific remediation technologies and laboratory and field tests to support the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 and Resource Conservation and Recovery Act of 1976 remedial decision-making process in the Central Plateau of the Hanford Site. Most of the technologies considered involve removing water from the vadose zone or immobilizing the contaminants to reduce the risk of contaminating groundwater. A multi-element approach to initial treatability testing is recommended, with the goal of providing the information needed to evaluate candidate technologies. The proposed tests focus on mitigating two contaminants--uranium and technetium. Specific technologies are recommended for testing at areas that may affect groundwater in the future, but a strategy to test other technologies is also presented

High-level core sample x-ray imaging at the Hanford Site

International Nuclear Information System (INIS)

Weber, J.R.; Keve, J.K.

1995-10-01

Waste tank sampling of radioactive high-level waste is required for continued operations, waste characterization, and site safety. Hanford Site tank farms consist of 28 double-shell and 149 single-shell underground storage tanks. The single shell tanks are out-of-service an no longer receive liquid waste. Core samples of salt cake and sludge waste are remotely obtained using truck-mounted, core drill platforms. Samples are recovered from tanks through a 2.25 inch (in.) drill pipe in 26-in. steel tubes, 1.5 in. diameter. Drilling parameters vary with different waste types. Because sample recovery has been marginal an inadequate at times, a system was needed to provide drill truck operators with ''real-time feedback'' about the physical condition of the sample and the percent recovery, prior to making nuclear assay measurements and characterizations at the analytical laboratory. The Westinghouse Hanford Company conducted proof-of-principal radiographic testing to verify the feasibility of a proposed imaging system. Tests were conducted using an iridium 192 radiography source to determine the effects of high radiation on image quality. The tests concluded that samplers with a dose rate in excess of 5000 R/hr could be imaged with only a slight loss of image quality and samples less than 1000 R/hr have virtually no effect on image quality. The Mobile Core Sample X-Ray Examination System, a portable vendor-engineered assembly, has components uniquely configured to produce a real-time radiographic system suitable for safely examining radioactive tank core segments collected at the Hanford Site. The radiographic region of interest extends from the bottom (valve) of the sampler upward 19 to 20 in. The purpose of the Mobile Core Sample X-Ray Examination System is to examine the physical contents of core samples after removal from the tank and prior to placement in an onsite transfer cask

Hanford spent fuel inventory baseline

International Nuclear Information System (INIS)

Bergsman, K.H.

1994-01-01

This document compiles technical data on irradiated fuel stored at the Hanford Site in support of the Hanford SNF Management Environmental Impact Statement. Fuel included is from the Defense Production Reactors (N Reactor and the single-pass reactors; B, C, D, DR, F, H, KE and KW), the Hanford Fast Flux Test Facility Reactor, the Shipping port Pressurized Water Reactor, and small amounts of miscellaneous fuel from several commercial, research, and experimental reactors

Hanford and Savannah River Site Programmatic and Technical Integration

International Nuclear Information System (INIS)

Ramsey, William Gene

2013-01-01

Abstract only. The Hanford Site and the Savannah River Site (SRS) were the primary plutonium production facilities within the U.S. nuclear weapons complex. Radioactive wastes were generated as part of these missions and are stored in similar fashion. The majority of radioactivity maintained by the two sites is located in underground carbon steel tanks in the physical form of supernatant, saltcake, or sludge. Disposition of SRS tank waste is ongoing by converting it into glass (pathway for sludge and radionuclides separated from supernatant or dissolved saltcake) or cement (pathway for the decontaminated supernatant and dissolved saltcake). Tank closure activity has also begun at SRS and will continue for the duration of mission. The Hanford tank waste inventory is roughly 2/3rds larger than SRS's by volume- but nominally half the radioactivity. The baseline disposition path includes high-level and low-activity waste vitrification with separate disposition of contact-handled transuranic tank waste. Retrieval of tank waste from aging single shell tanks (SSTs) into double-shell tanks (DSTs) is currently ongoing. As vitrification commences later this decade, Hanford will be in a similar operations mode as SRS. Site integration is increasing as the missions align. The ongoing integration is centered on key issues that impact both sites- regardless of mission timeframe. Three recent workshop exchanges have been held to improve communication with the primary intent of improving operations and technical work organization. The topics of these workshops are as follows: DST space utilization, optimization, and closure; Waste Feed Qualification; and, Cementitious Waste Forms. Key goals for these and future exchanges include aligning research and technology, preparing for joint initiatives (to maximize budgetary value for the customer), and reviewing lessons learned. Each site has played a leading role in the development of technology and operational practices that can be used

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

International Nuclear Information System (INIS)

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

2002-01-01

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

Challenges in radon management at uranium mining operations

International Nuclear Information System (INIS)

Paulka, Sharon

2011-01-01

Full text: Radon and its radioactive decay products are present some unique challenges to radiation protection professionals working at the uranium mining operations. This paper will detail some examples of these challenges and methods that can be employed to ensure doses to workers and members of the public are kept As Low As Reasonably Achievable (ALARA). Examples will be presented for conventional open pit and underground mining and In Situ recovery operations. One of the challenges facing new operations seeking approval is the demonstration that radon and its radioactive decay products sourced from the operations will not adversely impact local populations, Methodologies recently employed in the most recent environmental impact statements from uranium mining companies seeking approval are reviewed. The International Commission of Radiological Protection are currently reviewing the dose conversion factors used radon and its decay products. The challenges this change will present to uranium mining operators are presented.

In situ leaching of uranium in South Australia

International Nuclear Information System (INIS)

Matthews, D.

1998-01-01

The proposed two new uranium mines at Beverley and Honeymoon, South Australia plan to use the cheap but potentially polluting process of in situ leaching (ISL) and permission has already been given for experimental underground leaching at Beverley. The mining industry describes ISL as environmentally benign because, instead of excavating, a corrosive liquid such as sulphuric acid is used. The liquid, sometimes 10000 times more acid than the aquifer water, is pumped into the ground in order to leach out the uranium and the resulting solution is then pumped to the surface where the uranium is extracted. Because the groundwater is salty and radioactive, the mining companies regard it as useless, so its contamination by ISL is considered of no concern. Salty radioactive water can be purified or desalinated and such processes are commonly used by mining companies such as Western Mining Corporation at Roxby Downs. (author)

Hanford Site solid waste acceptance criteria

International Nuclear Information System (INIS)

Willis, N.P.; Triner, G.C.

1991-09-01

Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

FTIR fiber optic methods for the analysis of Hanford Site waste

International Nuclear Information System (INIS)

Rebagay, T.V.; Cash, R.J.; Dodd, D.A.

1995-06-01

Sampling and chemical characterization of mixed high-level waste stored in underground tanks at the Hanford Site is currently in progress. Waste tank safety concerns have provided impetus to analyze this waste. A major safety issue is the possibility of significant concentrations of fuel (ferrocyanide and/or organic compounds) in contact with oxidizers (nitrates and nitrites). It is postulated that under dry conditions and elevated temperatures, ferrocyanide- and/or organic-bearing wastes could undergo rapid exothermic reactions. To maintain the tanks in a safe condition, data are needed on the moisture and fuel concentrations in the waste. Because of the highly radioactive nature of the waste, non-radioactive waste simulants mimicking actual waste are used to provide an initial basis for identifying realistic waste tank safety concerns. Emphasis has been placed on the use of new or existing Fourier transform infrared (FTIR)-based systems with potential for field or tank deployment to perform in situ remote waste characterization. Near-infrared diffuse reflectance and mid-infrared attenuated total reflectance fiber optic probes coupled to a Bio-Rad FTS 60A spectrometry system have been evaluated. The near-infrared diffuse reflectance fiber probe system has also been used for preliminary screening of the moisture content and chemical composition of actual Hanford Site waste tank waste core samples. The attributes of this method for analyzing actual radioactive waste are discussed

Technetium Chemistry in High-Level Waste

International Nuclear Information System (INIS)

Hess, Nancy J.

2006-01-01

Tc contamination is found within the DOE complex at those sites whose mission involved extraction of plutonium from irradiated uranium fuel or isotopic enrichment of uranium. At the Hanford Site, chemical separations and extraction processes generated large amounts of high level and transuranic wastes that are currently stored in underground tanks. The waste from these extraction processes is currently stored in underground High Level Waste (HLW) tanks. However, the chemistry of the HLW in any given tank is greatly complicated by repeated efforts to reduce volume and recover isotopes. These processes ultimately resulted in mixing of waste streams from different processes. As a result, the chemistry and the fate of Tc in HLW tanks are not well understood. This lack of understanding has been made evident in the failed efforts to leach Tc from sludge and to remove Tc from supernatants prior to immobilization. Although recent interest in Tc chemistry has shifted from pretreatment chemistry to waste residuals, both needs are served by a fundamental understanding of Tc chemistry

Technetium Chemistry in HLW

International Nuclear Information System (INIS)

Hess, Nancy J.; Felmy, Andrew R.; Rosso, Kevin M.; Xia Yuanxian

2005-01-01

Tc contamination is found within the DOE complex at those sites whose mission involved extraction of plutonium from irradiated uranium fuel or isotopic enrichment of uranium. At the Hanford Site, chemical separations and extraction processes generated large amounts of high level and transuranic wastes that are currently stored in underground tanks. The waste from these extraction processes is currently stored in underground High Level Waste (HLW) tanks. However, the chemistry of the HLW in any given tank is greatly complicated by repeated efforts to reduce volume and recover isotopes. These processes ultimately resulted in mixing of waste streams from different processes. As a result, the chemistry and the fate of Tc in HLW tanks are not well understood. This lack of understanding has been made evident in the failed efforts to leach Tc from sludge and to remove Tc from supernatants prior to immobilization. Although recent interest in Tc chemistry has shifted from pretreatment chemistry to waste residuals, both needs are served by a fundamental understanding of Tc chemistry

SLUDGE RETRIEVAL FROM HANFORD K WEST BASIN SETTLER TANKS

International Nuclear Information System (INIS)

Erpenbeck, E.G.; Leshikar, G.A.

2011-01-01

In 2010, an innovative, remotely operated retrieval system was deployed to successfully retrieve over 99.7% of the radioactive sludge from ten submerged tanks in Hanford's K-West Basin. As part of K-West Basin cleanup, the accumulated sludge needed to be removed from the 0.5 meter diameter by 5 meter long settler tanks and transferred approximately 45 meters to an underwater container for sampling and waste treatment. The abrasive, dense, non-homogeneous sludge was the product of the washing process of corroded nuclear fuel. It consists of small (less than 600 micron) particles of uranium metal, uranium oxide, and various other constituents, potentially agglomerated or cohesive after 10 years of storage. The Settler Tank Retrieval System (STRS) was developed to access, mobilize and pump out the sludge from each tank using a standardized process of retrieval head insertion, periodic high pressure water spray, retraction, and continuous pumping of the sludge. Blind operations were guided by monitoring flow rate, radiation levels in the sludge stream, and solids concentration. The technology developed and employed in the STRS can potentially be adapted to similar problematic waste tanks or pipes that must be remotely accessed to achieve mobilization and retrieval of the sludge within.

Uranium concentrations in the water consumed by the resident population in the vicinity of the Lagoa Real uranium province, Bahia, Brazil

Energy Technology Data Exchange (ETDEWEB)

Silva, Luciana S. [State University of Bahia (UNEB), Campus Caetite, BA (Brazil); Pecequilo, Brigitte R.S.; Sarkis, Jorge; Nisti, Marcelo B., E-mail: brigitte@ipen.br, E-mail: jesarkis@ipen.br, E-mail: mbnisti@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

The Lagoa Real Uranium Province, situated in South Central Bahia in the region of Caetite and Lagoa Real, is considered the most important monomineralic province of Brazil. The urban population who lives in the proximities of this uranium province in the cities of Caetite, Lagoa Real and Livramento uses public supply water, while the inhabitants of the rural area due to long terms of dry weather use water from wells, cisterns, small dams, reservoirs and dikes which are supplied with the rains. In this work it was determined the concentration of uranium in the water consumed by the rural and urban population living in the proximities of the Lagoa Real Uranium Province. The study comprehends 32 sampling spots spread throughout the region of interest. Samples were collected in January and July 2010, covering superficial, underground and public supply water from the region. The uranium concentrations were determined by an inductively coupled plasma mass spectrometer (ICP-MS). Preliminary results showed that the uranium concentrations in the water from the Lagoa Real Uranium Province varied from 0.064 {+-} 0.005 {mu}g.L{sup -1} to 90 {+-} 1,5 {+-}g.L{sup -1}. It was observed that only two of them obtained values higher than the World Health Organization's recommended limit (2011) of 30 {mu}g.L{sup -1} for maximum uranium concentration in the water for human consumption. For a conclusive evaluation, the uranium concentrations results will be analyzed together with total alpha and beta concentrations determined elsewhere for the same samples. (author)

Uranium concentrations in the water consumed by the resident population in the vicinity of the Lagoa Real uranium province, Bahia, Brazil

International Nuclear Information System (INIS)

Silva, Luciana S.; Pecequilo, Brigitte R.S.; Sarkis, Jorge; Nisti, Marcelo B.

2011-01-01

The Lagoa Real Uranium Province, situated in South Central Bahia in the region of Caetite and Lagoa Real, is considered the most important monomineralic province of Brazil. The urban population who lives in the proximities of this uranium province in the cities of Caetite, Lagoa Real and Livramento uses public supply water, while the inhabitants of the rural area due to long terms of dry weather use water from wells, cisterns, small dams, reservoirs and dikes which are supplied with the rains. In this work it was determined the concentration of uranium in the water consumed by the rural and urban population living in the proximities of the Lagoa Real Uranium Province. The study comprehends 32 sampling spots spread throughout the region of interest. Samples were collected in January and July 2010, covering superficial, underground and public supply water from the region. The uranium concentrations were determined by an inductively coupled plasma mass spectrometer (ICP-MS). Preliminary results showed that the uranium concentrations in the water from the Lagoa Real Uranium Province varied from 0.064 ± 0.005 μg.L -1 to 90 ± 1,5 ±g.L -1 . It was observed that only two of them obtained values higher than the World Health Organization's recommended limit (2011) of 30 μg.L -1 for maximum uranium concentration in the water for human consumption. For a conclusive evaluation, the uranium concentrations results will be analyzed together with total alpha and beta concentrations determined elsewhere for the same samples. (author)

Hanford Site Development Plan

International Nuclear Information System (INIS)

Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J.; Yancey, E.F.

1990-01-01

The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs

Hanford Site Development Plan

Energy Technology Data Exchange (ETDEWEB)

Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J. (Westinghouse Hanford Co., Richland, WA (USA)); Yancey, E.F. (Pacific Northwest Lab., Richland, WA (USA))

1990-01-01

The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs.

Hanford defense waste studies

International Nuclear Information System (INIS)

Napier, B.A.; Zimmerman, M.G.; Soldat, J.K.

1981-01-01

PNL is assisting Rockwell Hanford Operations to prepare a programmatic environmental impact statement for the management of Hanford defense nuclear waste. The Ecological Sciences Department is leading the task of calculation of public radiation doses from a large matrix of potential routine and accidental releases of radionuclides to the environment

NHC's contribution to cleanup of the Hanford Site

International Nuclear Information System (INIS)

Chauve, H.D.

1998-01-01

The one billion dollars per year Project Hanford Management Contract (PHMC), managed by Fluor Daniel Hanford, calls for cleanup of the Hanford Site for the Department of Energy. Project Hanford comprises four major subprojects, each managed by a different major contractor. Numatec Hanford Corporation (NHC) is a fifth major subcontractor which provides energy and technology to each of the Hanford projects. NHC draws on the experience and capabilities of its parent companies, COGEMA and SGN, and relies on local support from its sister Company in Richland, COGEMA Engineering Corporation, to bring the best commercial practices and new technology to the Project

Organic Tank Safety Project: development of a method to measure the equilibrium water content of Hanford organic tank wastes and demonstration of method on actual waste

International Nuclear Information System (INIS)

Scheele, R.D.; Bredt, P.R.; Sell, R.L.

1996-09-01

Some of Hanford's underground waste storage tanks contain Organic- bearing high level wastes that are high priority safety issues because of potentially hazardous chemical reactions of organics with inorganic oxidants in these wastes such as nitrates and nitrites. To ensure continued safe storage of these wastes, Westinghouse Hanford Company has placed affected tanks on the Organic Watch List and manages them under special rules. Because water content has been identified as the most efficient agent for preventing a propagating reaction and is an integral part of the criteria developed to ensure continued safe storage of Hanford's organic-bearing radioactive tank wastes, as part of the Organic Tank Safety Program the Pacific Northwest National Laboratory developed and demonstrated a simple and easily implemented procedure to determine the equilibrium water content of these potentially reactive wastes exposed to the range of water vapor pressures that might be experienced during the wastes' future storage. This work focused on the equilibrium water content and did not investigate the various factors such as at sign ventilation, tank surface area, and waste porosity that control the rate that the waste would come into equilibrium, with either the average Hanford water partial pressure 5.5 torr or other possible water partial pressures

Uranium and radium in Finnsjoen - an experimental approach for calculation of transfer factors

International Nuclear Information System (INIS)

Evans, S.; Bergman, R.

1981-01-01

The radiological safety studies for underground disposal of HLW show that the future individual and collective doses to an important extent may originate from groundwater borne radium and uranium which reach the biosphere. Indications that the dispersion rates presently used give rise to overestimations of calculated doses justified an investigation for more realistic turnover rates of radium and uranium than those which now are in use. Within one of the sites selected for testing, the area around lake Finnsjoen, a small number of environmental samples were collected and analyzed with respect to radium and uranium and the new transfer coefficients between soil and lake water were derived. The dose rates obtained with the new transfer factors show a close agreement for radium and a slight increase for uranium compared with earlier calculations. (Auth.)

The siliceous-calcareous-argillaceous rock type uranium deposit in south subzone of Western Qinling

International Nuclear Information System (INIS)

Qian Farong; Zhou Dean; Ji Hongfang

1995-11-01

The siliceous-calcareous-argillaceous rock type uranium deposit in south subzone of western Qinling is an inland found type deposit with specific mineralization and good potentiality. The mineralization distributes along definite horizons and occurs in siliceous layer and lenses of siliceous-calcareous rocks. Orebody presents in forms of stratoid, lenticular and irregular veins and controlled by factorial structures. Ore is identified as massive and sandy and each characterized by various mineral compositions and element associations. The study shows that the mineralizing materials are mainly derived from ore-bearing strata. The metallogenic environment has characteristics of middle-low temperature and supergene The metallogenesis underwent three stages: (1) Sedimentation-diagenesis of the ore-bearing strata led to preliminary concentration of uranium; (2) Polytectonic activities accompanied by underground hydrothermal process resulted in the industrial concentration of uranium; and (3) Orebody reworked by oxidation-denudation and leaching, locally has taken place secondary concentration. The deposit in origin attributes to polygenesis dominated by underground hydrothermal metallogenesis. Main metallogenic epoch happens during the periods of Late Yanshan and Himalayan. According to the geological-tectonic conditions the further prospecting direction in study area is proposed. (3 refs., 5 figs., 9 tabs.)

Acoustic imaging of underground storage tank wastes: A feasibility study. Final report

International Nuclear Information System (INIS)

Turpening, R.; Zhu, Z.; Caravana, C.; Matarese, J.

1995-01-01

The objectives for this underground storage tank (UST) imaging investigation are: (1) to assess the feasibility of using acoustic methods in UST wastes, if shown to be feasible, develop and assess imaging strategies; (2) to assess the validity of using chemical simulants for the development of acoustic methods and equipment. This investigation examined the velocity of surrogates, both salt cake and sludge surrogates. In addition collected seismic cross well data in a real tank (114-TX) on the Hanford Reservation. Lastly, drawing on the knowledge of the simulants and the estimates of the velocities of the waste in tank 114-TX the authors generated a hypothetical model of waste in a tank and showed that non-linear travel time tomographic imaging would faithfully image that stratigraphy

Technology and the uranium industry

International Nuclear Information System (INIS)

Pool, T.C.

2000-01-01

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

Technology and the uranium industry

International Nuclear Information System (INIS)

Pool, T.C.

2002-01-01

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

Micronuclei in epithelial cells from sputum of uranium workers

International Nuclear Information System (INIS)

Loomis, D.P.; Shy, C.M.; Allen, J.W.; Saccomanno, G.

1990-01-01

The exfoliated-cell micronucleus (MN) assay was used to assess cytogenetic effects of exposure to radon progeny and cigarette smoke among 99 Colorado plateau uranium workers. Subjects were selected at random from employees in underground and open-pit uranium mines, ore mills, laboratories, and offices participating in a sputum screening program from 1964-88. The prevalence of cells with MN was determined by scoring one sputum specimen for each worker. Data obtained by interview were used to classify exposure to radon progeny and smoking at the time sputum specimens were taken. Underground miners were considered exposed to radon progeny, and others were considered unexposed. Neither radon progeny exposure nor cigarette smoking had any appreciable effect on the prevalence of cells with MN; crude prevalence ratios were 1.0 (95% CI 0.7-1.4) and 0.9 (95% CE 0.6-1.3), respectively. The effects of radon and smoking were not confounded by each other or by age, and there was no evidence of synergy between exposures. The findings appear to cast doubt on the epidemiological utility of a sputum-based MN assay for studies of other populations exposed to occupational or environmental lung carcinogens

U Plant Aggregate Area Management study technical baseline report

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1995-05-01

This document was prepared in support of an Aggregate Area Management Study of U Plant. It provides a technical baseline of the aggregate area and results from an environmental investigation that was undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC), which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. U Plant refers to the 221-U Process Canyon Building, a chemical separation facility constructed during World War II. It also includes the Uranium Oxide (UO 3 ) Plant constructed at the same time as 221-U as an adjunct to the original plutonium separation process but which, like 221-U, was converted for other missions. Waste sites are associated primarily with U Plant's 1952 through 1958 Uranium Metal Recovery Program mission and the U0 3 Plant's ongoing U0 3 mission. Waste sites include cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, a waste vault, and the lines and encasements that connect them. It also includes the U Pond and its feed ditches and an underground tank farm designed for high-level liquid wastes

Hanford Site Solid Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

1993-11-17

This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

Hanford Site Solid Waste Acceptance Criteria

International Nuclear Information System (INIS)

1993-01-01

This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities

Development of the Falea Polymetallic Uranium Project, Mali

International Nuclear Information System (INIS)

Ring, Bob; Freeman, Paul

2014-01-01

Falea project basics: • Project now owned by Denison Mines; • ANSTO Minerals working with owner and their consultant, DRA; • Located in south western Mali, West Africa, near the intersection of the Senegal and Guinea borders; • Established mining region (mainly gold); • Location on plateau favourable for underground operation; • Significant uranium, silver and copper mineralisation - different to other U deposits; • Excellent metallurical outcomes to date

Hanford Site baseline risk assessment methodology

International Nuclear Information System (INIS)

1993-03-01

This methodology has been developed to prepare human health and environmental evaluations of risk as part of the Comprehensive Environmental Response, Compensation, and Liability Act remedial investigations (RIs) and the Resource Conservation and Recovery Act facility investigations (FIs) performed at the Hanford Site pursuant to the Hanford Federal Facility Agreement and Consent Order referred to as the Tri-Party Agreement. Development of the methodology has been undertaken so that Hanford Site risk assessments are consistent with current regulations and guidance, while providing direction on flexible, ambiguous, or undefined aspects of the guidance. The methodology identifies Site-specific risk assessment considerations and integrates them with approaches for evaluating human and environmental risk that can be factored into the risk assessment program supporting the Hanford Site cleanup mission. Consequently, the methodology will enhance the preparation and review of individual risk assessments at the Hanford Site

Hanford Site 1998 Environmental Report

Energy Technology Data Exchange (ETDEWEB)

RL Dirkes; RW Hanf; TM Poston

1999-09-21

This Hanford Site environmental report is prepared annually to summarize environmental data and information, to describe environmental management performance, to demonstrate the status of compliance with environmental regulations, and to highlight major environmental programs and efforts. The report is written to meet requirements and guidelines of the U.S. Department of Energy (DOE) and to meet the needs of the public. This summary has been written with a minimum of technical terminology. Individual sections of the report are designed to: describe the Hanford Site and its mission; summarize the status of compliance with environmental regulations; describe the environmental programs at the Hanford Site; discuss the estimated radionuclide exposure to the public from 1998 Hanford Site activities; present the effluent monitoring, environmental surveillance, and groundwater protection and monitoring information; and discuss the activities to ensure quality.

Modeled atmospheric radon concentrations from uranium mines

Energy Technology Data Exchange (ETDEWEB)

Droppo, J.G.

1985-04-01

Uranium mining and milling operations result in the release of radon from numerous sources of various types and strengths. The US Environmental Protection Agency (EPA) under the Clean Air Act, is assessing the health impact of air emissions of radon from underground uranium mines. In this case, the radon emissions may impact workers and residents in the mine vicinity. To aid in this assessment, the EPA needs to know how mine releases can affect the radon concentrations at populated locations. To obtain this type of information, Pacific Northwest Laboratory used the radon emissions, release characteristics and local meterological conditions for a number of mines to model incremental radon concentrations. Long-term, average, incremental radon concentrations were computed based on the best available information on release rates, plume rise parameters, number and locations of vents, and local dispersion climatology. Calculations are made for a model mine, individual mines, and multiple mines. Our approach was to start with a general case and then consider specific cases for comparison. A model underground uranium mine was used to provide definition of the order of magnitude of typical impacts. Then computations were made for specific mines using the best mine-specific information available for each mine. These case study results are expressed as predicted incremental radon concentration contours plotted on maps with local population data from a previous study. Finally, the effect of possible overlap of radon releases from nearby mines was studied by calculating cumulative radon concentrations for multiple mines in a region with many mines. The dispersion model, modeling assumptions, data sources, computational procedures, and results are documented in this report. 7 refs., 27 figs., 18 tabs.

Modeled atmospheric radon concentrations from uranium mines

International Nuclear Information System (INIS)

Droppo, J.G.

1985-04-01

Uranium mining and milling operations result in the release of radon from numerous sources of various types and strengths. The US Environmental Protection Agency (EPA) under the Clean Air Act, is assessing the health impact of air emissions of radon from underground uranium mines. In this case, the radon emissions may impact workers and residents in the mine vicinity. To aid in this assessment, the EPA needs to know how mine releases can affect the radon concentrations at populated locations. To obtain this type of information, Pacific Northwest Laboratory used the radon emissions, release characteristics and local meterological conditions for a number of mines to model incremental radon concentrations. Long-term, average, incremental radon concentrations were computed based on the best available information on release rates, plume rise parameters, number and locations of vents, and local dispersion climatology. Calculations are made for a model mine, individual mines, and multiple mines. Our approach was to start with a general case and then consider specific cases for comparison. A model underground uranium mine was used to provide definition of the order of magnitude of typical impacts. Then computations were made for specific mines using the best mine-specific information available for each mine. These case study results are expressed as predicted incremental radon concentration contours plotted on maps with local population data from a previous study. Finally, the effect of possible overlap of radon releases from nearby mines was studied by calculating cumulative radon concentrations for multiple mines in a region with many mines. The dispersion model, modeling assumptions, data sources, computational procedures, and results are documented in this report. 7 refs., 27 figs., 18 tabs

Hanford Site ground-water surveillance for 1989

International Nuclear Information System (INIS)

Evans, J.C.; Bryce, R.W.; Bates, D.J.; Kemner, M.L.

1990-06-01

This annual report of ground-water surveillance activities provides discussions and listings of results for ground-water monitoring at the Hanford Site during 1989. The Pacific Northwest Laboratory (PNL) assesses the impacts of Hanford operations on the environment for the US Department of Energy (DOE). The impact Hanford operations has on ground water is evaluated through the Hanford Site Ground-Water Surveillance program. Five hundred and sixty-seven wells were sampled during 1989 for Hanford ground-water monitoring activities. This report contains a listing of analytical results for calendar year (CY) 1989 for species of importance as potential contaminants. 30 refs., 29 figs,. 4 tabs

Actinide analytical program for characterization of Hanford waste

International Nuclear Information System (INIS)

Johnson, S.J.; Winters, W.I.

1977-01-01

The objective of this program has been to develop faster, more accurate methods for the concentration and determination of actinides at their maximum permissible concentration (MPC) levels in a controlled zone. These analyses are needed to characterize various forms of Hanford high rad waste and to support characterization of products and effluents from new waste management processes. The most acceptable methods developed for the determination of 239 Pu, 238 Pu, 237 Np, 241 Am, and 243 Cm employ solvent extraction with the addition of tracer isotopes. Plutonium and neptunium are extracted from acidified waste solutions into Aliquat-336. Americium and curium are then extracted from the waste solution at the same acidity into dihexyl-N,N-diethylcarbamylmethylenephosphonate (DHDECMP). After back extraction into an aqueous matrix, these actinides are electrodeposited on steel disks for alpha energy analysis. Total uranium and total thorium are also isolated by solvent extraction and determined spectrophotometrically

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

International Nuclear Information System (INIS)

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

1995-09-01

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

Solution (in situ leach) mining of uranium: an overview

International Nuclear Information System (INIS)

Kuhaida, A.J. Jr.; Kelly, M.J.

1978-01-01

Increases in the demand for and price of uranium have made in-situ mining an attractive alternative to the open-pit and underground U mining methods. Up to 50% of the known ore-bearing sandstone in the western U.S. can be mined using the in-situ mining method. In-situ mining also offers a significant environmental advantage. Restoration of the contaminated groundwater is discussed

Conversion of Hanford salt cake to glass: laboratory studies

International Nuclear Information System (INIS)

Schulz, W.W.; Dressen, A.L.; Hobbick, C.W.; Kupfer, M.J.

1976-05-01

Approximately 140 million liters of solid salt cake (mainly NaNO 3 ), produced by evaporation of aged, alkaline high-level wastes, will be stored in underground tanks when the present Hanford Waste Management Program is completed in the early 1980's. These solid wastes can be converted to silicate-based glasses by melting them either at 1200 to 1300 0 C with appropriate amounts of sand and lime (soda-lime formulation) or at 1000 to 1100 0 C with appropriate amounts of Columbia River basalt and B 2 O 3 (basalt formulation). Both formulations yield dense, immobile glasses of low water leachability (10 -7 to 10 -6 g cm -2 day -1 ) suitable for terminal storage. The soda-lime formulation is presently preferred over the basalt formulation because it can accommodate more salt cake (50 wt percent versus 30 to 40 wt percent) while yielding a glass whose volume is 10 to 20 percent less than the volume of the salt cake in the melt charge

The Hanford Site Tank Waste Remediation System: An update

International Nuclear Information System (INIS)

Alumkal, W.T.; Babad, H.; Harmon, H.D.; Wodrich, D.D.

1994-01-01

The U.S. Department of Energy's Hanford Site, located in southeastern Washington State, has the most diverse and largest amount of highly radioactive waste in the United States. High-level radioactive waste has been stored in large underground tanks since 1944. Approximately 230,000 m 3 (61 Mgal) of caustic liquids, slurries, saltcakes, and sludges have 137 Cs accumulated in 177 tanks. In addition, significant amounts of 90 Sr and were removed from the tank waste, converted to salts, doubly encapsulated in metal containers., and stored in water basins. A Tank Waste Remediation System Program was established by the U.S. Department of Energy in 1991 to safely manage and immobilize these wastes in anticipation of permanent disposal of the high-level waste fraction in a geologic repository. Since 1991, progress has been made resolving waste tank safety issues, upgrading Tank Farm facilities and operations, and developing a new strategy for retrieving, treating, and immobilizing the waste for disposal

New exploration results of the Elkon uranium district deposits and prospects for their development

International Nuclear Information System (INIS)

Danilov, A.; Krasnykh, S.; Zhuravlev, V.; Kuzmin, E.; Tarkhanov, A.

2014-01-01

The Elkon Uranium District (EUD) is located in the Republic of Sakha (Yakutia) and is of strategic importance for the Russian uranium industry. It comprises more than 40% of the entire Russian uranium mineral resource and 4% of the world's uranium resources. Drilling and underground mining completed in 1961-1986 amounted to over 600,000 m and 52,500 m, respectively. The performed activities resulted in the discovery of the Yuzhnaya Zone and the Severnoe deposits. The Yuzhnaya Zone uranium resources (Measured + Indicated + Inferred) amounted to 257.8 kt (grade 0.146%). Uranium mineralisation contains 141 t of gold, 1784 t of silver and 41,5 kt of molybdenum. The Severnoe Inferred resources have been estimated at 58.6 kt (grade 0.149%). During the period of 2007-2011 over 100,000 m of drilling and associated activities was completed within the Yuzhnaya Zone and Severnoe deposits along with optimisation of ore mining and processing methods, and geological and economic revaluation of the deposits.

Canada's uranium future, based on forty years of development

International Nuclear Information System (INIS)

Aspin, N.; Dakers, R.G.

1982-09-01

Canada's role as a major supplier of uranium has matured through the cyclical markets of the past forty years. Present resource estimates would support a potential production capability by the late 1980s 50 per cent greater than the peak production of 12 200 tonnes uranium in 1959. New and improved exploration techniques are being developed as uranium deposits become more difficult to discover. Radiometric prospecting of glacial boulder fields and the use of improved airborne and ground geophysical methods have contributed significantly to recent discoveries in Saskatchewan. Advances have also been made in the use of airborne radiometric reconnaissance, borehole logging, emanometry (radon and helium gas) and multi-element regional geochemistry techniques. Higher productivity in uranium mining has been achieved through automation and mechanization, while improved ventilation systems in conjunction with underground environmental monitoring have contributed to worker health and safety. Improved efficiency is being achieved in all phases of ore processing. Factors contributing to the increased time required to develop uranium mines and mills from a minimum of three years in the 1950s to the ten years typical of today, are discussed. The ability of Canada's uranium refinery to manufacture ceramic grade UO 2 powder to consistent standards has been a major factor in the successful development of high density natural uranium fuel for the CANDU (CANada Deuterium Uranium) reactor. Over 400 000 fuel assemblies have been manufactured by three companies. The refinery is undertaking a major expansion of its capacity

HANFORD SCIENCE & TECHNOLOGY NEEDS STATEMENTS 2002

Energy Technology Data Exchange (ETDEWEB)

WIBLE, R.A.

2002-04-01

This document: (a) provides a comprehensive listing of the Hanford sites science and technology needs for fiscal year (FY) 2002; and (b) identifies partnering and commercialization opportunities within industry, other federal and state agencies, and the academic community. These needs were prepared by the Hanford projects (within the Project Hanford Management Contract, the Environmental Restoration Contract and the River Protection Project) and subsequently reviewed and endorsed by the Hanford Site Technology Coordination Group (STCG). The STCG reviews included participation of DOE-RL and DOE-ORP Management, site stakeholders, state and federal regulators, and Tribal Nations. These needs are reviewed and updated on an annual basis and given a broad distribution.

Pollution prevention opportunity assessments at Hanford

Energy Technology Data Exchange (ETDEWEB)

Betsch, M.D., Westinghouse Hanford

1996-06-26

The Pollution Prevention Opportunity Assessment (PPOA) is a pro- active way to look at a waste generating activity and identify opportunities to minimize wastes through a cost benefit analysis. Hanford`s PPOA process is based upon the graded approach developed by the Kansas City Plant. Hanford further streamlined the process while building in more flexibility for the individual users. One of the most challenging aspects for implementing the PPOA process at Hanford is one overall mission which is environmental restoration, Now that the facilities are no longer in production, each has a different non- routine activity making it difficult to quantify the inputs and outputs of the activity under consideration.

Hanford Sitewide Groundwater Remediation Strategy

International Nuclear Information System (INIS)

Knepp, A.J.; Isaacs, J.D.

1997-09-01

This document fulfills the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-13-81, to develop a concise statement of strategy that describe show the Hanford Site groundwater remediation will be accomplished. The strategy addresses objectives and goals, prioritization of activities, and technical approaches for groundwater cleanup. The strategy establishes that the overall goal of groundwater remediation on the Hanford Site is to restore groundwater to its beneficial uses in terms of protecting human health and the environment, and its use as a natural resource. The Hanford Future Site Uses Working Group established two categories for groundwater commensurate with various proposed landuses: (1) restricted use or access to groundwater in the Central Plateau and in a buffer zone surrounding it and (2) unrestricted use or access to groundwater for all other areas. In recognition of the Hanford Future Site Uses Working Group and public values, the strategy establishes that the sitewide approach to groundwater cleanup is to remediate the major plumes found in the reactor areas that enter the Columbia River and to contain the spread and reduce the mass of the major plumes found in the Central Plateau

Electrical resistivity tomography at the DOE Hanford site

International Nuclear Information System (INIS)

Narbutovskih, S.M.; Halter, T.D.; Sweeney, M.D.; Daily, W.; Ramirez, A.L.

1996-01-01

Recent work at the DOE Hanford site has established the potential of applying Electrical Resistivity Tomography (ERT) for early leak detection under hazardous waste storage facilities. Several studies have been concluded to test the capabilities and limitations of ERT for two different applications. First, field experiments have been conducted to determine the utility of ERT to detect and map leaks from underground storage tanks during waste removal processes. Second, the use of ERT for long term vadose zone monitoring has been tested under different field conditions of depth, installation design, acquisition mode/equipment and infiltration chemistry. This work involves transferring the technology from Lawrence Livermore National Laboratory (LLNL) to the Resource Conservation and Recovery Act (RCRA) program at the DOE Hanford Site. This paper covers field training studies relevant to the second application for long term vadose zone monitoring. Electrical resistivity tomography is a cross-borehole, imaging technique for mapping subsurface resistivity variations. Electrodes are placed at predetermined depths in an array of boreholes. Electrical current is introduced into one electrode pair located in one borehole while the resulting voltage change is detected between electrode pairs in other boreholes similar to a surface dipole-dipole array. These data are tomographically inverted to image temporal resistivity contrasts associated with an infiltration event. Thus a dynamic plume is spatially mapped as a function of time. As a long-term vadose zone monitoring method, different field conditions and performance requirements exist than those for short term tank leak detection. To test ERT under these conditions, two vertical electrode arrays were constructed to a depth of 160 feet with a linear surface array between boreholes

Hydrogeology of exogenic epigenic uranium deposits (sedimentary type) in Uzbekistan

International Nuclear Information System (INIS)

Irgashev, Yu.I.; Gavrilov, V.A.; Muslimov, B.A.

1996-01-01

Common problems of hydrogeology and geotechnology for uranium deposits (sedimentary type) in the Republic of Uzbekistan are discussed in the paper. Hydrogeology includes studies of texture of water-bearing horizons, occurrences of ore bodies in horizons, hydrochemical survey, hydrodynamics and engineering geology. Features of deposits workable by underground leaching are presented. Such terms as 'water-bearing horizon', 'efficiency', 'water-bearing bed' are explained accounting the results of 30 year investigations conducted during prospecting, designing and exploitation of uranium deposits. Stages of hydrogeological survey are listed and features of each of them are described. Importance of geotechnology for a deposit characterization is shown. (author). 6 refs.; 1 fig.; 1 tab

An Integrated Biological Control System At Hanford

International Nuclear Information System (INIS)

Johnson, A.R.; Caudill, J.G.; Giddings, R.F.; Rodriguez, J.M.; Roos, R.C.; Wilde, J.W.

2010-01-01

In 1999 an integrated biological control system was instituted at the U.S. Department of Energy's Hanford Site. Successes and changes to the program needed to be communicated to a large and diverse mix of organizations and individuals. Efforts at communication are directed toward the following: Hanford Contractors (Liquid or Tank Waste, Solid Waste, Environmental Restoration, Science and Technology, Site Infrastructure), General Hanford Employees, and Hanford Advisory Board (Native American Tribes, Environmental Groups, Local Citizens, Washington State and Oregon State regulatory agencies). Communication was done through direct interface meetings, individual communication, where appropriate, and broadly sharing program reports. The objectives of the communication efforts was to have the program well coordinated with Hanford contractors, and to have the program understood well enough that all stakeholders would have confidence in the work performed by the program to reduce or elimate spread of radioactive contamination by biotic vectors. Communication of successes and changes to an integrated biological control system instituted in 1999 at the Department of Energy's Hanford Site have required regular interfaces with not only a diverse group of Hanford contractors (i.e., those responsible for liquid or tank waste, solid wastes, environmental restoration, science and technology, and site infrastructure), and general Hanford employees, but also with a consortium of designated stake holders organized as the Hanford Advisory Board (i.e., Native American tribes, various environmental groups, local citizens, Washington state and Oregon regulatory agencies, etc.). Direct interface meetings, individual communication where appropriate, and transparency of the biological control program were the methods and outcome of this effort.

AN INTEGRATED BIOLOGICAL CONTROL SYSTEM AT HANFORD

Energy Technology Data Exchange (ETDEWEB)

JOHNSON AR; CAUDILL JG; GIDDINGS RF; RODRIGUEZ JM; ROOS RC; WILDE JW

2010-02-11

In 1999 an integrated biological control system was instituted at the U.S. Department of Energy's Hanford Site. Successes and changes to the program needed to be communicated to a large and diverse mix of organizations and individuals. Efforts at communication are directed toward the following: Hanford Contractors (Liquid or Tank Waste, Solid Waste, Environmental Restoration, Science and Technology, Site Infrastructure), General Hanford Employees, and Hanford Advisory Board (Native American Tribes, Environmental Groups, Local Citizens, Washington State and Oregon State regulatory agencies). Communication was done through direct interface meetings, individual communication, where appropriate, and broadly sharing program reports. The objectives of the communication efforts was to have the program well coordinated with Hanford contractors, and to have the program understood well enough that all stakeholders would have confidence in the work performed by the program to reduce or elimated spread of radioactive contamination by biotic vectors. Communication of successes and changes to an integrated biological control system instituted in 1999 at the Department of Energy's Hanford Site have required regular interfaces with not only a diverse group of Hanford contractors (i.e., those responsible for liquid or tank waste, solid wastes, environmental restoration, science and technology, and site infrastructure), and general Hanford employees, but also with a consortium of designated stake holders organized as the Hanford Advisory Board (i.e., Native American tribes, various environmental groups, local citizens, Washington state and Oregon regulatory agencies, etc.). Direct interface meetings, individual communication where appropriate, and transparency of the biological control program were the methods and outcome of this effort.

Hanford Waste Management Plan, 1987

International Nuclear Information System (INIS)

1987-01-01

The purpose of the Hanford Waste Management Plan (HWMP) is to provide an integrated plan for the safe storage, interim management, and disposal of existing waste sites and current and future waste streams at the Hanford Site. The emphasis of this plan is, however, on the disposal of Hanford Site waste. The plans presented in the HWMP are consistent with the preferred alternative which is based on consideration of comments received from the public and agencies on the draft Hanford Defense Waste Environmental Impact Statement (HDW-EIS). Low-level waste was not included in the draft HDW-EIS whereas it is included in this plan. The preferred alternative includes disposal of double-shell tank waste, retrievably stored and newly generated TRU waste, one pre-1970 TRU solid waste site near the Columbia River and encapsulated cesium and strontium waste

Hanford Site Environmental Report 1999

International Nuclear Information System (INIS)

Poston, TM; Hanf, RW; Dirkes, RL

2000-01-01

This Hanford Site environmental report is prepared annually to summarize environmental data and information, to describe environmental management performance, to demonstrate the status of compliance with environmental regulations, and to highlight major environmental programs and efforts. The report is written to meet requirements and guidelines of the U.S. Department of Energy (DOE) and to meet the needs of the public. This summary has been written with a minimum of technical terminology. Individual sections of the report are designed to: (1) describe the Hanford Site and its mission; (2) summarize the status of compliance with environmental regulations; (3) describe the environmental programs at the Hanford Site; (4) discuss the estimated radionuclide exposure to the public from 1999 Hanford Site activities; (5) present the effluent monitoring, environmental surveillance, groundwater protection and monitoring information; and (6) discuss the activities to ensure quality

Hanford Site Environmental Report 1999

Energy Technology Data Exchange (ETDEWEB)

TM Poston; RW Hanf; RL Dirkes

2000-09-28

This Hanford Site environmental report is prepared annually to summarize environmental data and information, to describe environmental management performance, to demonstrate the status of compliance with environmental regulations, and to highlight major environmental programs and efforts. The report is written to meet requirements and guidelines of the U.S. Department of Energy (DOE) and to meet the needs of the public. This summary has been written with a minimum of technical terminology. Individual sections of the report are designed to: (1) describe the Hanford Site and its mission; (2) summarize the status of compliance with environmental regulations; (3) describe the environmental programs at the Hanford Site; (4) discuss the estimated radionuclide exposure to the public from 1999 Hanford Site activities; (5) present the effluent monitoring, environmental surveillance, groundwater protection and monitoring information; and (6) discuss the activities to ensure quality.

Tackling the Challenge of Deep Vadose Zone Remediation at the Hanford Site

Science.gov (United States)

Morse, J. G.; Wellman, D. M.; Gephart, R.

2010-12-01

The Central Plateau of the Hanford Site in Washington State contains some 800 waste disposal sites where 1.7 trillion liters of contaminated water was once discharged into the subsurface. Most of these sites received liquids from the chemical reprocessing of spent uranium fuel to recover plutonium. In addition, 67 single shell tanks have leaked or are suspected to have leaked 3.8 million liters of high alkali and aluminate rich cesium-contaminated liquids into the sediment. Today, this inventory of subsurface contamination contains an estimated 550,000 curies of radioactivity and 150 million kg (165,000 tons) of metals and hazardous chemicals. Radionuclides range from mobile 99Tc to more immobilized 137Cs, 241Am, uranium, and plutonium. A significant fraction of these contaminants likely remain within the deep vadose zone. Plumes of groundwater containing tritium, nitrate, 129I and other contaminants have migrated through the vadose zone and now extend outward from the Central Plateau to the Columbia River. During most of Hanford Site history, subsurface studies focused on groundwater monitoring and characterization to support waste management decisions. Deep vadose zone studies were not a priority because waste practices relied upon that zone to buffer contaminant releases into the underlying aquifer. Remediation of the deep vadose zone is now central to Hanford Site cleanup because these sediments can provide an ongoing source of contamination to the aquifer and therefore to the Columbia River. However, characterization and remediation of the deep vadose zone pose some unique challenges. These include sediment thickness; contaminant depth; coupled geohydrologic, geochemical, and microbial processes controlling contaminant spread; limited availability and effectiveness of traditional characterization tools and cleanup remedies; and predicting contaminant behavior and remediation performance over long time periods and across molecular to field scales. The U

Chapter 2: uranium mines and mills

International Nuclear Information System (INIS)

O'Connell, W.J.

1983-03-01

This chapter will be included in a larger ASCE Committee Report. Uranium mining production is split between underground and open pit mines. Mills are sized to produce yellowcake concentrate from hundreds to thousands of tons of ore per day. Miner's health and safety, and environmental protection are key concerns in design. Standards are set by the US Mine Safety and Health Administration, the EPA, NRC, DOT, the states, and national standards organizations. International guidance and standards are extensive and based on mining experience in many nations

Feasibility study and concepts for use of compact process units to treat Hanford tank wastes

Energy Technology Data Exchange (ETDEWEB)

Collins, E.D.; Bond, W.D.; Campbell, D.O.; Harrington, F.E.; Malkemus, D.W.; Peishel, F.L.; Yarbro, O.O.

1994-06-01

A team of experienced radiochemical design engineers and chemists was assembled at Oak Ridge National Laboratory (ORNL) at the request of the Underground Storage Tank Integrated Demonstration (USTID) Program to evaluate the feasibility and perform a conceptual study of options for the use of compact processing units (CPUs), located at the Hanford, Washington, waste tank sites, to accomplish extensive pretreatment of the tank wastes using the clean-option concept. The scope of the ORNL study included an evaluation of the constraints of the various chemical process operations that may be employed and the constraints of necessary supporting operations. The latter include equipment maintenance and replacement, process control methods, product and by-product storage, and waste disposal.

Feasibility study and concepts for use of compact process units to treat Hanford tank wastes

International Nuclear Information System (INIS)

Collins, E.D.; Bond, W.D.; Campbell, D.O.; Harrington, F.E.; Malkemus, D.W.; Peishel, F.L.; Yarbro, O.O.

1994-06-01

A team of experienced radiochemical design engineers and chemists was assembled at Oak Ridge National Laboratory (ORNL) at the request of the Underground Storage Tank Integrated Demonstration (USTID) Program to evaluate the feasibility and perform a conceptual study of options for the use of compact processing units (CPUs), located at the Hanford, Washington, waste tank sites, to accomplish extensive pretreatment of the tank wastes using the clean-option concept. The scope of the ORNL study included an evaluation of the constraints of the various chemical process operations that may be employed and the constraints of necessary supporting operations. The latter include equipment maintenance and replacement, process control methods, product and by-product storage, and waste disposal

DOE underground storage tank waste remediation chemical processing hazards. Part I: Technology dictionary

International Nuclear Information System (INIS)

DeMuth, S.F.

1996-10-01

This document has been prepared to aid in the development of Regulating guidelines for the Privatization of Hanford underground storage tank waste remediation. The document has been prepared it two parts to facilitate their preparation. Part II is the primary focus of this effort in that it describes the technical basis for established and potential chemical processing hazards associated with Underground Storage Tank (UST) nuclear waste remediation across the DOE complex. The established hazards involve those at Sites for which Safety Analysis Reviews (SARs) have already been prepared. Potential hazards are those involving technologies currently being developed for future applications. Part I of this document outlines the scope of Part II by briefly describing the established and potential technologies. In addition to providing the scope, Part I can be used as a technical introduction and bibliography for Regulatory personnel new to the UST waste remediation, and in particular Privatization effort. Part II of this document is not intended to provide examples of a SAR Hazards Analysis, but rather provide an intelligence gathering source for Regulatory personnel who must eventually evaluate the Privatization SAR Hazards Analysis

Fact sheet on uranium exploration, mining production and environmental protection

International Nuclear Information System (INIS)

2006-01-01

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

Probabilistic safety assessment for Hanford high-level waste tank 241-SY-101

Energy Technology Data Exchange (ETDEWEB)

MacFarlane, D.R.; Bott, T.F.; Brown, L.F.; Stack, D.W. [Los Alamos National Lab., NM (United States); Kindinger, J.; Deremer, R.K.; Medhekar, S.R.; Mikschl, T.J. [PLG, Inc., Newport Beach, CA (United States)

1994-05-01

Los Alamos National Laboratory (Los Alamos) is performing a comprehensive probabilistic safety assessment (PSA), which will include consideration of external events for the 18 tank farms at the Hanford Site. This effort is sponsored by the Department of Energy (DOE/EM, EM-36). Even though the methodology described herein will be applied to the entire tank farm, this report focuses only on the risk from the weapons-production wastes stored in tank number 241-SY-101, commonly known as Tank 101-SY, as configured in December 1992. This tank, which periodically releases ({open_quotes}burps{close_quotes}) a gaseous mixture of hydrogen, nitrous oxide, ammonia, and nitrogen, was analyzed first because of public safety concerns associated with the potential for release of radioactive tank contents should this gas mixture be ignited during one of the burps. In an effort to mitigate the burping phenomenon, an experiment is being conducted in which a large pump has been inserted into the tank to determine if pump-induced circulation of the tank contents will promote a slow, controlled release of the gases. At the Hanford Site there are 177 underground tanks in 18 separate tank farms containing accumulated liquid/sludge/salt cake radioactive wastes from 50 yr of weapons materials production activities. The total waste volume is about 60 million gal., which contains approximately 120 million Ci of radioactivity.

Probabilistic safety assessment for Hanford high-level waste tank 241-SY-101

International Nuclear Information System (INIS)

MacFarlane, D.R.; Bott, T.F.; Brown, L.F.; Stack, D.W.; Kindinger, J.; Deremer, R.K.; Medhekar, S.R.; Mikschl, T.J.

1994-05-01

Los Alamos National Laboratory (Los Alamos) is performing a comprehensive probabilistic safety assessment (PSA), which will include consideration of external events for the 18 tank farms at the Hanford Site. This effort is sponsored by the Department of Energy (DOE/EM, EM-36). Even though the methodology described herein will be applied to the entire tank farm, this report focuses only on the risk from the weapons-production wastes stored in tank number 241-SY-101, commonly known as Tank 101-SY, as configured in December 1992. This tank, which periodically releases (open-quotes burpsclose quotes) a gaseous mixture of hydrogen, nitrous oxide, ammonia, and nitrogen, was analyzed first because of public safety concerns associated with the potential for release of radioactive tank contents should this gas mixture be ignited during one of the burps. In an effort to mitigate the burping phenomenon, an experiment is being conducted in which a large pump has been inserted into the tank to determine if pump-induced circulation of the tank contents will promote a slow, controlled release of the gases. At the Hanford Site there are 177 underground tanks in 18 separate tank farms containing accumulated liquid/sludge/salt cake radioactive wastes from 50 yr of weapons materials production activities. The total waste volume is about 60 million gal., which contains approximately 120 million Ci of radioactivity

History of Hanford Site Defense Production (Brief)

Energy Technology Data Exchange (ETDEWEB)

GERBER, M S

2001-02-01

This paper acquaints the audience with the history of the Hanford Site, America's first full-scale defense plutonium production site. The paper includes the founding and basic operating history of the Hanford Site, including World War II construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), a brief production spurt from 1984-86, the end of the Cold War, and the beginning of the waste cleanup mission. The paper also delineates historical waste practices and policies as they changed over the years at the Hanford Site, past efforts to chemically treat, ''fractionate,'' and/or immobilize Hanford's wastes, and resulting major waste legacies that remain today. This paper presents original, primary-source research into the waste history of the Hanford Site. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history.

History of Hanford Site Defense Production (Brief)

International Nuclear Information System (INIS)

GERBER, M.S.

2001-01-01

This paper acquaints the audience with the history of the Hanford Site, America's first full-scale defense plutonium production site. The paper includes the founding and basic operating history of the Hanford Site, including World War II construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), a brief production spurt from 1984-86, the end of the Cold War, and the beginning of the waste cleanup mission. The paper also delineates historical waste practices and policies as they changed over the years at the Hanford Site, past efforts to chemically treat, ''fractionate,'' and/or immobilize Hanford's wastes, and resulting major waste legacies that remain today. This paper presents original, primary-source research into the waste history of the Hanford Site. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history

Vascular Plants of the Hanford Site

International Nuclear Information System (INIS)

Sackschewsky, Michael R.; Downs, Janelle L.

2001-01-01

This report provides an updated listing of the vascular plants present on and near the U.S. Department of Energy Hanford Site. This document is an update of a listing of plants prepared by Sackschewdky et al. in 1992. Since that time there has been a significant increase in the botanical knowledge of the Hanford Site. The present listing is based on an examination of herbarium collections held at PNNL, at WSU-Tri Cities, WSU-Pullman, Brigham Young University, and The University of Washington, and on examination of ecological literature derived from the Hanford and Benton county areas over the last 100 years. Based on the most recent analysis, there are approximately 725 different plant species that have been documented on or around the Hanford Site. This represents an approximate 20% increase in the number of species reported within Sackschewsky et al. (1992). This listing directly supports DOE and contractor efforts to assess the potential impacts of Hanford Site operations

Supplementary recovery of uranium by in-situ leaching at the Brugeaud deposit (Limousin, France)

International Nuclear Information System (INIS)

Lyaudet, G.

1980-01-01

The actual mining operations at the Brugeaud Deposit (West Brugeaud and East Brugeaud) were followed by supplementary recoveries of uranium by means of in-situ leaching. There were a number of factors which favoured consideration of these operations: the amounts of uranium present at the edge of the stoped areas; the underground mining infrastructure, which did not require supplementary operations for the recovery of solutions; the nature of the rock, which presented a dense network of fractures and micro-fractures conducive to impregnation by the acid solutions; and the immediate proximity of a concentration plant. The amount of uranium recovered by in-situ leaching is close to 200 t. This production is approximately nine per cent of all the uranium extracted from the deposit. The cost of the metal obtained in this way was always less than FF 100 (FF of 1978) per kilogram of uranium. (author)

Facility effluent monitoring plan for the uranium trioxide facility

International Nuclear Information System (INIS)

Thompson, R.J.; Sontag, S.

1991-11-01

A facility effluent monitoring plant is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The UO 3 Plant is located in the south-central portion of the 200 West Area of the Hanford Site. The plant consists of two primary processing buildings and several ancillary facilities. The purpose of the UO 3 Plant is to receive uranyl nitrate hexahydrate (UNH) from the Plutonium-Uranium Extraction (PUREX) Plant, concentrate it, convert the UNH to uranium trioxide (UO 3 ) powder by calcination and package it for offsite shipment. The UO 3 Plant has been placed in a standby mode. There are two liquid discharges, and three gaseous exhaust stacks, and seven building exhausters that are active during standby conditions

Hanford Patrol Academy demolition sites closure plan

Energy Technology Data Exchange (ETDEWEB)

1993-09-30

The Hanford Site is owned by the U.S. Government and operated by the U.S. Department of Energy, Richland Operations Office. Westinghouse Hanford Company is a major contractor to the U.S. Department of Energy, Richland Operations Office and serves as co-operator of the Hanford Patrol Academy Demolition Sites, the unit addressed in this paper. This document consists of a Hanford Facility Dangerous Waste Part A Permit Application, Form 3 (Revision 4), and a closure plan for the site. An explanation of the Part A Form 3 submitted with this closure plan is provided at the beginning of the Part A section. This Hanford Patrol Academy Demolition Sites Closure Plan submittal contains information current as of December 15, 1994.

Uranium migration in a podzol. The role of colloids in the non-saturated zone and the phreatic water: application to the Landes de Gascogne area

International Nuclear Information System (INIS)

Crancon, P.

2001-01-01

The non-saturated zone of a soil represents the interface between the atmosphere and the phreatic water. The confinement efficiency of the non-saturated zone above the phreatic water depends on the fastness of water transfers and on the type of pollutant transport mechanisms. Uranium (VI) can combine with humid acids to form very stable complexes. The aggregates of the absorbing complex are highly sensible to the variations of the ionic force of the environment. This sensitiveness can be at the origin of a strong remobilization of the colloid humic compounds of the soil, and of their migration towards the underground water. In this situation, the uranium complexed by humic compounds can rapidly migrate in the soil. The comparative reactive transport of the total uranium and its isotopes has been studied in a site, the Landes de Gascogne podzol (SW France), where metallic uranium has been sprinkled on the surface of the soil. The field study has been completed with an experimental column transport study using uranium isotopes tracer techniques. The field study shows that most of uranium is trapped in the very first cm of the soil. However, anomalous high uranium concentrations are observed in underground waters, more than 2 km away from the contaminated areas. This demonstrates that a fast and long distance transport process exists for uranium in the unsaturated zone. In the sandy soil of the study area, natural argillo-humic colloids migrate with the velocity of water but can be delayed when the ionic force of the underground waters increases. It is shown that uranium is strongly linked with the thin grain size fraction ( 233 U allows to discriminate between the uranium transported through the sand in a non-reactive way, and the uranium desorbed from the argillo-humic aggregates and the sand grain coatings. A fast reduction of the ionic force of the environment during the tests shows an important remobilization of uranium from the soil. When the complex relations

Risks associated with mining and processing of uranium

International Nuclear Information System (INIS)

Archer, V.E.

1976-01-01

Mortality from all causes was determined for groups of white and Indian underground uranium miners, and for a small group of uranium mill workers. Analysis was by a life table method. A significant excess of respiratory cancer was found among both white and Indian miners. A significant excess of nonmalignant respiratory disease was found among whites. It was attributed primarily to diffuse parenchymal damage by radiation; it approaches respiratory cancer in importance as a cause of death among whites. A significant excess of malignant disease of the lymphatic and hematopoietic tissue was found among uranium mill workers. This was attributed primarily to irradiation of lymph nodes by thorium-230. Exposure-response curves for nonsmoking uranium miners are linear for both respiratory cancer and ''other respiratory disease.'' Cigarette smoking elevates and distorts that curve. Light cigarette smokers appear to be most vulnerable to lung parenchymal damage by the radiation. The predominant histological type of cancer among nonsmokers, white smokers and Indians is small cell undifferentiated. Accidental deaths are high among inexperienced miners, and even among experienced miners it is about 3 times what is expected

Glances on uranium. Tome 2. Exploration, production

International Nuclear Information System (INIS)

Valsardieu, C.

1997-01-01

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

List of currently classified documents relative to Hanford Production Facilities Operations originated on the Hanford Site between 1961 and 1972

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

The United States Department of Energy (DOE) has declared that all Hanford plutonium production- and operations-related information generated between 1944 and 1972 is declassified. Any documents found and deemed useful for meeting Hanford Environmental Dose Reconstruction (HEDR) objectives may be declassified with or without deletions in accordance with DOE guidance by Authorized Derivative Declassifiers. The September 1992, letter report, Declassifications Requested by the Technical Steering Panel of Hanford Documents Produced 1944--1960, (PNWD-2024 HEDR UC-707), provides an important milestone toward achieving a complete listing of documents that may be useful to the HEDR Project. The attached listing of approximately 7,000 currently classified Hanford-originated documents relative to Hanford Production Facilities Operations between 1961 and 1972 fulfills TSP Directive 89-3. This list does not include such titles as the Irradiation Processing Department, Chemical Processing Department, and Hanford Laboratory Operations monthly reports generated after 1960 which have been previously declassified with minor deletions and made publicly available. Also Kaiser Engineers Hanford (KEH) Document Control determined that no KEH documents generated between January 1, 1961 and December 31, 1972 are currently classified. Titles which address work for others have not been included because Hanford Site contractors currently having custodial responsibility for these documents do not have the authority to determine whether other than their own staff have on file an appropriate need-to-know. Furthermore, these documents do not normally contain information relative to Hanford Site operations.

Idaho Chemical Processing Plant and Plutonium-Uranium Extraction Plant phaseout/deactivation study

International Nuclear Information System (INIS)

Patterson, M.W.; Thompson, R.J.

1994-01-01

The decision to cease all US Department of Energy (DOE) reprocessing of nuclear fuels was made on April 28, 1992. This study provides insight into and a comparison of the management, technical, compliance, and safety strategies for deactivating the Idaho Chemical Processing Plant (ICPP) at Westinghouse Idaho Nuclear Company (WINCO) and the Westinghouse Hanford Company (WHC) Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this study is to ensure that lessons-learned and future plans are coordinated between the two facilities

HANFORD SITE RIVER CORRIDOR CLEANUP

International Nuclear Information System (INIS)

BAZZELL, K.D.

2006-01-01

In 2005, the US Department of Energy (DOE) launched the third generation of closure contracts, including the River Corridor Closure (RCC) Contract at Hanford. Over the past decade, significant progress has been made on cleaning up the river shore that bordes Hanford. However, the most important cleanup challenges lie ahead. In March 2005, DOE awarded the Hanford River Corridor Closure Contract to Washington Closure Hanford (WCH), a limited liability company owned by Washington Group International, Bechtel National and CH2M HILL. It is a single-purpose company whose goal is to safely and efficiently accelerate cleanup in the 544 km 2 Hanford river corridor and reduce or eliminate future obligations to DOE for maintaining long-term stewardship over the site. The RCC Contract is a cost-plus-incentive-fee closure contract, which incentivizes the contractor to reduce cost and accelerate the schedule. At $1.9 billion and seven years, WCH has accelerated cleaning up Hanford's river corridor significantly compared to the $3.2 billion and 10 years originally estimated by the US Army Corps of Engineers. Predictable funding is one of the key features of the new contract, with funding set by contract at $183 million in fiscal year (FY) 2006 and peaking at $387 million in FY2012. Another feature of the contract allows for Washington Closure to perform up to 40% of the value of the contract and subcontract the balance. One of the major challenges in the next few years will be to identify and qualify sufficient subcontractors to meet the goal