Relevant bibliographies by topics / Radioactive waste disposal in rivers

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  2. Dissertations / Theses
  3. Books
  4. Book chapters
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Academic literature on the topic 'Radioactive waste disposal in rivers'

Author: Grafiati
Published: 4 June 2021
Last updated: 12 February 2022

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Journal articles on the topic "Radioactive waste disposal in rivers"

1

Devgun, J. S. "Suitability of unconsolidated sediments for hosting low-level radioactive waste disposal facilities." Canadian Journal of Civil Engineering 16, no. 4 (August 1, 1989): 560–67. http://dx.doi.org/10.1139/l89-086.

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Among the unconsolidated sediments, sand deposits are considered a rather unconventional geologic host medium for siting radioactive waste repositories, the clays being the preferred choice. A closer examination of the various geologic media, however, shows that in each case there are advantages and disadvantages. The key to safe and cost-effective disposal is to match the engineered design of the facility to the site's characteristics as well as the nature of the waste to be disposed of. In humid climates, free-draining sediments such as sand can provide the advantage of eliminating concern related to the “bathtub effect.”At Chalk River Nuclear Laboratories (CRNL), a sand dune has been proposed for hosting a low-level radioactive waste disposal facility. This paper discusses the suitability of unconsolidated sediments for radioactive waste disposal in general; in particular, it provides the rationalization for the selection of a sand dune as the host site at CRNL. Key words: radioactive waste, disposal facilities, unconsolidated sediments, site suitability, trench cover materials, sreismicity, soil liquefaction.
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Ewing, R. C., and W. Lutze. "Materials Science of Radioactive Waste Forms." MRS Bulletin 19, no. 12 (December 1994): 16–19. http://dx.doi.org/10.1557/s0883769400048636.

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The materials science of radioactive waste forms and containment materials has long been a subject of interest to the Materials Research Society. One of the earliest (and continuing) MRS symposia, the Scientific Basis for Nuclear Waste Management, has been held 18 times since 1978. This symposium rotates abroad every third year: Berlin in 1982, Stockholm in 1985, Berlin in 1988, Strasbourg in 1991, and Kyoto this past October. Nearly 170 papers were presented at the Kyoto meeting.Materials science issues for nuclear waste disposal are unique in their scale and consequences. The wastes include an extremely wide variety of materials: spent nuclear fuel from commercial and research reactors; high-level liquid waste produced at West Valley, New York, during the reprocessing of commercial spent nuclear fuel; high-level waste (HLW) generated by the nuclear weapons program; nearly pure plutonium from the dismantling of nuclear weapons; highly enriched uranium from weapons; low-level, medium-level, and mixed waste from laboratories and medical facilities; and, finally, mill tailings from uranium mines and the residues from chemical processing, such as the radium-bearing filtrate presently in storage at Fernald, Ohio, and Niagara Falls, New York. Some material can be simply stabilized and monitored in situ, as is done for most uranium mill tailings and residues, but other materials require retrieval, processing, immobilization, and permanent disposal. The volumes of material that will require handling, immobilization, and disposal are enormous. In the United States, much of the weapons program waste is stored in tanks at Hanford, Washington and Savannah River, South Carolina.
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Hutchinson, Harry. "More Weight on the Job." Mechanical Engineering 132, no. 07 (July 1, 2010): 36–38. http://dx.doi.org/10.1115/1.2010-jul-4.

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This article discusses that new methods and heavier equipment are expected to hasten the nuclear waste transfer at the Hanford Site’s tank farms. The site includes old processing plants, groundwater that exceeds safe levels of radioactivity, and high-level radioactive waste held in 149 aging tanks—some more than 60 years old—that lie underground just 10 miles from the Columbia River. The objective is to remove the highly radioactive waste from the old tanks, which have a single shell construction, and transfer it to 28 newer, more-secure double-shell tanks nearby, where the waste will safely reside until it can be treated in facilities now under construction. There are approximately 53,000,000 gallons of nuclear and chemical waste stored in the tanks at the Hanford Site. Bechtel National Inc., another of the prime contractors for Office of River Protection, is building a treatment plant that will process the wastes being stored in the underground tanks into a stable glass form for permanent disposal in a federal geological repository.
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Vasilyev, A. V., G. P. Malinovsky, A. D. Onishchenko, and I. V. Yarmoshenko. "RESULTS OF RADON INSPECTION OF SETTLEMENTS COMPROMISED DUE TO DISPOSAL OF RADIOACTIVE WASTE INTO THE TECHA RIVER." Hygiene and sanitation 96, no. 5 (March 27, 2019): 418–21. http://dx.doi.org/10.18821/0016-9900-2017-96-5-418-421.

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During past decades, specialists perform an epidemiological observation of the population exposed to the impact of radioactive discharges into the Techa River. The Techa River cohort studies have identified excess cases of leukemia and solid cancers associated with radiation exposure. At the same time natural sources of radiation, such as radon and its decay products, known to be significant human radiation exposure factor, are not sufficiently studied on this territory. The purpose of the study is to assess the mean value and the distribution indices of radon concentration in 14 settlements affected by radioactive contamination. Radon inspection in settlements located on the Techa River (Chelyabinsk and Kurgan regions) was executed. The measurements were performed in 511 dwellings. For radon inspection there were applied detectors based on LR-115 Kodak Track. The analysis shows the sample both to be representative and allow to estimate radon exposure for inhabitants. The average radon concentration in dwellings is 150 Bq/m3, which results in an annual effective dose of 11 mSv. The estimated number of dwellings with radon concentrations above ECC radon action level 200 Bq/m3 is 19. The factors affecting indoor radon accumulation were established. The radiation dose due to the inhalation of radon, accumulated over a long period of time, seems to be generally comparable to doses associated with the radioactive discharges into the Techa River during the 1949-1956.
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Le, V. T., N. V. Beamer, and L. P. Buckley. "Experience with radioactive waste incineration at chalk river nuclear laboratories." Waste Management 9, no. 2 (January 1989): 67–72. http://dx.doi.org/10.1016/0956-053x(89)90392-9.

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6

Dewanto, Pandu, Setyo Sarwanto Moersidik, and Sucipta Sucipta. "Radionuclide Release Prediction in Water and Soil at Demonstration Plant of Near Surface Disposal for Radioactive Waste." Indonesian Journal of Physics and Nuclear Applications 1, no. 2 (June 30, 2016): 116. http://dx.doi.org/10.24246/ijpna.v1i2.116-122.

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Near Surface Disposal (NSD) for Radioactive Waste that should be developed due to increment of the low level radioactive waste, need to be analyzed and evaluated related to the radiological impact of the environment. A research method applied is done by modeling the distribution of radionuclide releases process. Analysis related with the releases of radionuclide in water and soil is using PRESTO (Prediction of Radiological Effects Due to Shallow Trench Operations). The application scenarios selected in this safety assessment is the migrations of Co-60 and Cs-137 scenario through the shallow groundwater flow pattern in the NSD site. The SigmaPlot software is also used to determine the concentration equation in well water and river water. The final results showed the concentration of radionuclide in wells and streams below the provision. Radionuclide activity concentrations in well ranged from 10<sup>-10</sup>Bq/m<sup>3</sup> to 10<sup>0</sup>Bq/m<sup>3</sup> and in the river ranged from 10<sup>-15</sup>Bq / m<sup>3</sup> to 10<sup>-1</sup>Bq / m3. The impact of radioactive waste of radionuclide Co-60 and Cs-137 will decrease to the background radiation level at a distance less than 10m and penetrate into the saturated layer up to 4m. In this study, an equation have been obtained that can predict radionuclide concentration patterns based on the distance and the depth of the ground surface against to the facility operation time.
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Valstar, J. R., and N. Goorden. "Far-field transport modelling for a repository in the Boom Clay in the Netherlands." Netherlands Journal of Geosciences 95, no. 3 (May 25, 2016): 337–47. http://dx.doi.org/10.1017/njg.2016.13.

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AbstractA groundwater model was set up to study far-field transport for the potential of a radioactive waste repository the Boom Clay in the Netherlands. The existing national groundwater model, the Netherlands Hydrological Instrument, was extended in the vertical direction to include geological formation up to and beyond the Boom Clay. As the amount of hydrogeological data in the deeper subsurface is limited, simplifications in the model schematisation were necessary. Moreover, nationwide data about the tops and bottoms of many of the deeper geological formations and their members are lacking and required interpolation. Finally, values for hydrogeological parameters, such as porosity and hydraulic conductivity, are also lacking for the deeper formations. These values were estimated using relationships with depth and lithology. Moreover, no quantitative data about heterogeneity within the deeper geological formations or its members were available.In the Dutch research programme on the geological disposal of radioactive waste (OPERA), the post-closure safety of a generic repository is assessed in either Boom Clay or rock salt. Disposal of Dutch radioactive waste is not foreseen in the next decades and a choice of host rock has not been made. In the early, conceptual phase of the radioactive waste disposal process in the Netherlands no potential repository locations were selected and a groundwater flow model for the entire Netherlands was build. As a starting point a geological disposal facility is assumed to be present at a depth of at least 500 m within a Boom Clay formation of 100 m in order to be able to make an assessment of post-closure safety with this geological formation in a disposal concept. With these assumptions, a general idea of potential flow patterns has been obtained and broken down into pathline trajectories. These trajectories were calculated to achieve input for the potential transport of radioactive isotopes (radionuclides) from this waste in the Netherlands after the closure of a disposal facility in Boom Clay.The groundwater flow patterns in the deeper subsurface strongly resemble the larger scale flow patterns in the shallow subsurface, with flow from infiltration areas in the east and the south of the Netherlands towards to seepage areas of the polders in the west and the northern part of the country or towards the river valleys of the Rhine and IJssel. Groundwater flow velocities, however, are much lower in the deeper part of the model and consequently travel times are much larger. The conservative travel times from the pathlines range from a few 1000 years to more than 10,000,000 years depending on the location for the repository. Longer travel times are obtained for locations with a downward groundwater flow in the Boom Clay.Because of the simplifications in the model schematisation and the uncertainty in the model parameters, the present results should only be considered as a first indication. Moreover, the model could not be validated due to a lack of validation data. However, the insight gained with the model may help to design a data collection strategy for dedicated model validation, such as measuring the hydraulic gradient over the Boom Clay to validate downward flow in the Boom Clay to obtain the necessary data for a post-closure safety assessment.
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Konshina, Lydia G. "RETROSPECTIVE ANALYSIS OF CANCER MORTALITY RATE IN THE POPULATION EXPOSED TO ACCIDENTS AT MAYAK PRODUCTION." Hygiene and sanitation 97, no. 2 (February 15, 2018): 138–43. http://dx.doi.org/10.18821/0016-9900-2017-96-6-138-143.

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Radioactive pollution of the territory of the Chelyabinsk district is significantly determined by accidents happened at the largest nuclear industry enterprise - Mayak Production Association related to the waste disposal of radioactive fluids into the Techa River due to the accident of 1957 and the spread of the dusty radioactive clay from the Karachay lake with the wind. We executed a selective retrospective epidemiologic study of the mortality rate in the population residing in five districts (Argayashsky, Kaslinsky, Krasnoarmeysky, Kunashaksky, Sosnovsky), and two cities - Kasli and Kyshtym (all of them are located in the Chelyabinsk region), exposed to atmospheric and liquid radioactive wastes. In the administrative districts, those were inhabited only in settlements located within the zone of the intensive radioactive pollution were studied. The source of information about the cases of death was the official death records provided by the Office of Vital Records of the Chelyabinsk region for the time period of 1947-1996. As a whole about 135 thousand death records were considered. The gain in the cancer mortality rate was noted for both males and females in cities of Kyshtym and Kasli. In 1950-60s the highest mortality rate indices were typical for the population of Kasli, and in 1960-70-s - for Kyshtym. A two-fold gain in the cancer mortality rate was noted in districts of Chelyabinsk region suffered from the accidents. Practically the permanent excess of estimated benchmarks was noted in Argayashsky and Kaslinski districts and during some periods in Krasnoarmeisky and Sosnovsky districts. In the city of Kasli, Kaslinsky, Argayashsky and Krasnoarmeisky districts the rise in the mortality rate was noted already from the beginning of 1950s and was twice or more as much. The increase in the cancer mortality rate among the population of both genders is sufficiently determined by the growth of age coefficients (in ages of 60-69 and 70 years and older). The coefficient of the cancer mortality rate decreases progressively to the distance from Mayak Production Association.
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Wyatt, Douglas E., Frank H. Syms, and Randolph Cumbest. "High-resolution stratigraphic modeling of the vadose zone at the Savannah River Site low-level radioactive waste trenches disposal facility." Environmental Geosciences 12, no. 4 (December 2005): 267–77. http://dx.doi.org/10.1306/eg.02090504047.

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Yin, Wenjie, Litang Hu, Shin-Chan Han, Menglin Zhang, and Yanguo Teng. "Reconstructing Terrestrial Water Storage Variations from 1980 to 2015 in the Beishan Area of China." Geofluids 2019 (January 14, 2019): 1–13. http://dx.doi.org/10.1155/2019/3874742.

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Terrestrial water storage (TWS) is a key element in the global and continental water cycle. Since 2002, the Gravity Recovery and Climate Experiment (GRACE) has provided a highly valuable dataset, which allows the study of TWS over larger river basins worldwide. However, the lifetime of GRACE is too short to demonstrate long-term variability in TWS. In the Beishan area of northwestern China, which is selected as the most prospective site for high-level radioactive waste (HLRW) disposal, the assessment of long-term TWS changes is crucial to understand disposal safety. Monthly and annual TWS changes during the past 35 years are reconstructed using GRACE data, other remote sensing products, and the water balance method. Hydrological flux outputs from multisource remote sensing products are analyzed and compared to select appropriate data sources. The results show that a decreasing trend is found for GRACE-filtered and Center for Space Research (CSR) mascon solutions from 2003 to 2015, with slopes of −2.30 ± 0.52 and −1.52 ± 0.24 mm/year, respectively. TWS variations independently computed from the water balance method also show a similar decreasing trend with the GRACE observations, with a slope of −0.94 mm/year over the same period. Overall, the TWS anomalies in the Beishan area change seasonally within 10 mm and have been decreasing since 1980, keeping a desirable dry condition as a HLRW disposal site.
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Dissertations / Theses on the topic "Radioactive waste disposal in rivers"

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Norris, James 1953. "Preliminary hydraulic characterization of a fractured schist aquifer at the Koongarra uranium deposit, Northern Territory, Australia." Thesis, The University of Arizona, 1989. http://hdl.handle.net/10150/291720.

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The Koongarra uranium deposit is hosted by quartz-chlorite schists. A conceptual model for the hydrogeology of the deposit is proposed on the basis of lithologic criteria and limited hydraulic testing. Water-level and aquifer-test data are presented that indicate the deposit lies within a partially confined, heterogeneous, anisotropic fractured-rock aquifer. The aquifer is dynamic with annual, diurnal, and semidiurnal water-level fluctuations. The results of aquifer tests indicate a high degree of connectivity in the aquifer. Fracture-dominated flow is observed in some tests, but the overall aquifer response appears to be that of an equivalent porous medium. A homogeneous, anisotropic model is used to estimate the transmissivity tensor for subregions of the aquifer. Anisotropy is well-developed with north- to east-northeast-oriented principal transmissivities. Northeast directions represent large-scale drawdown patterns and are subparallel to bedrock structure and the Koongarra fault. Northerly directions are localized and may reflect a less extensive fracture fabric or a flexure in the bedrock foliation.
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Trone, Paul M. "Textural and mineralogical characteristics of altered Grande Ronde basalt, northeastern Oregon : a natural analog for a nuclear waste repository in basalt." PDXScholar, 1987. https://pdxscholar.library.pdx.edu/open_access_etds/3824.

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Altered flows that are low-MgO chemical types of the Grande Ronde Basalt crop out in the steep walls of the Grande Ronde River canyon near Troy, Wallowa County, Oregon. The alteration effects in these flows are being investigated as a natural analog system to a high level nuclear waste repository in basalt. The flows within the study are referred to as the analog flow, in which the alteration effects are the strongest, and the superjacent flow. The analog flow crops out at Grande Ronde River level and a roadcut-outcrop is developed in the flow-top breccia of this flow. The two flows have been divided into flow zones based on intraflow structures observed in the field and primary igneous textures observed in thin section. These zones include, from the base upward, the flow interior, transition, and flow-top breccia zones of the analog flow, the interflow contact zone, and the flow interior and flow-top breccia zone of the superjacent flow. The intraflow structures and textures of the transition and interflow contact zones are atypical of Grande Ronde Basalt flows. The transition zone is transitional in textures between the flow interior zone and flow-top breccia zone, and includes holocrystalline spines mantled with fused in situ breccias. The interflow contact zone reflects the dynamic interaction during the emplacement of the superjacent flow manifested as invasive basalt tongues, clasts shed from tongues, pipe vesicles and tree molds, and pockets of breccia caught up in the base of the superjacent flow.
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Davison, Nigel. "The geochemistry of radioactive waste disposal." Thesis, Aston University, 1987. http://publications.aston.ac.uk/9698/.

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The present study attempted to identify the significant parameters which affect radionuclide migration from a low level radioactive waste disposal site located in a clay deposit. From initial sorption studies on smectite minerals, increased Kd with decreasing initial cation concentration was observed, and three sorption mechanisms were identified. The observation of anion dependent sorption was related to the existence of a mechanism in which an anion-cation pair are bound to the clay surface through the anion. The influence of competing cations, typical of inorganic groundwater constituents, depended on: (1) Ni/Co:Mn+(Mn+ = competing cation) ratio, (2) nature of M^n+, (3) total solution ionic strength. The presence of organic material in groundwater is well documented, but its effect on cation sorption has not been established. An initial qualitative investigation involving addition of simple organic ligands to Ni(Co)-hectorite samples demonstrated the formation of metal complexes in the clay interlayers, although some modified behaviour was observed. Further quantitative examination involving likely groundwater organic constituents and more comprehensive physical investigation confirmed this behaviour and enabled separation of the organic compounds used into two classes, according to their effect on cation sorption; (i) acids, (ii) amine compounds. X-ray photoelectron spectroscopy, scanning electron microscopy and Mossbauer spectroscopy were used to investigate the nature of transition metal ions sorbed onto montmorillonite and hectorite. Evidence strongly favoured the sorption of the hexaaquo cation, although a series of sorption sites of slightly different chemical characteristics were responsible for broadened peak widths observed in XPS and Mossbauer investigations. The surface sensitivity of XPS enabled recognition of the two surface sorption sites proposed in earlier sorption studies. Although thermal treatment of Fe^3+/Fe^2+-hectorite samples left iron atoms bonded to the silicate sheet structure, Mossbauer evidence indicated the presence of both ferric and ferrous iron in all samples.
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Maiden, Benjamin Gaylord. "Geographic implications of public policy : the siting of noxious facilities /." The Ohio State University, 1986. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487266011225094.

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Adkins, Dawn Marie. "A comparison perceived and calculated risk for a low-level radioactive waste disposal facility." Thesis, Georgia Institute of Technology, 1991. http://hdl.handle.net/1853/19683.

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McKeown, Christopher. "A model approach to radioactive waste disposal at Sellafield." Thesis, University of Glasgow, 1997. http://theses.gla.ac.uk/2588/.

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Sellafield in West Cumbria is the potential site of a repository for radioactive, Intermediate Level Waste (ILW). The proposed repository lies at 650 m beneath the ground surface to the west of the 1000 m uplands of the Lake District. The fractured Borrowdale Volcanic Group (BVG) host rock is overlain by a sequence of Carboniferous and Permo-Triassic sediments. Fresh, saline and brine groundwaters exist in the subsurface. Upward trending fluid pressure gradients have been measured in the area of the potential repository site. Steady-state, 2-D simulations of fluid flow were undertaken with the OILGEN code. Topographically driven flow dominates the regional hydrogeology. Subsurface fluid flow trended persistently upwards through the potential repository site. The dense brines to the west of the site promoted upward deflection of groundwaters. The groundwater flow rate through the potential repository site was dependent upon the hydraulic conductivity of the BVG. Calibration of the model was achieved by matching simulated subsurface pressures to those measured in-situ. Emergent repository fluids could reach the surface in 15,000 years. The measured BVG hydraulic conductivity is up to 1000 times too high to be simply declared safe. Geochemical simulations, with Geochemist's Workbench?, showed natural BVG groundwaters display redox disequilibrium. The in-situ Eh is most probably +66 mV. Pyrite, absent from rock fractures, would not enforce a reducing -250 mV Eh. Steel barrels and alkaline cement are intended to geochemically retain 2.5x106 kg of uranium. Simulations of repository cement/BVG groundwater interactions produced pH 10 at 80°C but no change in the +66 mV Eh. Steel barrel interactions produced an alkaline fluid with Eh -500 mV. Uranium solubility in the high pH repository near field was as high as 10-2.7 M, regardless of steel interactions. Uranium solubility adjacent to the repository (pseudo near field) was controlled by Eh; ranging from 10-13 M in the presence of steel, to 10-2.7 M with no steel. Uranium retention is controlled only by steel barrel durability. Oxidising, natural BVG groundwater will enhance steel barrel destruction. Distant from repository (far field) uranium solubility was 10-5.4 M if Eh was as measured in-situ. Thermodynamic data variations affect the calculation of uranium solubility; uranium near field solubility can be as high as 10-1.4 M. Uranium solubilities in near-field high pH groundwater could be more than 600 times greater than the 10-5.5 M used by the UK Nirex Ltd. in their safety case simulations.
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West, J. M. "Geomicrobiological aspects of the deep disposal of radioactive waste." Thesis, Edinburgh Napier University, 1987. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.379139.

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Taiyabi, Asif A. "A multi-attribute analysis of nuclear waste disposal alternatives." Master's thesis, This resource online, 1991. http://scholar.lib.vt.edu/theses/available/etd-02022010-020127/.

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Bonnett, Timothy Charles. "A systems view of the nuclear waste dilemma." Master's thesis, This resource online, 1991. http://scholar.lib.vt.edu/theses/available/etd-01202010-020205/.

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Creese, Thomas Chalmers. "Use of metamodels in a probabilistic radiological assessment /." Digital version accessible at:, 1998. http://wwwlib.umi.com/cr/utexas/main.

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Books on the topic "Radioactive waste disposal in rivers"

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Trask, N. J. U.S. Geological Survey research in radioactive waste disposal: Fiscal years 1986 - 1990. Reston, Va: U.S. Dept. of the Interior, U.S. Geological Survey, 1991.

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Trask, N. J. U.S. Geological Survey research in radioactive waste disposal: Fiscal years 1986 - 1990. Reston, Va: U.S. Dept. of the Interior, U.S. Geological Survey, 1991.

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Trask, N. J. U.S. Geological Survey research in radioactive waste disposal: Fiscal years 1986 - 1990. Reston, Va: U.S. Dept. of the Interior, U.S. Geological Survey, 1991.

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Hunt, G. J. Radioactivity in surface and coastal waters of the British Isles, 1985. Lowestoft: Ministry of Agriculture, Fisheries and Food, Directorate of Fisheries Research, 1986.

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Hunt, G. J. Radioactivity in surface and coastal waters of the British Isles, 1983. Lowestoft [Suffolk]: Ministry of Agriculture, Fisheries, and Food, Directorate of Fisheries Research, 1985.

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Bird, G. A. Transport of radionuclides in rivers: A review of river transport models. Pinawa, Man: AECL, Whiteshell Laboratories, 1996.

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Guerrero, Peter F. Water pollution: Coordinated strategy needed to address radioactive and toxic wastes in the Massachusetts Bay : statement of Peter F. Guerrero, associate director, Environmental Protection Issues, Resources, Community, and Economic Development Division, before the Subcommittee on Fisheries and Wildlife Conservation and the Environment, Committee on Merchant Marine and Fisheries, House of Representatives. [Washington, D.C.]: The Office, 1991.

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Bird, G. A. Background chemical and radiological levels in Canadian Shield lakes and in groundwater. Pinawa, Man: AECL, Whiteshell Laboratories, 1997.

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United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment. Implementation of the Nuclear Waste Policy Act: Oversight hearing before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-eighth Congress, second session ... hearing held in Salt Lake City, UT, October 12, 1984. Washington: U.S. G.P.O., 1985.

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United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment. Implementation of the Nuclear Waste Policy Act: Oversight hearing before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-eighth Congress, second session ... hearing held in Salt Lake City, UT, October 12, 1984. Washington: U.S. G.P.O., 1985.

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Book chapters on the topic "Radioactive waste disposal in rivers"

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Duerden, P., C. Golian, C. J. Hardy, T. Nightingale, and T. Payne. "Alligator Rivers Analogue Project Review of Research and Its Implications for Model Validation." In Natural Analogues in Radioactive Waste Disposal, 82–91. Dordrecht: Springer Netherlands, 1987. http://dx.doi.org/10.1007/978-94-009-3465-8_8.

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Bennett, William M., and Herbert H. Elder. "Startup of Savannah River’s Defense Waste Processing Facility To Produce Radioactive Glass." In Science and Technology for Disposal of Radioactive Tank Wastes, 323–34. Boston, MA: Springer US, 1998. http://dx.doi.org/10.1007/978-1-4899-1543-6_24.

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Niibori, Yuichi. "Radioactive Waste Disposal." In An Advanced Course in Nuclear Engineering, 153–73. Tokyo: Springer Japan, 2015. http://dx.doi.org/10.1007/978-4-431-55417-2_6.

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Saha, Gopal B. "Disposal of Radioactive Waste." In Radiation Safety in Nuclear Medicine, 143–48. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-16406-5_10.

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Fentiman, Audeen W. "Radioactive Waste Management radioactive radioactive waste management : Storage, Transport, Disposal." In Encyclopedia of Sustainability Science and Technology, 8588–97. New York, NY: Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4419-0851-3_29.

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Owunwanne, Azuwuike, Mohan Patel, and Samy Sadek. "Disposal of radioactive waste material." In The Handbook of Radiopharmaceuticals, 202. Boston, MA: Springer US, 1995. http://dx.doi.org/10.1007/978-1-4757-0414-3_20.

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Cliffe, Andrew. "Modelling in Radioactive Waste Disposal." In Simplicity, Complexity and Modelling, 173–85. Chichester, UK: John Wiley & Sons, Ltd, 2011. http://dx.doi.org/10.1002/9781119951445.ch10.

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Krauskopf, Konrad B. "Critique of disposal models." In Radioactive Waste Disposal and Geology, 69–79. Dordrecht: Springer Netherlands, 1988. http://dx.doi.org/10.1007/978-94-009-1201-4_5.

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Krauskopf, Konrad B. "Institutional aspects of waste disposal." In Radioactive Waste Disposal and Geology, 121–26. Dordrecht: Springer Netherlands, 1988. http://dx.doi.org/10.1007/978-94-009-1201-4_10.

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Krauskopf, Konrad B. "High-level waste: the problem." In Radioactive Waste Disposal and Geology, 12–29. Dordrecht: Springer Netherlands, 1988. http://dx.doi.org/10.1007/978-94-009-1201-4_2.

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Conference papers on the topic "Radioactive waste disposal in rivers"

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Kruger, Albert A. "Waste Loading Enhancements for Hanford Low-Activity Waste Glasses." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59018.

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About 50 million gallons of mixed waste is currently stored in underground tanks at The United States Department of Energy’s (DOE) Hanford site in Washington state. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide the Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product is destined for disposal in an engineered facility at Hanford site while the IHLW product will be disposed in a national geological repository. Both waste forms must meet a variety of requirements to ensure the protection of the environment before they can be accepted for disposal.
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Kawamura, Makoto, Shin-ichi Tanikawa, Tadafumi Niizato, and Ken-ichi Yasue. "Development of Methodology to Construct a Generic Conceptual Model of River-Valley Evolution for Performance Assessment of HLW Geological Disposal." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40137.

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In order to assess the long-term safety of a geological disposal system for high-level radioactive waste (HLW), it is important to consider the impact of uplift and erosion, which cannot be precluded on a timescale in the order of several hundred thousand years for many locations in Japan. Geomorphic evolution, caused by uplift and erosion and coupled to climatic and sea-level changes, will impact the geological disposal system due to resulting spatial and temporal changes in the disposal environment. Degradation of HLW barrier performance will be particularly significant when the remnant repository structures near, and are eventually exposed at, the ground surface. In previous studies, fluvial erosion was identified as the key concern in most settings in Japan. Interpretation of the impact of the phenomena at relevant locations in Japan has led to development of a generic conceptual model which contains the features typical at middle reach of rivers. Here, therefore, we present a methodology for development of a generic conceptual model based on best current understanding of fluvial erosion in Japan, which identifies the simplifications and uncertainties involved and assesses their consequences in the context of repository performance.
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Diaconu, Daniela, Kay Birdsell, and George Zyvoloski. "Natural and Engineered Barriers in a Romanian Disposal Site for Low and Intermediate Level Waste." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4638.

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The operational waste generated by the Cernavoda Nuclear Power Plant will be disposed in a near-surface facility. The low and intermediate level wastes, containing particularly large concentrations of C-14 and H-3, are treated and conditioned in steel drums, which will be placed in the disposal cells and then immobilized in concrete. The Saligny site has been proposed for LIL waste disposal. Geologically, the main components of this site are the quaternary loess, the Precambrian and pre-quaternary clays, and the Eocene and Barremian limestones. Hydrologically, the site can be divided into a vadose zone down to 45–50m and three distinct aquifers, two of them in the limestone beds and the third into the lenses of sand and limestone existing in the pre-quaternary clay layer. Preliminary performance assessments, presented in this paper, indicate that the geologic layers are efficient natural barriers against water flow and radionuclide migration from the vadose zone to the Barremian aquifer. The semi-arid climate and the low precipitation rate prevent contaminant transport from the disposal site to the Eocene aquifer. FEHM simulations of transient groundwater flow showed that seasonal variations influence the moisture content profile in the top of the vadose zone, but the influence over the long term is not significant for contaminant transport. The Danube River level variations control water movement in the Barremian aquifer, especially in the upper part where the limestone is highly fractured and water moves toward the river when its level is low and toward the site when the river level is high. The disposal concept tries to combine the natural and engineered barriers in order to ensure the safety of the environment and population. Therefore, the concrete filling the disposal cells surrounds the waste with a medium that facilitates C-14 retention by precipitation, thus reducing the C-14 releases in the atmosphere and geosphere.
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Marivoet, Jan, Xavier Sillen, and Peter De Preter. "Functional Requirements and Performance Assessment: Application to the Case of Spent Fuel Disposal in Clay." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1246.

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Abstract Geological repository systems for the disposal of radioactive waste are based on a multi-barrier design. Individual barriers contribute in different ways to the overall long-term performance of the repository system, and furthermore, the contribution of each barrier can considerably change with time. In a systematic analysis of the functional requirements for achieving long-term safety a number of basic safety functions can be defined: physical confinement, retardation / slow release, dispersion / dilution and limited accessibility. In the case of the geological disposal of spent fuel in a clay formation a series of barriers are designed or chosen to contribute to the realisation of the basic safety functions. The physical confinement is realised by the watertight, high-integrity container, which prevents contact between groundwater and the confined radionuclides. In first instance the retardation / slow release function is realised by the slow dissolution of the waste matrix and by the limited solubility of many elements in the near field. However, the natural clay barrier provides the main contribution to this safety function. The migration of radionuclides through the Boom Clay is mainly due to molecular diffusion, which is an extremely slow process. Furthermore, many elements are strongly sorbed by the clay minerals what makes their migration even much slower. The dispersion / dilution function mainly occurs in the aquifer and the rivers draining the aquifer in the surroundings of the disposal system. Various performance indicators are used to quantify the contributions of each safety function and to explain the functioning of the repository system.
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Jordan, Jeff, and Greg Flach. "Containment of Low-Level Radioactive Waste at the DOE Saltstone Disposal Facility." In ASME 2012 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/pvp2012-78797.

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As facilities look for permanent storage of toxic materials, they are forced to address the long-term impacts to the environment as well as any individuals living in affected area. As these materials are stored underground, modeling of the contaminant transport through the ground is an essential part of the evaluation. The contaminant transport model must address the long-term degradation of the containment system as well as any movement of the contaminant through the soil and into the groundwater. In order for disposal facilities to meet their performance objectives, engineered and natural barriers are relied upon. Engineered barriers include things like the design of the disposal unit, while natural barriers include things like the depth of soil between the disposal unit and the water table. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) in South Carolina is an example of a waste disposal unit that must be evaluated over a timeframe of thousands of years. The engineered and natural barriers for the SDF allow it to meet its performance obejective over the long time frame.
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Blankenhorn, James A. "A Model for a National Low Level Waste Program." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16372.

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A national program for the management of low level waste is essential to the success of environmental clean-up, decontamination and decommissioning, current operations and future missions. The value of a national program is recognized through procedural consistency and a shared set of resources. A national program requires a clear waste definition and an understanding of waste characteristics matched against available and proposed disposal options. A national program requires the development and implementation of standards and procedures for implementing the waste hierarchy, with a specific emphasis on waste avoidance, minimization and recycling. It requires a common set of objectives for waste characterization based on the disposal facility’s waste acceptance criteria, regulatory and license requirements and performance assessments. Finally, a national waste certification program is required to ensure compliance. To facilitate and enhance the national program, a centralized generator services organization, tasked with providing technical services to the generators on behalf of the national program, is necessary. These subject matter experts are the interface between the generating sites and the disposal facility(s). They provide an invaluable service to the generating organizations through their involvement in waste planning prior to waste generation and through championing implementation of the waste hierarchy. Through their interface, national treatment and transportation services are optimized and new business opportunities are identified. This national model is based on extensive experience in the development and on-going management of a national transuranic waste program and management of the national repository, the Waste Isolation Pilot Plant. The Low Level Program at the Savannah River Site also successfully developed and implemented the waste hierarchy, waste certification and waste generator services concepts presented below. The Savannah River Site services over forty generators and has historically managed over 12,000 cubic meters of low level waste annually. The results of the waste minimization program at the site resulted in over 900 initiatives, avoiding over 220,000 cubic meters of waste for a life cycle cost savings of $275 million. At the Los Alamos National Laboratory, the low level waste program services over 20 major generators and several hundred smaller generators that produce over 4,000 cubic meters of low level waste annually. The Los Alamos National Laboratory low level waste program utilizes both on-site and off-site disposal capabilities. Off-site disposal requires the implementation of certification requirements to utilize both federal and commercial options. The Waste Isolation Pilot Plant is the US Department of Energy’s first deep geological repository for the permanent disposal of Transuanic waste. Transuranic waste was generated and retrievably stored at 39 sites across the US. Transuranic waste is defined as waste with a radionuclide concentration equal to or greater than 100 nCi/g consisting of radionuclides with half-lives greater than 20 years and with an atomic mass greater than uranium. Combining the lessons learned from the national transuranic waste program, the successful low level waste program at Savannah River Site and the experience of off-site disposal options at Los Alamos National Laboratory provides the framework and basis for developing a viable national strategy for managing low level waste.
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Geddes, Brian, Chris Wenzel, Michael Owen, Mark Gardiner, and Julie Brown. "Remediation of Canada’s Historic Haul Route for Radium and Uranium Ores: The Northern Transportation Route." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59303.

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Established in the 1930s, the Northern Transportation Route (NTR) served to transport pitchblende ore 2,200 km from the Port Radium Mine in Canada’s Northwest Territories to Fort McMurray in Alberta. From there, the ore was shipped 3,000 km by rail to the Town of Port Hope, Ontario, where it was refined for its radium content and used for medical purposes. Later, transport and refinement focussed on uranium. The corridor of lakes, rivers, portages and roads that made up the NTR included a number of transfer points, where ore was unloaded and transferred to other barges or trucks. Ore was occasionally spilled during these transfer operations and, in some cases, subsequently distributed over larger areas as properties were re-developed or modified. In addition, relatively small volumes of ore were sometimes transported by air to the south. Since 1991, the Low-Level Radioactive Waste Management Office (LLRWMO), working with communities and its consulting contractors, has conducted surveys to identify and characterize spill sites along the NTR where soils exhibit elevated concentrations of uranium, radium and/or arsenic. In addition to significant areas of impact in Fort McMurray, contamination along the NTR was centred in the Sahtu region near Great Bear Lake and along the southern part of the Slave River. Early radiological investigations found contaminated buildings and soil and occasionally discrete pieces of pitchblende ore at many transfer points and storage areas along the NTR. Where possible, survey work was undertaken in conjunction with property redevelopment activity requiring the relocation of impacted soils (e.g., at Tulita, Fort Smith, Hay River, and Fort McMurray). When feasible to consolidate contaminated material locally, it was placed into Long Term Management Facilities developed to manage and monitor the materials over extended timelines. Radiological activity generated by these engineered facilities are generally below thresholds established by Canadian regulators, meaning they are straightforward to maintain, with minor environmental and community impacts. Securing community acceptance for these facilities is critical, and represents the predominant development component of plans for managing ore-impacted soils. In those circumstances where local consolidation is not achievable, materials have been relocated to disposal facilities outside of the region. The LLRWMO is continuing a program of public consultation, technical evaluation and environmental assessment to develop management plans for the remaining ore-impacted sites on the NTR. This paper will highlight current activities and approaches applied for the responsible management of uranium and radium mining legacies.
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Hobbs, D. T., T. B. Peters, M. C. Duff, M. J. Barnes, S. D. Fink, and D. D. Walker. "Radiochemical Separations for the Pretreatment of High-Level Nuclear Waste Solutions at the Savannah River Site." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4536.

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A significant fraction of the high-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) must be pretreated to remove 137Cs, 90Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes planned at the SRS include caustic side solvent extraction for 137Cs and sorption onto monosodium titanate (MST) for 90Sr and alpha-emitters. The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes 238Pu, 239Pu and 240Pu. This paper describes the planned Sr/actinide separation process and summarizes recent tests and demonstrations with simulated and actual tank waste solutions.
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Lawless, W. F., Mito Akiyoshi, John Whitton, Fjorentina Angjellari-Dajci, and Christian Poppeliers. "A Comparative Study of Stakeholder Participation in the Cleanup of Radioactive Wastes in the US, Japan and UK." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40219.

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We review case studies of stakeholder participation in the environmental cleanup of radioactive wastes in the United States, Japan and United Kingdom (e.g., [21,26,27,66,78]). Citizen participation programs in these three countries are at different stages: mature in the US, starting in Japan, and becoming operational in the UK. The US issue at the US Department of Energy’s (DOE) Savannah River Site (SRS) in South Carolina (SC) had been focused on citizens encouraging Federal (DOE; US Environmental Protection Agency, or EPA; and the US Nuclear Regulatory Commission, or NRC) and State (SC’s Department of Health and Environmental Compliance, or DHEC) agencies to pursue “Plug-in-RODs” at SRS to simplify the regulations to accelerate closing seepage basins at SRS. In Japan, the Reprocessing of spent fuel and deep geological disposal of vitrified high-level waste have been among Japan’s priorities. A reprocessing plant in Rokkasho, Aomori Prefecture is expected to commence operations in October 2010. The search of a site for a deep geological disposal facility has been ongoing since 2002. But the direct engagement of stakeholders has not occurred in Japan. Indirectly, stakeholders attempt to exert influence on decision-making with social movements, local elections, and litigation. In the UK, the issue is gaining effective citizen participation with the UK’s Nuclear Decommissioning Authority (NDA). We hope that the case studies from these countries may improve citizen participation.
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Spears, Terrel J., James W. McCullough, Harry D. Harmon, and Robert K. Leugemors. "Status of the Salt Waste Processing Facility at the Savannah River Site." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4651.

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The Department of Energy’s (DOE) Savannah River Site (SRS) High-Level Waste (HLW) Program is responsible for storage, treatment, and immobilization of HLW for disposal. The Salt Processing Program (SPP) is the salt (soluble) waste treatment portion of this effort. The overall SPP encompasses the selection, design, construction and operation of treatment technologies to prepare the salt waste feed material for the site’s Saltstone Facility and vitrification facility (Defense Waste Processing Facility). Major constituents that must be removed from the salt waste include actinides, strontium, cesium, and entrained sludge. In fiscal year (FY) 2002, research and development (R&D) on the actinide and strontium removal and Caustic-Side Solvent Extraction (CSSX) processes transitioned from technology development for baseline process selection to providing input for conceptual design of the Salt Waste Processing Facility (SWPF), a key component at the SRS SPP. This work included laboratory studies, bench-scale tests, and prototype equipment development. To implement the salt waste treatment technologies, DOE initiated a competitive procurement process to select Engineering, Procurement, and Construction (EPC) contractors for design of the SWPF. The Department awarded EPC contracts to Parsons Infrastructure & Technology Group, Inc. and Foster Wheeler USA Corporation for preparation of conceptual designs (Phase I) for the SWPF. The two EPC contractors began conceptual design activities in September 2002 and are scheduled to complete this work in January 2004. After evaluation of the conceptual designs, DOE will down select one EPC contractor to continue with final design, construction, and hot commissioning (Phase II). Hot startup of the SWPF is targeted for December 2009.
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Reports on the topic "Radioactive waste disposal in rivers"

1

Van Hoesen, S. (Low-level radioactive waste disposal). Office of Scientific and Technical Information (OSTI), June 1985. http://dx.doi.org/10.2172/5273682.

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White, G. J., T. W. Ferns, M. D. Otis, S. T. Marts, M. S. DeHaan, R. G. Schwaller, and G. J. White. Low-level radioactive waste disposal facility closure. Office of Scientific and Technical Information (OSTI), November 1990. http://dx.doi.org/10.2172/6324264.

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Cranwell, R. M., J. E. Campbell, N. R. Ortiz, and R. V. Guzowski. Risk methodology for geologic disposal of radioactive waste. Office of Scientific and Technical Information (OSTI), April 1990. http://dx.doi.org/10.2172/7178896.

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Sassani, David Carl, Charles Michael Stone, Francis D. Hansen, Ernest L. Hardin, Thomas A. Dewers, Mario J. Martinez, Robert Paul Rechard, et al. Shale disposal of U.S. high-level radioactive waste. Office of Scientific and Technical Information (OSTI), May 2010. http://dx.doi.org/10.2172/992338.

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Stein, Joshua S., Geoffrey A. Freeze, Patrick Vane Brady, Peter N. Swift, Robert Paul Rechard, Bill Walter Arnold, Joseph F. Kanney, and Stephen J. Bauer. Deep borehole disposal of high-level radioactive waste. Office of Scientific and Technical Information (OSTI), July 2009. http://dx.doi.org/10.2172/985495.

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Kuhlman, Kristopher L., Edward N. Matteo, Benjamin Reedlunn, Melissa Marie Mills, Steven R. Sobolik, Michael B. Gross, and Eric Simo. International Collaborations on Radioactive Waste Disposal in Salt. Office of Scientific and Technical Information (OSTI), August 2019. http://dx.doi.org/10.2172/1559570.

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Freeze, Geoffrey A., Paul E. Mariner, Joon H. Lee, Ernest L. Hardin, Barry Goldstein, Francis D. Hansen, Ronald H. Price, and Anna Snider Lord. Granite disposal of U.S. high-level radioactive waste. Office of Scientific and Technical Information (OSTI), August 2011. http://dx.doi.org/10.2172/1029794.

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Hoffman, E. A., W. M. Stacey, and N. E. Hertel. Radioactive waste disposal characteristics of candidate tokamak demonstration reactors. Office of Scientific and Technical Information (OSTI), August 1998. http://dx.doi.org/10.2172/639799.

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Kuhlman, Kristopher, Edward Matteo, Melissa Mills, Richard Jayne, Benjamin Reedlunn, Steven Sobolik, James Bean, Emily Stein, and Michael Gross. International Collaborations on Radioactive Waste Disposal in Salt (FY20). Office of Scientific and Technical Information (OSTI), July 2020. http://dx.doi.org/10.2172/1643980.

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Seitz, R. R., R. S. Garcia, K. M. Kostelnik, and R. J. Starmer. Performance assessment handbook for low-level radioactive waste disposal facilities. Office of Scientific and Technical Information (OSTI), February 1992. http://dx.doi.org/10.2172/7117572.

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