Infiltration SuDS Map

OpenAIRE

Dearden, Rachel

2012-01-01

Infiltration SuDS are sustainable drainage systems (SuDS) that allow surface water to infiltrate to the ground. Examples include soakaways, infiltration basins, infiltration trenches and permeable pavements. Before planning to install Infiltration SuDS, the suitability of the ground should be assessed. The British Geological Survey has developed a bespoke Infiltration SuDS Map that enables a preliminary assessment of the suitability of the ground for infiltration SuDS. Th...

Ground-water quality beneath solid-waste disposal sites at anchorage, Alaska

Science.gov (United States)

Zenone, Chester; Donaldson, D.E.; Grunwaldt, J.J.

1975-01-01

Studies at three solid-waste disposal sites in the Anchorage area suggest that differences in local geohydrologic conditions influence ground-water quality. A leachate was detected in ground water within and beneath two sites where the water table is very near land surface and refuse is deposited either at or below the water table in some parts of the filled areas. No leachate was detected in ground water beneath a third site where waste disposal is well above the local water table.

Skin hydration in nursing home residents using disposable bed baths.

Science.gov (United States)

Gillis, Katrin; Tency, Inge; Roelant, Ella; Laureys, Sarina; Devriendt, Hendrik; Lips, Dirk

2016-01-01

The objective of this study was to evaluate a new way for applying bed baths and reducing the risk for dry skin by comparing the effect of two washing methods on skin hydration. A cluster randomized trial was conducted. Skin hydration was measured before and after implementation of disposable wash gloves, using a MoistureMeter SC at three skin sites. Total skin hydration did not differ between residents at the start of the study in both groups. After implementation, the post minus pre hydration scores were higher for the intervention group than the control group at all skin sites. However, the difference was only significant at cheek site. The use of disposable wash gloves does not increase the risk for dry skin in comparison with traditional washing methods. These results may encourage the introduction of disposable wash gloves as an innovation in daily skin care practice. Copyright © 2016 Elsevier Inc. All rights reserved.

UNSAT-H infiltration model calibration at the Subsurface Disposal Area, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Martian, P.

1995-10-01

Soil moisture monitoring data from the expanded neutron probe monitoring network located at the Subsurface Disposal Area (SDA) of the Idaho National Engineering Laboratory (INEL) were used to calibrate numerical infiltration models for 15 locations within and near the SDA. These calibrated models were then used to simulate infiltration into the SDA surficial sediments and underlying basalts for the entire operational period of the SDA (1952--1995). The purpose of performing the simulations was to obtain a time variant infiltration source term for future subsurface pathway modeling efforts as part of baseline risk assessment or performance assessments. The simulation results also provided estimates of the average recharge rate for the simulation period and insight into infiltration patterns at the SDA. These results suggest that the average aquifer recharge rate below the SDA may be at least 8 cm/yr and may be as high as 12 cm/yr. These values represent 38 and 57% of the average annual precipitation occurring at the INEL, respectively. The simulation results also indicate that the maximum evaporative depth may vary between 28 and 148 cm and is highly dependent on localized lithology within the SDA

Control of water infiltration into near surface low-level waste disposal units. Final report on field experiments at a humid region site, Beltsville, Maryland

International Nuclear Information System (INIS)

Schulz, R.K.; Ridky, R.W.; O'Donnell, E.

1997-09-01

This study''s objective was to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work was carried out in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (70 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration were investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management

Deep geologic disposal of mixed waste in bedded salt: The Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Rempe, N.T.

1993-01-01

Mixed waste (i.e., waste that contains both chemically hazardous and radioactive components) poses a moral, political, and technical challenge to present and future generations. But an international consensus is emerging that harmful byproducts and residues can be permanently isolated from the biosphere in a safe and environmentally responsible manner by deep geologic disposal. To investigate and demonstrate such disposal for transuranic mixed waste, derived from defense-related activities, the US Department of Energy has prepared the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This research and development facility was excavated approximately at the center of a 600 m thick sequence of salt (halite) beds, 655 m below the surface. Proof of the long-term tectonic and hydrological stability of the region is supplied by the fact that these salt beds have remained essentially undisturbed since they were deposited during the Late Permian age, approximately 225 million years ago. Plutonium-239, the main radioactive component of transuranic mixed waste, has a half-life of 24,500 years. Even ten half-lives of this isotope - amounting to about a quarter million years, the time during which its activity will decline to background level represent only 0.11 percent of the history of the repository medium. Therefore, deep geologic disposal of transuranic mixed waste in Permian bedded salt appears eminently feasible

Comparison and analysis of release scenarios for ground disposal of various nations

International Nuclear Information System (INIS)

Sakata, Sadahiro; Nakai, Kunihiro

1985-01-01

This report is aimed at comparing and analyzing the concept and evaluation methods of varuous foreign countries concerning their release scenarios for ground disposal of low- and high-level radioactive wastes in order to provide helpful information to be used in developing release scenarios for Japan. The groundwater release scenario and human intrusion scenario should particularly be well examined in considering shallow ground disposal of low-level wastes. Assessment of the leaching rate is important for a groundwater release scenario. Experimental data and verification tests are required to support the simplified model to be used for safety assessment. Evaluation of the radioactive nucleide inventory is also important for ground disposal of low-level wastes. An evaluation system should be established as soon as possible. For ground disposal of high-level radioactive wastes, on the other hand, it will become increasingly important to establish performance assessment models for practical evaluation of the rate of release from the engineered barrier and to collect test and verification data for suporting them. (Nogami, K.)

Disposal facility in Olkiluoto, description of above ground facilities in tunnel transport alternative

International Nuclear Information System (INIS)

Kukkola, T.

2006-11-01

The above ground facilities of the disposal plant on the Olkiluoto site are described in this report as they will be when the operation of the disposal facility starts in the year 2020. The disposal plant is visualised on the Olkiluoto site. Parallel construction of the deposition tunnels and disposal of the spent fuel canisters constitute the principal design basis of the disposal plant. The annual production of disposal canisters for spent fuel amounts to about 40. Production of 100 disposal canisters has been used as the capacity basis. Fuel from the Olkiluoto plant and from the Loviisa plant will be encapsulated in the same production line. The disposal plant will require an area of about 15 to 20 hectares above ground level. The total building volume of the above ground facilities is about 75000 m 3 . The purpose of the report is to provide the base for detailed design of the encapsulation plant and the repository spaces, as well as for coordination between the disposal plant and ONKALO. The dimensioning bases for the disposal plant are shown in the Tables at the end of the report. The report can also be used as a basis for comparison in deciding whether the fuel canisters are transported to the repository by a lift or a by vehicle along the access tunnel. (orig.)

Disposal facility in olkiluoto, description of above ground facilities in lift transport alternative

International Nuclear Information System (INIS)

Kukkola, T.

2006-11-01

The above ground facilities of the disposal plant on the Olkiluoto site are described in this report as they will be when the operation of the disposal facility starts in the year 2020. The disposal plant is visualised on the Olkiluoto site. Parallel construction of the deposition tunnels and disposal of the spent fuel canisters constitute the principal design basis of the disposal plant. The annual production of disposal canisters for spent fuel amounts to about 40. Production of 100 disposal canisters has been used as the capacity basis. Fuel from the Olkiluoto plant and from the Loviisa plant will be encapsulated in the same production line. The disposal plant will require an area of about 15 to 20 hectares above ground level. The total building volume of the above ground facilities is about 75000 m 3 . The purpose of the report is to provide the base for detailed design of the encapsulation plant and the repository spaces, as well as for coordination between the disposal plant and ONKALO. The dimensioning bases for the disposal plant are shown in the Tables at the end of the report. The report can also be used as a basis for comparison in deciding whether the fuel canisters are transported to the repository by a lift or by a vehicle along the access tunnel. (orig.)

Considerations of the Differences between Bedded and Domal Salt Pertaining to Disposal of Heat-Generating Nuclear Waste

Energy Technology Data Exchange (ETDEWEB)

Hansen, Francis D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kuhlman, Kristopher L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sobolik, Steven R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-07-07

Salt formations hold promise for eternal removal of nuclear waste from our biosphere. Germany and the United States have ample salt formations for this purpose, ranging from flat-bedded formations to geologically mature dome structures. As both nations revisit nuclear waste disposal options, the choice between bedded, domal, or intermediate pillow formations is once again a contemporary issue. For decades, favorable attributes of salt as a disposal medium have been extoled and evaluated, carefully and thoroughly. Yet, a sense of discovery continues as science and engineering interrogate naturally heterogeneous systems. Salt formations are impermeable to fluids. Excavation-induced fractures heal as seal systems are placed or natural closure progresses toward equilibrium. Engineering required for nuclear waste disposal gains from mining and storage industries, as humans have been mining salt for millennia. This great intellectual warehouse has been honed and distilled, but not perfected, for all nuances of nuclear waste disposal. Nonetheless, nations are able and have already produced suitable license applications for radioactive waste disposal in salt. A remaining conundrum is site location. Salt formations provide isolation and geotechnical barriers reestablish impermeability after waste is placed in the geology. Between excavation and closure, physical, mechanical, thermal, chemical, and hydrological processes ensue. Positive attributes for isolation in salt have many commonalities independent of the geologic setting. In some cases, specific details of the environment will affect the disposal concept and thereby define interaction of features, events and processes, while simultaneously influencing scenario development. Here we identify and discuss high-level differences and similarities of bedded and domal salt formations. Positive geologic and engineering attributes for disposal purposes are more common among salt formations than are significant differences

Considerations of the Differences between Bedded and Domal Salt Pertaining to Disposal of Heat-Generating Nuclear Waste

Energy Technology Data Exchange (ETDEWEB)

Hansen, Francis D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kuhlman, Kristopher L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sobolik, Steven R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-07-07

Salt formations hold promise for eternal removal of nuclear waste from our biosphere. Germany and the United States have ample salt formations for this purpose, ranging from flat-bedded formations to geologically mature dome structures. As both nations revisit nuclear waste disposal options, the choice between bedded, domal, or intermediate pillow formations is once again a contemporary issue. For decades, favorable attributes of salt as a disposal medium have been extoled and evaluated, carefully and thoroughly. Yet, a sense of discovery continues as science and engineering interrogate naturally heterogeneous systems. Salt formations are impermeable to fluids. Excavation-induced fractures heal as seal systems are placed or natural closure progresses toward equilibrium. Engineering required for nuclear waste disposal gains from mining and storage industries, as humans have been mining salt for millennia. This great intellectual warehouse has been honed and distilled, but not perfected, for all nuances of nuclear waste disposal. Nonetheless, nations are able and have already produced suitable license applications for radioactive waste disposal in salt. A remaining conundrum is site location. Salt formations provide isolation, and geotechnical barriers reestablish impermeability after waste is placed in the geology. Between excavation and closure, physical, mechanical, thermal, chemical, and hydrological processes ensue. Positive attributes for isolation in salt have many commonalities independent of the geologic setting. In some cases, specific details of the environment will affect the disposal concept and thereby define interaction of features, events and processes, while simultaneously influencing scenario development. Here we identify and discuss high-level differences and similarities of bedded and domal salt formations. Positive geologic and engineering attributes for disposal purposes are more common among salt formations than are significant differences

Considerations of the Differences between Bedded and Domal Salt Pertaining to Disposal of Heat-Generating Nuclear Waste

International Nuclear Information System (INIS)

Hansen, Francis D.; Kuhlman, Kristopher L.; Sobolik, Steven R.

2016-01-01

Salt formations hold promise for eternal removal of nuclear waste from our biosphere. Germany and the United States have ample salt formations for this purpose, ranging from flat-bedded formations to geologically mature dome structures. As both nations revisit nuclear waste disposal options, the choice between bedded, domal, or intermediate pillow formations is once again a contemporary issue. For decades, favorable attributes of salt as a disposal medium have been extoled and evaluated, carefully and thoroughly. Yet, a sense of discovery continues as science and engineering interrogate naturally heterogeneous systems. Salt formations are impermeable to fluids. Excavation-induced fractures heal as seal systems are placed or natural closure progresses toward equilibrium. Engineering required for nuclear waste disposal gains from mining and storage industries, as humans have been mining salt for millennia. This great intellectual warehouse has been honed and distilled, but not perfected, for all nuances of nuclear waste disposal. Nonetheless, nations are able and have already produced suitable license applications for radioactive waste disposal in salt. A remaining conundrum is site location. Salt formations provide isolation, and geotechnical barriers reestablish impermeability after waste is placed in the geology. Between excavation and closure, physical, mechanical, thermal, chemical, and hydrological processes ensue. Positive attributes for isolation in salt have many commonalities independent of the geologic setting. In some cases, specific details of the environment will affect the disposal concept and thereby define interaction of features, events and processes, while simultaneously influencing scenario development. Here we identify and discuss high-level differences and similarities of bedded and domal salt formations. Positive geologic and engineering attributes for disposal purposes are more common among salt formations than are significant differences

Groundwater flow analysis using mixed hybrid finite element method for radioactive waste disposal facilities

International Nuclear Information System (INIS)

Aoki, Hiroomi; Shimomura, Masanori; Kawakami, Hiroto; Suzuki, Shunichi

2011-01-01

In safety assessments of radioactive waste disposal facilities, ground water flow analysis are used for calculating the radionuclide transport pathway and the infiltration flow rate of groundwater into the disposal facilities. For this type of calculations, the mixed hybrid finite element method has been used and discussed about the accuracy of ones in Europe. This paper puts great emphasis on the infiltration flow rate of groundwater into the disposal facilities, and describes the accuracy of results obtained from mixed hybrid finite element method by comparing of local water mass conservation and the reliability of the element breakdown numbers among the mixed hybrid finite element method, finite volume method and nondegenerated finite element method. (author)

On-site infiltration of road runoff using pervious pavements with subjacent infiltration trenches as source control strategy.

Science.gov (United States)

Fach, S; Dierkes, C

2011-01-01

The focus in this work was on subsoil infiltration of stormwater from parking lots. With regard to operation, reduced infiltration performance due to clogging and pollutants in seepage, which may contribute to contaminate groundwater, are of interest. The experimental investigation covered a pervious pavement with a subjacent infiltration trench draining an impervious area of 2 ha. In order to consider seasonal effects on the infiltration performance, the hydraulic conductivity was measured tri-monthly during monitoring with a mobile sprinkling unit. To assess natural deposits jointing, road bed, gravel of infiltration trenches and subsoil were analysed prior to commencement of monitoring for heavy metals, polycyclic aromatic and mineral oil type hydrocarbons. Furthermore, from 22 storm events, water samples of rainfall, surface runoff, seepage and ground water were analysed with regard to the above mentioned pollutants. The study showed that the material used for the joints had a major impact on the initial as well as the final infiltration rates. Due to its poor hydraulic conductivity, limestone gravel should not be used as jointing. Furthermore, it is recommended that materials for the infiltration facilities are ensured free of any contaminants prior to construction. Polycyclic aromatic and mineral oil type hydrocarbons were, with the exception of surface runoff, below detection limits. Heavy metal concentrations of groundwater were with the exception of lead (because of high background concentrations), below the permissible limits.

Ground-Water Hydrology and Projected Effects of Ground-Water Withdrawals in the Sevier Desert, Utah

OpenAIRE

United States Geological Survey

1983-01-01

The principal ground-water reservoir in the Sevier Desert is the unconsolidated basin fill. The fill has been divided generally into aquifers and confining beds, although there are no clearcut boundaries between these units--the primary aquifers are the shallow and deep artesian aquifers. Recharge to the ground-water reservoir is by infiltration of precipitation; seepage from streams, canals, reservoirs, and unconsumed irrigation water; and subsurface inflow from consolidated rocks in mount...

Bacterial Colonization of Disposable Soft Contact Lenses Is Greater during Corneal Infiltrative Events than during Asymptomatic Extended Lens Wear

OpenAIRE

Sankaridurg, Padmaja R.; Sharma, Savitri; Willcox, Mark; Naduvilath, Thomas J.; Sweeney, Deborah F.; Holden, Brien A.; Rao, Gullapalli N.

2000-01-01

Microorganisms, especially gram-negative bacteria, are considered to play a role in the etiology of certain corneal infiltrative events (CIEs) observed during soft contact lens wear. This study explored the possibility of microbial colonization of soft contact lenses as a risk factor leading to CIEs. In a clinical trial conducted from March 1993 to January 1996, 330 subjects wore disposable soft contact lenses on a 6-night extended-wear and disposal schedule. During this period, 4,321 lenses ...

Ground water pollution by roof runoff infiltration evidenced with multi-tracer experiments.

Science.gov (United States)

Ammann, Adrian A; Hoehn, Eduard; Koch, Sabine

2003-03-01

The infiltration of urban roof runoff into well permeable subsurface material may have adverse effects on the ground water quality and endanger drinking water resources. Precipitation water from three different roofs of an industrial complex was channelled to a pit and infiltrated into a perialpine glaciofluvial gravel-and-sand aquifer. A shaft was constructed at the bottom of the pit and equipped with an array of TDR probes, lysimeters and suction cups that allowed measuring and sampling soil water at different depths. A fast infiltration flow was observed during natural rainfall events and during artificial infiltration experiments. For a better understanding of the behaviour of contaminants, experiments were conducted with cocktails of compounds of different reactivity (ammonium, strontium, atratone) and of non-reactive tracers (uranine, bromide, naphthionate), which represent different classes of pollutants. The experiment identified cation exchange reactions influencing the composition of the infiltrating water. These processes occurred under preferential flow conditions in macropores of the material. Measuring concentration changes under the controlled inflow of tracer experiments, the pollution potential was found to be high. Non-reactive tracers exhibited fast breakthrough and little sorption.

Application of an infiltration evaluation methodology to a hypothetical low-level waste disposal facility

International Nuclear Information System (INIS)

Meyer, P.D.

1993-12-01

This report provides an analysis of infiltration and percolation at a hypothetical low-level waste (LLW) disposal facility was carried out. The analysis was intended to illustrate general issues of concern in assessing the performance of LLW disposal facilities. Among the processes considered in the analysis were precipitation, runoff, information, evaporation, transpiration, and redistribution. The hypothetical facility was located in a humid environment characterized by frequent and often intense precipitation events. The facility consisted of a series of concrete vaults topped by a multilayer cover. Cover features included a sloping soil surface to promote runoff, plant growth to minimize erosion and promote transportation, a sloping clay layer, and a sloping capillary barrier. The analysis within the root zone was carried out using a one-dimensional, transient simulation of water flow. Below the root zone, the analysis was primarily two-dimensional and steady-state

Control of water infiltration into near-surface, low-level waste-disposal units in humid regions

International Nuclear Information System (INIS)

O'Donnell, E.; Ridky, R.W.; Schulz, R.K.

1994-01-01

This study's objective is to assess means for controlling water infiltration through waste-disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters (75 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste-disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care

A study on water infiltration barriers with compacted layered soils

International Nuclear Information System (INIS)

Umeda, Y.; Komori, K.; Fujiwara, A.

1993-01-01

In shallow-ground disposal of low-level radioactive wastes, water movements due to natural processes in the soil covering the disposal facility must be properly controlled. A capillary barrier with compacted layered soils can provide an effective means of controlling water movement in the soil covering placed on a low-level radioactive waste disposal facility. An experiment was performed to determine the effectiveness of a full-scale fill as a capillary barrier. The fill used in the experiment was constructed of compacted layers of clay, fine sand, and gravel. Man-made rain was caused to fall on the surfaces of the fill to observe the infiltration of rainwater into the fill and to measure the amount of water drained from within. The experiment established the effectiveness of the capillary barrier

Performance assessment for the disposal of low-level waste in the 200 east area burial grounds

Energy Technology Data Exchange (ETDEWEB)

Wood, M.I., Westinghouse Hanford

1996-08-15

A performance assessment analysis was completed for the 200 East Area Low-Level Burial Grounds (LLBG) to satisfy compliance requirements in DOE Order 5820.2A. In the analysis, scenarios of radionuclide release from the 200 East Area Low-Level waste facility was evaluated. The analysis focused on two primary scenarios leading to exposure. The first was inadvertent intrusion. In this scenario, it was assumed that institutional control of the site and knowledge of the disposal facility has been lost. Waste is subsequently exhumed and dose from exposure is received. The second scenario was groundwater contamination.In this scenario, radionuclides are leached from the waste by infiltrating precipitation and transported through the soil column to the underlying unconfined aquifer. The contaminated water is pumped from a well 100 m downstream and consumed,causing dose. Estimates of potential contamination of the surrounding environment were developed and the associated doses to the maximum exposed individual were calculated. The doses were compared with performance objective dose limits, found primarily in the DOE order 5850.2A. In the 200 East Area LLBG,it was shown that projected doses are estimated to be well below the limits because of the combination of environmental, waste inventory, and disposal facility characteristics of the 200 East Area LLBG. Waste acceptance criteria were also derived to ensure that disposal of future waste inventories in the 200 East Area LLBG will not cause an unacceptable increase in estimated dose.

Modeling snowmelt infiltration in seasonally frozen ground

Science.gov (United States)

Budhathoki, S.; Ireson, A. M.

2017-12-01

In cold regions, freezing and thawing of the soil govern soil hydraulic properties that shape the surface and subsurface hydrological processes. The partitioning of snowmelt into infiltration and runoff has also important implications for integrated water resource management and flood risk. However, there is an inadequate representation of the snowmelt infiltration into frozen soils in most land-surface and hydrological models, creating the need for improved models and methods. Here we apply, the Frozen Soil Infiltration Model, FroSIn, which is a novel algorithm for infiltration in frozen soils that can be implemented in physically based models of coupled flow and heat transport. In this study, we apply the model in a simple configuration to reproduce observations from field sites in the Canadian prairies, specifically St Denis and Brightwater Creek in Saskatchewan, Canada. We demonstrate the limitations of conventional approaches to simulate infiltration, which systematically over-predict runoff and under predict infiltration. The findings show that FroSIn enables models to predict more reasonable infiltration volumes in frozen soils, and also represent how infiltration-runoff partitioning is impacted by antecedent soil moisture.

Streambed infiltration and ground-water flow from the trout creek drainage, an intermittent tributary to the Humboldt River, north-central Nevada: Chapter K in Ground-water recharge in the arid and semiarid southwestern United States (Professional Paper 1703)

Science.gov (United States)

Prudic, David E.; Niswonger, Richard G.; Harrill, James R.; Wood, James L.; Stonestrom, David A.; Constantz, Jim; Ferré, Ty P.A.; Leake, Stanley A.

2007-01-01

Ground water is abundant in many alluvial basins of the Basin and Range Physiographic Province of the western United States. Water enters these basins by infiltration along intermittent and ephemeral channels, which originate in the mountainous regions before crossing alluvial fans and piedmont alluvial plains. Water also enters the basins as subsurface ground-water flow directly from the mountains, where infiltrated precipitation recharges water-bearing rocks and sediments at these higher elevations. Trout Creek, a typical intermittent stream in the Middle Humboldt River Basin in north-central Nevada, was chosen to develop methods of estimating and characterizing streambed infiltration and ground-water recharge in mountainous terrains. Trout Creek has a drainage area of about 4.8 × 107 square meters. Stream gradients range from more than 1 × 10–1 meter per meter in the mountains to 5 × 10–3 meter per meter at the foot of the piedmont alluvial plain. Trout Creek is perennial in short reaches upstream of a northeast-southwest trending normal fault, where perennial springs discharge to the channel. Downstream from the fault, the water table drops below the base of the channel and the stream becomes intermittent.Snowmelt generates streamflow during March and April, when streamflow extends onto the piedmont alluvial plain for several weeks in most years. Rates of streambed infiltration become highest in the lowest reaches, at the foot of the piedmont alluvial plain. The marked increases in infiltration are attributed to increases in streambed permeability together with decreases in channel-bed armoring, the latter which increases the effective area of the channel. Large quartzite cobbles cover the streambed in the upper reaches of the stream and are absent in the lowest reach. Such changes in channel deposits are common where alluvial fans join piedmont alluvial plains. Poorly sorted coarse and fine sediments are deposited near the head of the fan, while

Ground disposal of oil shale wastes: a review with an indexed annotated bibliography through 1976

Energy Technology Data Exchange (ETDEWEB)

Routson, R.C.; Bean, R.M.

1977-12-01

This review covers the available literature concerning ground-disposed wastes and effluents of a potential oil shale industry. Ground disposal has been proposed for essentially all of the solid and liquid wastes produced (Pfeffer, 1974). Since an oil shale industry is not actually in operation, the review is anticipatory in nature. The section, Oil Shale Technology, provides essential background for interpreting the literature on potential shale oil wastes and the topics are treated more completely in the section entitled Environmental Aspects of the Potential Disposal of Oil Shale Wastes to Ground. The first section of the annotated bibliography cites literature concerning potential oil shale wastes and the second section cites literature concerning oil shale technology. Each section contains references arranged historically by year. An index is provided.

A FIXED BED SORPTION SYSTEM FOR DEFLUORIDATION OF GROUND WATER

Directory of Open Access Journals (Sweden)

Ayoob Sulaiman

2009-06-01

Full Text Available The presence of excess fluoride in ground water has become a global threat with as many as 200 million people affected in more than 35 countries in all the continents. Of late, there have been significant advances in the knowledge base regarding the effects of excess fluoride on human health. As a result, defluoridation of ground water is regarded as one of the key areas of attention among the universal water community triggering global research. This study describes the sorptive responses of a newly developed adsorbent, alumina cement granules (ALC, in its real-life application in fixed beds, for removing fluoride from the ground waters of a rural Indian village. ALC exhibited almost consistent scavenging capacity at various bed depths in column studies with an enhanced adsorption potential of 0.818 mg/g at a flow rate of 4 ml/min. The Thomas model was examined to describe the sorption process. The process design parameters of the column were obtained by linear regression of the model. In all the conditions examined, the Thomas model could consistently predict its characteristic parameters and describe the breakthrough sorption profiles in the whole range of sorption process.

The effects of actinide separation on the radiological consequences of disposal of high-level radioactive waste on the ocean bed

International Nuclear Information System (INIS)

Camplin, W.C.; Grimwood, P.D.; White, I.F.

1980-01-01

One option in the management of high-level radioactive wastes is to separate the actinides prior to vitrification and disposal. This option is examined in the context of disposal of high-level wastes on the deep ocean bed. The initial quantity of waste corresponds to the generation of 1000 GW(e)y of nuclear energy, and the actinide-separation process is assumed to remove 99% of all elements of atomic number greater than that of actinium. The models used to describe the dispersion of activity from a single disposal site on the bed of the Atlantic Ocean represent both local dispersion and long-term mixing. Collective doses and doses to individuals are calculated for six potential pathways: ingestion of fish, crustacea, molluscs, plankton and seaweed, and external irradiation from contaminated beach sediments. The period from 400 to 1,000,000 years after disposal is considered. The potential radiological impact from disposal of high-level waste without separation of actinides on the ocean bed arises from the actinides; isotopes of americium, neptunium and plutonium give the highest doses. Actinide separation would reduce these doses in proportion to the effectiveness of the separation process, until doses become determined by fission products rather than actinides: the achievable dose reduction would be a factor of approximately a hundred, or less for certain pathways. This reduction applies only to doses to the public from waste disposal: no account was taken of doses arising from the separation process itself or from the management of the separated actinides. The results of the assessment are contrasted with those of similar studies based on toxicity indices. Major deficiencies are identified in the use of toxicity indices as a basis for decision-making. (author)

Current status of high level radioactive waste disposal in Japan and foreign countries

International Nuclear Information System (INIS)

Tanaka, Satoru; Tanabe, Hiromi; Inagaki, Yusuke; Ishida, Hisahiro; Kato, Osamu; Kurata, Mitsuyuki; Yamachika, Hidehiko

2002-01-01

At a time point of 2002, there is no country actually disposing high level radioactive wastes into grounds, but in most of countries legislative preparation and practicing agents are carried out and site selection is promoted together with energetic advancement of its R and Ds. As disposal methods of the high level radioactive wastes, various methods such as space disposal, oceanic bottom disposal, ice bed disposal, ground disposal, and so on have been examined. And, a processing technology called partitioning and transmutation technology separating long-lived radionuclides from liquid high level radioactive waste and transmutation into short-lived or harmless radionuclides has also been studied. Here was introduced their wrestling conditions in Japan and main foreign countries, as a special issue of the Current status of high level radioactive waste disposal in Japan and foreign countries'. The high level radioactive wastes (glassification solids or spent nuclear fuels) are wastes always formed by nuclear power generation and establishment of technologies is an important subject for nuclear fuel cycle. (G.K.)

Geochemical and Geophysical Study in a Degraded Area Used for Disposal of Sludge from a Water Treatment Plant

International Nuclear Information System (INIS)

Moreira, R.C.A.; Nunes, S.A.; Da Silva, D.R.; Lira, C.P.; Boaventura, G.R.; Do Nascimento, C.T.C.; Moreira, R.C.A.; Pinheiro, L.A.

2011-01-01

The effects of disposal of sludge from water treatment plant (WTS) in area damaged by laterite extraction and its consequences to soil and groundwater were investigated. Therefore, the presence and concentration of anthropogenic elements and chemical compounds were determinated. WTS disposal's influence was characterized by electroresistivity method. The WTS's geochemical dispersion was noticed in the first meters of the non saturated zone from the lending area. Lateritic profiles were characterized due to the large variation in chemical composition between the horizons. Infiltration and percolation of rainwater through the WTS have caused migration of total dissolved solids to the groundwater. WTS's disposing area has more similarities to local preserved vegetation than to gravel bed area. WTS can be considered a noninert residue if disposed in degraded areas located in regions with similar geological and hydrochemical characteristics.

Treatment/Disposal Plan for Drummed Waste from the 300-FF-1 Operable Unit, 618-4 Burial Ground

International Nuclear Information System (INIS)

Lerch, J.A.

1999-01-01

The objective of this plan is to support selection of a safe, environmentally responsible, and cost-effective treatment and disposal method for drums containing depleted uranium metal chips submerged in oil that have been and will be excavated from the 618-4 Burial Ground. Remediation of the 300-FF-1 Operable Unit, 618-4 Burial Ground was initiated in fiscal year (FY) 1998 as an excavation and removal operation. Routine processes were established to excavate and ship contaminated soil and debris to the Environmental Restoration Disposal Facility (ERDF) for disposal

Cultivation and Differentiation of Encapsulated hMSC-TERT in a Disposable Small-Scale Syringe-Like Fixed Bed Reactor

DEFF Research Database (Denmark)

Weber, Christian; Pohl, Sebastian; Pörtner, Ralf

2007-01-01

The use of commercially available plastic syringes is introduced as disposable small-scale fixed bed bioreactors for the cultivation of implantable therapeutic cell systems on the basis of an alginate-encapsulated human mesenchymal stem cell line. The system introduced is fitted with a noninvasiv...

Simulation of the distribution of radionuclides in the reservoir bed for deep-well injection disposal of acid liquid radioactive waste

International Nuclear Information System (INIS)

Noskov, M.D.; Istomin, A.D.; Kesler, A.G.; Zubkov, A.A.; Zakharova, E.V.; Egorov, G.F.

2007-01-01

A mathematical model was developed for describing the changes in the state of the reservoir bed for dee-well injection disposal of acid liquid radioactive waste. The model considers the multicomponent filtration of the solution in the heterogeneous bed, sorption-desorption of radionuclides, taking into account the dependence of the distribution coefficient on the temperature and pH, as well as radioactive decay, interaction of acids with minerals, radiation-chemical and thermochemical decomposition of the acids, and dynamics of the temperature field, taking into account the convective heat transfer, thermal conductivity, and radiogenic heat release. The results of the simulation of the migration of radionuclides were reported, as well as of the distribution of the acids and the dynamics of the temperature field in the vicinity of the injection well of the site for deep-well injection disposal of the waste from Siberian Chemical Combine. A man-caused barrier is formed in the vicinity of the injection well, hindering the spread of radionuclides in the reservoir bed [ru

On the influence of infiltration of radioactive beds by flushing fluid on γ-ray logging results obtained from uranium deposit No. 387

International Nuclear Information System (INIS)

Ren Bingxiang; Zhang Yuechun; Ai Shuyi.

1985-01-01

A large number of field logging data obtained during the course of exploration on uranium deposit No. 387 show when the radioactive beds are encountered by drill holes and the drilling continues the γ-ray intensity decreases. It is considered that the escape of emanation does not considerably influence the logging results. Therefore, based upon the experiment of immerseing ores in fluid and geological and hydrogeological data of the deposit, the hypotheses that the γ-ray intensity in drill hole is closely related with the infiltration of flushing fluid is suggested. The ore bodies are strictly controlled by faults. Most of the uranium and thorium are absorbed by pelitic-carbonaceous cements or fill the porous spaces in structural breccia and cataclasite. They are easy to dissolve in water. Moreover, the ore-bearing structures are the unique water aquifers which is under pressure. As the level of flushing fluid is higher than the pressure head so it continuously pours into the ore-bearing beds, resulting in the infiltration of U and Ra. Consequently, the radioactivity detected is low

An assessment of biological processes close to the sea bed in a slope region and its significance to the assessment of sea bed disposal of radioactive waste

International Nuclear Information System (INIS)

Hargreaves, P.M.; Ellis, C.J.; Angel, M.V.

1984-01-01

Vertical profiles of planktonic and micronektonic biomass observed close to the sea bed along a transect running up the continental slope on the southern flank of the Porcupine Seabight (to the southwest of Ireland) showed that a doubling in biomass concentration occurs from 100 to 10m above the sea bed. Comparison with biomass concentrations at two deep water stations, one in the Seabight and the other in the Rockall Trough, showed that there was a consistent increase in standing crop close to the sea bed over the slope. Supplementary data were collected on the northern flank of the Seabight. Analysis of both taxonomic groups and individual species showed that some taxa were more abundant near the sea floor and extended their vertical ranges to greater depths over the slope than over deep water, other taxa were unaffected. The implications to the problem of assessing the safety of sea bed disposal of high level radioactive waste are summarised. (author)

Studies involving proposed waste disposal facilities in Turkey

International Nuclear Information System (INIS)

Uslu, I.; Fields, D.E.; Yalcintas, M.G.

1987-01-01

Today principal sources of radioactive wastes are hospitals, research institutions, biological research centers, universities, industries and two research reactors in Turkey. These wastes will be treated in a pilot waste treatment facility located in Cekmece Nuclear Research and Training Center, Istanbul. In this temporary waste disposal facility, the wastes will be stored in 200 liter concrete containers until the establishment of the permanent waste disposal sites in Turkey, in 1990. The PRESTO - II (Prediction of Radiation Effects From Shallow Trench Operations) computer code was applied for the general probable sites for LLW disposal in Turkey. The model is non-site specific screening model for assessing radionuclide transport, ensuring exposure, and health impacts to a static local population for a chosen time period, following the end of the disposal operation. The methodology that this codes takes into consideration is versatile and explicitly considers infiltration and percolation of surface water into the trench, leaching of radionuclides, vertical and horizontal transport of radionuclides and use of this contaminated ground water for farming, irrigation, and ingestion

THE RESULTS OF THE DEFECT PLACES INVESTIGATION OF DONETSK RAILWAY ROAD BED BY GROUND PENETRATING RADAR COMPLEX

Directory of Open Access Journals (Sweden)

V. D. Petrenko

2014-10-01

Full Text Available Purpose. Defective places definition of road bed at ground penetrating radar is examined. Methodology. For achievement of this goal the experimental research on ground penetrating radar inspection of road bed defective places of the Donetsk Railway, which are caused by a complex of various reasons of geotechnical and constructive character, were conducted. Findings. According to these diagnostic results of road bed on the three districts of the Donetsk Railway is revealed the main causes which lead to the defects appearance, deformities and injuries in it, there is abuse of process parameters and modify its physic mechanical soil properties of natural and technology-related factors. As it is established, the use of ground penetrating radar of series “Losa” on the railways of Ukraine allows searching ballast tank in the body of road bed, defining damp places in soil road bed and foundations, to find arrangement of foreign matter in the soil road bed and work search heterogeneity and places weakening soil. In addition, the use of ground penetrating radar provides rapid detection of defects, deformation and damage of railway track, especially in areas the most dangerous for rolling stock that creates the high level security at the main and auxiliary lines of Ukrzaliznytsia. In conducting the research was justified the high level of reliability and performance with autonomous use of ground penetrating radar. Originality. In modern conditions of defects determination, deformations and damages by traditional methods with application of engineering-geological investigations, it is impossible in connection with their insufficient efficiency. Therefore the using of highly effective methodology of expeditious tool identification of defective places allows reducing significantly the periods of repair of a railway track which is very important for introduction of the high-speed movement on the Ukrainian Railways. Practical value. On the basis of the

Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

International Nuclear Information System (INIS)

Hladek, K.L.

1997-01-01

The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together

Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

Energy Technology Data Exchange (ETDEWEB)

Hladek, K.L.

1997-10-07

The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together

Hydrological balancing as applied to shallow ground disposal of radioactive wastes

International Nuclear Information System (INIS)

Kobera, P.; Dlouhy, Z.

1984-02-01

Shallow ground repositories are suitable disposal means for low and intermediate level radioactive wastes which offer an adequate form of containment of relatively short-lived radionuclides. The majority of safety related problems are connected with occurrence of water at the site. These problems include water accumulation in the disposal modules, high water table, hydrogeological complexity, water erosion, etc. In this context a simple technique is proposed for water balancing in the region of interest which would be relatively inexpensive and could supply large amounts of pertinent information. In the paper several balancing techniques based on water and/or energy balance methods are discussed. The results of a static evaluation of long term water balance averages are presented for the regions of planned shallow ground repositories near Dukovany and Mochovce in the CSSR. Hydrological processes and elements taking part in different hydrological cycles are treated from the dynamical point of view. The calculation methods for application of the kinematic approach are briefly touched. The results may be acquired at relatively low costs

Zebra mussel beds: an effective feeding ground for Ponto-Caspian gobies or suitable shelter for their prey?

Science.gov (United States)

Kobak, Jarosław; Poznańska, Małgorzata; Jermacz, Łukasz; Kakareko, Tomasz; Prądzynski, Daniel; Łodygowska, Małgorzata; Montowska, Karolina; Bącela-Spychalska, Karolina

2016-01-01

Aggregations of the Ponto-Caspian invasive zebra mussel ( Dreissena polymorpha ) constitute a suitable habitat for macroinvertebrates, considerably increasing their abundance and providing effective antipredator protection. Thus, the overall effect of a mussel bed on particular predator species may vary from positive to negative, depending on both prey density increase and predator ability to prey in a structurally complex habitat. Alien Ponto-Caspian goby fish are likely to be facilitated when introduced into new areas by zebra mussels, provided that they are capable of utilizing mussel beds as habitat and feeding grounds. We ran laboratory experiments to find which prey (chironomid larvae) densities (from ca. 500 to 2,000 individuals m -2 ) in a mussel bed make it a more beneficial feeding ground for the racer goby Babka gymnotrachelus (RG) and western tubenose goby Proterorhinus semilunaris (WTG) compared to sandy and stone substrata (containing the basic prey density of 500 ind. m -2 ). Moreover, we checked how food availability affects habitat selection by fish. Mussel beds became more suitable for fish than alternative mineral substrata when food abundance was at least two times higher (1,000 vs. 500 ind. m -2 ), regardless of fish size and species. WTG was associated with mussel beds regardless of its size and prey density, whereas RG switched to this habitat when it became a better feeding ground than alternative substrata. Larger RG exhibited a stronger affinity for mussels than small individuals. WTG fed more efficiently from a mussel bed at high food abundances than RG. A literature review has shown that increasing chironomid density, which in our study was sufficient to make a mussel habitat an attractive feeding ground for the gobies, is commonly observed in mussel beds in the field. Therefore, we conclude that zebra mussels may positively affect the alien goby species and are likely to facilitate their establishment in novel areas, contributing to an

Zebra mussel beds: an effective feeding ground for Ponto-Caspian gobies or suitable shelter for their prey?

Directory of Open Access Journals (Sweden)

Jarosław Kobak

2016-11-01

Full Text Available Aggregations of the Ponto-Caspian invasive zebra mussel (Dreissena polymorpha constitute a suitable habitat for macroinvertebrates, considerably increasing their abundance and providing effective antipredator protection. Thus, the overall effect of a mussel bed on particular predator species may vary from positive to negative, depending on both prey density increase and predator ability to prey in a structurally complex habitat. Alien Ponto-Caspian goby fish are likely to be facilitated when introduced into new areas by zebra mussels, provided that they are capable of utilizing mussel beds as habitat and feeding grounds. We ran laboratory experiments to find which prey (chironomid larvae densities (from ca. 500 to 2,000 individuals m−2 in a mussel bed make it a more beneficial feeding ground for the racer goby Babka gymnotrachelus (RG and western tubenose goby Proterorhinus semilunaris (WTG compared to sandy and stone substrata (containing the basic prey density of 500 ind. m−2. Moreover, we checked how food availability affects habitat selection by fish. Mussel beds became more suitable for fish than alternative mineral substrata when food abundance was at least two times higher (1,000 vs. 500 ind. m−2, regardless of fish size and species. WTG was associated with mussel beds regardless of its size and prey density, whereas RG switched to this habitat when it became a better feeding ground than alternative substrata. Larger RG exhibited a stronger affinity for mussels than small individuals. WTG fed more efficiently from a mussel bed at high food abundances than RG. A literature review has shown that increasing chironomid density, which in our study was sufficient to make a mussel habitat an attractive feeding ground for the gobies, is commonly observed in mussel beds in the field. Therefore, we conclude that zebra mussels may positively affect the alien goby species and are likely to facilitate their establishment in novel areas

Disposal of tritium-exposed metal hydrides

International Nuclear Information System (INIS)

Nobile, A.; Motyka, T.

1991-01-01

A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R ampersand D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed

Discharge of treated wastewater from drilling exploratory wells by infiltration of hydrocarbons in the ground

International Nuclear Information System (INIS)

Rodriguez Miranda, J. P.

2009-01-01

The discharge of treated waste water from a well drilling exploratory oil, such as the consideration ser out to determine the minimum area needed to saturate the ground is not where he planned the infiltration of the dumping in special conditions of soil type and permeability, limited space, water quality and influence of underground aquifers in the study area. (Author) 16 refs

The microelectronics and photonics test bed (MPTB) space, ground test and modeling experiments

International Nuclear Information System (INIS)

Campbell, A.

1999-01-01

This paper is an overview of the MPTB (microelectronics and photonics test bed) experiment, a combination of a space experiment, ground test and modeling programs looking at the response of advanced electronic and photonic technologies to the natural radiation environment of space. (author)

Control of water infiltration into near surface LLW disposal units-progress report on field experiments at a humid region site, Beltsville, Maryland

International Nuclear Information System (INIS)

O'Donnell, E.; Ridky, R.W.; Schulz, R.K.

1994-01-01

The study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters (75'x45'x10') at Beltsville, MD, and results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated. They are: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry into waste and without institutional care

Efficient expansion of mesenchymal stromal cells in a disposable fixed bed culture system.

Science.gov (United States)

Mizukami, Amanda; Orellana, Maristela D; Caruso, Sâmia R; de Lima Prata, Karen; Covas, Dimas T; Swiech, Kamilla

2013-01-01

The need for efficient and reliable technologies for clinical-scale expansion of mesenchymal stromal cells (MSC) has led to the use of disposable bioreactors and culture systems. Here, we evaluate the expansion of cord blood-derived MSC in a disposable fixed bed culture system. Starting from an initial cell density of 6.0 × 10(7) cells, after 7 days of culture, it was possible to produce of 4.2(±0.8) × 10(8) cells, which represents a fold increase of 7.0 (±1.4). After enzymatic retrieval from Fibra-Cell disks, the cells were able to maintain their potential for differentiation into adipocytes and osteocytes and were positive for many markers common to MSC (CD73, CD90, and CD105). The results obtained in this study demonstrate that MSC can be efficiently expanded in the culture system. This novel approach presents several advantages over the current expansion systems, based on culture flasks or microcarrier-based spinner flasks and represents a key element for MSC cellular therapy according to GMP compliant clinical-scale production system. Copyright © 2013 American Institute of Chemical Engineers.

Waste disposal into the ground

Energy Technology Data Exchange (ETDEWEB)

Mawson, C A

1955-07-01

The establishment of an atomic energy project is soon followed by the production of a variety of radioactive wastes which must be disposed of safely, quickly and cheaply. Experience has shown that much more thought has been devoted to the design of plant and laboratories than to the apparently dull problem of what to do with the wastes, but the nature of the wastes which will arise from nuclear power production calls for a change in this situation. We shall not be concerned here with power pile wastes, but disposal problems which have occurred in operation of experimental reactors have been serious enough to show that waste disposal should be considered during the early planning stages. (author)

Control of water infiltration into near surface LLW disposal units. Progress report on field experiments at a humid region site, Beltsville, Maryland: Volume 7

International Nuclear Information System (INIS)

Schulz, R.K.; Ridky, R.W.; O'Donnell, E.

1994-12-01

The project objective is to assess means for controlling waste infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large scale lysimeters (70 ft x 45 ft x 10 ft) at Beltsville, MD and results of the assessment are applicable to disposal of LLW, uranium mill tailings, hazardous waste, and sanitary landfills. Three concepts are under investigation: (1) resistive layer barrier, (2) conductive layer barrier, and bioengineering water management. The resistive layer barrier consists of compacted earth (clay). The conductive layer barrier is a special case of the capillary barrier and it requires a flow layer (e.g. fine sandy loam) over a capillary break. As long as unsaturated conditions are maintained water is conducted by the flow layer to below the waste. This barrier is most efficient at low flow rates and is thus best placed below a resistive layer barrier. Such a combination of the resistive layer over the conductive layer barrier promises to be highly effective provided there is no appreciable subsidence. Bioengineering water management is a surface cover that is designed to accommodate subsidence. It consists of impermeable panels which enhance run-off and limit infiltration. Vegetation is planted in narrow openings between panels to transpire water from below the panels. This system has successfully dewatered two lysimeters thus demonstrating that this procedure could be used for remedial action (drying out) existing water-logged disposal sites at low cost

Processes and parameters involved in modeling radionuclide transport from bedded salt repositories. Final report. Technical memorandum

International Nuclear Information System (INIS)

Evenson, D.E.; Prickett, T.A.; Showalter, P.A.

1979-07-01

The parameters necessary to model radionuclide transport in salt beds are identified and described. A proposed plan for disposal of the radioactive wastes generated by nuclear power plants is to store waste canisters in repository sites contained in stable salt formations approximately 600 meters below the ground surface. Among the principal radioactive wastes contained in these canisters will be radioactive isotopes of neptunium, americium, uranium, and plutonium along with many highly radioactive fission products. A concern with this form of waste disposal is the possibility of ground-water flow occurring in the salt beds and endangering water supplies and the public health. Specifically, the research investigated the processes involved in the movement of radioactive wastes from the repository site by groundwater flow. Since the radioactive waste canisters also generate heat, temperature is an important factor. Among the processes affecting movement of radioactive wastes from a repository site in a salt bed are thermal conduction, groundwater movement, ion exchange, radioactive decay, dissolution and precipitation of salt, dispersion and diffusion, adsorption, and thermomigration. In addition, structural changes in the salt beds as a result of temperature changes are important. Based upon the half-lives of the radioactive wastes, he period of concern is on the order of a million years. As a result, major geologic phenomena that could affect both the salt bed and groundwater flow in the salt beds was considered. These phenomena include items such as volcanism, faulting, erosion, glaciation, and the impact of meteorites. CDM reviewed all of the critical processes involved in regional groundwater movement of radioactive wastes and identified and described the parameters that must be included to mathematically model their behavior. In addition, CDM briefly reviewed available echniques to measure these parameters

Control of water infiltration into near surface LLW disposal units: Progress report on field experiments at a humid region site, Beltsville, Maryland

International Nuclear Information System (INIS)

Schulz, R.K.; Ridky, R.W.

1996-08-01

This study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (70 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care

Mine tailings disposal

International Nuclear Information System (INIS)

Gonzales, P.A.; Adams, B.J.

1980-06-01

The hydrologic evaluation of mine tailings disposal sites after they are abandoned is considered in relation to their potential environmental impact on a long term basis. There is a direct relation between the amounts and types of water leaving a disposal site and the severity of the potential damage to the environment. The evaluation of the relative distribution of the precipitation reaching the ground into evaporation, runoff and infiltration is obtained for a selected site and type of tailings material whose characteristics and physical properties were determined in the soils laboratory. A conceptual model of the hydrologic processes involved and the corresponding mathematical model were developed to simulate the physical system. A computer program was written to solve the set of equations forming the mathematical model, considering the physical properties of the tailings and the rainfall data selected. The results indicate that the relative distribution of the precipitation depends on the surface and upper layer of the tailings and that the position of the groundwater table is governed by the flow through the bottom of the profile considered. The slope of the surface of the mass of tailings was found to be one of the principal factors affecting the relative distribution of precipitation and, therefore, the potential pollution of the environment

Studies involving proposed waste disposal facilities in Turkey

International Nuclear Information System (INIS)

Uslu, I.; Fields, D.E.; Yalcintas, M.G.

1987-01-01

The Turkish government is in the process of planning two nuclear reactors in Turkey. The Turkish Atomic Energy Authority has been given the task of developing plans for improved control of low-level wastes (LLW) in Turkey. Principal sources of radioactive wastes are hospitals, research institutions, biological research centers, universities, industries, and two research reactors in Turkey. These wastes will be treated in a pilot water treatment facility located in Cekmece Nuclear Research and Training Center, Istanbul. In this temporary waste disposal facility, the wastes will be stored in 200-l concrete containers until the establishment of the permanent waste disposal sites in Turkey in 1990. The PRESTO-II (prediction of radiation effects from shallow trench operations) computer code has been applied for the general probable sites for LLW disposal in Turkey. The model is intended to serve as a non-site-specific screening model for assessing radionuclide transport, ensuring exposure, and health impacts to a static local population for a chosen time period, following the end of the disposal operation. The methodology that this code takes into consideration is versatile and explicitly considers infiltration and percolation of surface water into the trench, leaching of radionuclides, vertical and horizontal transport of radionuclides, and use of this contaminated ground water for farming, irrigation, and ingestion

Fluidized bed heat exchanger utilizing angularly extending heat exchange tubes

Science.gov (United States)

Talmud, Fred M.; Garcia-Mallol, Juan-Antonio

1980-01-01

A fluidized bed heat exchanger in which air is passed through a bed of particulate material containing fuel disposed in a housing. A steam/water natural circulation system is provided and includes a steam drum disposed adjacent the fluidized bed and a series of tubes connected at one end to the steam drum. A portion of the tubes are connected to a water drum and in the path of the air and the gaseous products of combustion exiting from the bed. Another portion of the tubes pass through the bed and extend at an angle to the upper surface of the bed.

Mineral sources of water and their influence on the safe disposal of radioactive wastes in bedded salt deposits

International Nuclear Information System (INIS)

Fallis, S.M.

1973-12-01

With the increased use of nuclear energy, there will be subsequent increases in high-level radioactive wastes such as Sr 90 , Cs 137 , and Pu 239 . Several agencies have considered the safest possible means to store or dispose of wastes in geologic environments such as underground storage in salt deposits, shale beds, abandoned dry mines, and in clay and shale pits. Salt deposits have received the most favorable attention because they exist in dry environments and because of other desirable properties of halite (its plasticity, gamma-ray shielding, heat dissipation ability, low mining cost, and worldwide abundance). Much work has been done on bedded salt deposits, particularly the Hutchinson Salt Member of the Wellington Formation at Lyons, Kansas. Salt beds heated by the decay of the radioactive wastes may release water by dehydration of hydrous minerals commonly present in evaporite sequences or water present in other forms such as fluid inclusions. More than 80 hydrous minerals are known to occur in evaporite deposits. The occurrences, total water contents (up to 63%) and dehydration temperatures (often less that 150 0 C) of these minerals are given. Since it is desirable to dispose of radioactive wastes in a dry environment, care must be taken that large quantities of water are not released through the heating of hydrous minerals. Seventy-four samples from four cores taken at Lyons, Kansas, were analyzed by x-ray diffraction. The minerals detected were halite, anhydrite, gypsum, polyhalite, dolomite, magnesite, quartz, feldspar, and the clay minerals illite, chlorite, kaolinite, vermiculite, smectite, mixed-layer clay, and corrensite (interstratified chlorite-vermiculite). Of these, gypsum, polyhalite and the clay minerals are all capable of releasing water when heated

Selection of Computer Codes for Shallow Land Waste Disposal in PPTA Serpong

International Nuclear Information System (INIS)

Syahrir

1996-01-01

Selection of Computer Codes for Shallow Land Waste Disposal in PPTA Serpong. Models and computer codes have been selected for safety assessment of near surface waste disposal facility. This paper provides a summary and overview of the methodology and codes selected. The methodology allows analyses of dose to individuals from offsite releases under normal conditions as well as on-site doses to inadvertent intruders. A demonstration in the case of shallow land waste disposal in Nuclear Research Establishment are in Serpong has been given for normal release scenario. The assessment includes infiltration of rainfall, source-term, ground water (well) and surface water transport, food-chain and dosimetry. The results show dose history of maximally exposed individuals. The codes used are VS2DT, PAGAN and GENII. The application of 1 m silt loam as a moisture barrier cover decreases flow in the disposal unit by a factor of 27. The selected radionuclides show variety of dose histories according to their chemical and physical characteristics and behavior in the environment

Low-Level Burial Grounds dangerous waste permit application: Request for exemption from lined trench requirements and from land disposal restrictions for residual liquid at 218-E-12B Burial Ground Trench 94

International Nuclear Information System (INIS)

1992-10-01

This document has been prepared and is being submitted to the respective agencies to satisfy three objectives of the US Department of Energy (DOE) Richland Field Office (DOE-RL) concerning Trench 94 of the 218-E-12B Burial Ground. The 218-E-12B Burial Ground is located in the 200 East Area of the Hanford Facility. Figure 1-1 shows the general location of the Hanford Site. The 218-E-12B Burial Ground is one of eight burial grounds included in the Low-Level Burial Grounds (LLBG), a treatment, storage and/or disposal (TSD) unit. Decommissioned, defueled naval submarine reactor compartments (SRCs) contain radioactivity caused by exposure of structural components to neutrons during normal operation of the submarines. After all the alternatives were evaluated in the US Department of the Navy 1984 environmental impact statement (EIS) (USN 1984), land burial of the SRCs was selected as the preferred disposal option. The SRCs currently are sent to Trench 94 of the 218-E-12B Burial Ground. In addition to radioactivity, the SRCs disposed in. The DOE-RL's three objectives in preparing and submitting this document are as follows. Request from Ecology an exemption from dangerous waste landfill liner and leachate collection and removal system (hereinafter referred to as liner/leachate system) requirements for Trench 94 of the 218-E-12B Burial Ground. Petition Ecology to exempt residual liquid in the SRCs from land disposal restrictions. Obtain EPA Region 10 review and comment on the request to Ecology for exemption from liner/leachate system requirements

Acceptance criteria for disposal of radioactive wastes in shallow ground and rock cavities

International Nuclear Information System (INIS)

1985-01-01

This document provides an overview of basic information related to waste acceptance criteria for disposal in shallow ground and rock cavity repositories, consisting of a discussion of acceptable waste types. The last item includes identification of those waste characteristics which may influence the performance of the disposal system and as such are areas of consideration for criteria development. The material is presented in a manner similar to a safety assessment. Waste acceptance criteria aimed at limiting the radiation exposure to acceptable levels are presented for each pathway. Radioactive wastes considered here are low-level radioactive wastes and intermediate-level radioactive wastes from nuclear fuel cycle operations and applications of radionuclides in research, medicine and industry

Using multiple bed load measurements: Toward the identification of bed dilation and contraction in gravel-bed rivers

Science.gov (United States)

Marquis, G. A.; Roy, A. G.

2012-02-01

This study examines bed load transport processes in a small gravel-bed river (Béard Creek, Québec) using three complementary methods: bed elevation changes between successive floods, bed activity surveys using tags inserted into the bed, and bed load transport rates from bed load traps. The analysis of 20 flood events capable of mobilizing bed material led to the identification of divergent results among the methods. In particular, bed elevation changes were not consistent with the bed activity surveys. In many cases, bed elevation changes were significant (1 to 2 times the D50) even if the bed surface had not been activated during the flood, leading to the identification of processes of bed dilation and contraction that occurred over 10% to 40% of the bed surface. These dynamics of the river bed prevent accurate derivation of bed load transport rates from topographic changes, especially for low magnitude floods. This paper discusses the mechanisms that could explain the dilation and contraction of particles within the bed and their implications in fluvial dynamics. Bed contraction seems to be the result of the winnowing of the fine sediments under very low gravel transport. Bed dilation seems to occur on patches of the bed at the threshold of motion where various processes such as fine sediment infiltration lead to the maintenance of a larger sediment framework volume. Both processes are also influenced by flood history and the initial local bed state and in turn may have a significant impact on sediment transport and morphological changes in gravel-bed rivers.

A Safety Case Approach for Deep Geologic Disposal of DOE HLW and DOE SNF in Bedded Salt - 13350

Energy Technology Data Exchange (ETDEWEB)

Sevougian, S. David [Advanced Nuclear Energy Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); MacKinnon, Robert J. [Advanced Nuclear Energy Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); Leigh, Christi D. [Defense Waste Management Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); Hansen, Frank D. [Geoscience Research and Applications Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States)

2013-07-01

The primary objective of this study is to investigate the feasibility and utility of developing a defensible safety case for disposal of United States Department of Energy (U.S. DOE) high-level waste (HLW) and DOE spent nuclear fuel (SNF) in a conceptual deep geologic repository that is assumed to be located in a bedded salt formation of the Delaware Basin [1]. A safety case is a formal compilation of evidence, analyses, and arguments that substantiate and demonstrate the safety of a proposed or conceptual repository. We conclude that a strong initial safety case for potential licensing can be readily compiled by capitalizing on the extensive technical basis that exists from prior work on the Waste Isolation Pilot Plant (WIPP), other U.S. repository development programs, and the work published through international efforts in salt repository programs such as in Germany. The potential benefits of developing a safety case include leveraging previous investments in WIPP to reduce future new repository costs, enhancing the ability to effectively plan for a repository and its licensing, and possibly expediting a schedule for a repository. A safety case will provide the necessary structure for organizing and synthesizing existing salt repository science and identifying any issues and gaps pertaining to safe disposal of DOE HLW and DOE SNF in bedded salt. The safety case synthesis will help DOE to plan its future R and D activities for investigating salt disposal using a risk-informed approach that prioritizes test activities that include laboratory, field, and underground investigations. It should be emphasized that the DOE has not made any decisions regarding the disposition of DOE HLW and DOE SNF. Furthermore, the safety case discussed herein is not intended to either site a repository in the Delaware Basin or preclude siting in other media at other locations. Rather, this study simply presents an approach for accelerated development of a safety case for a potential

A Safety Case Approach for Deep Geologic Disposal of DOE HLW and DOE SNF in Bedded Salt - 13350

International Nuclear Information System (INIS)

Sevougian, S. David; MacKinnon, Robert J.; Leigh, Christi D.; Hansen, Frank D.

2013-01-01

The primary objective of this study is to investigate the feasibility and utility of developing a defensible safety case for disposal of United States Department of Energy (U.S. DOE) high-level waste (HLW) and DOE spent nuclear fuel (SNF) in a conceptual deep geologic repository that is assumed to be located in a bedded salt formation of the Delaware Basin [1]. A safety case is a formal compilation of evidence, analyses, and arguments that substantiate and demonstrate the safety of a proposed or conceptual repository. We conclude that a strong initial safety case for potential licensing can be readily compiled by capitalizing on the extensive technical basis that exists from prior work on the Waste Isolation Pilot Plant (WIPP), other U.S. repository development programs, and the work published through international efforts in salt repository programs such as in Germany. The potential benefits of developing a safety case include leveraging previous investments in WIPP to reduce future new repository costs, enhancing the ability to effectively plan for a repository and its licensing, and possibly expediting a schedule for a repository. A safety case will provide the necessary structure for organizing and synthesizing existing salt repository science and identifying any issues and gaps pertaining to safe disposal of DOE HLW and DOE SNF in bedded salt. The safety case synthesis will help DOE to plan its future R and D activities for investigating salt disposal using a risk-informed approach that prioritizes test activities that include laboratory, field, and underground investigations. It should be emphasized that the DOE has not made any decisions regarding the disposition of DOE HLW and DOE SNF. Furthermore, the safety case discussed herein is not intended to either site a repository in the Delaware Basin or preclude siting in other media at other locations. Rather, this study simply presents an approach for accelerated development of a safety case for a potential

Internal dust recirculation system for a fluidized bed heat exchanger

Science.gov (United States)

Gamble, Robert L.; Garcia-Mallol, Juan A.

1981-01-01

A fluidized bed heat exchanger in which air is passed through a bed of particulate material containing fuel disposed in a housing. A steam/water natural circulation system is provided in a heat exchange relation to the bed and includes a steam drum disposed adjacent the bed and a tube bank extending between the steam drum and a water drum. The tube bank is located in the path of the effluent gases exiting from the bed and a baffle system is provided to separate the solid particulate matter from the effluent gases. The particulate matter is collected and injected back into the fluidized bed.

Application of spreadsheet to estimate infiltration parameters

OpenAIRE

Zakwan, Mohammad; Muzzammil, Mohammad; Alam, Javed

2016-01-01

Infiltration is the process of flow of water into the ground through the soil surface. Soil water although contributes a negligible fraction of total water present on earth surface, but is of utmost importance for plant life. Estimation of infiltration rates is of paramount importance for estimation of effective rainfall, groundwater recharge, and designing of irrigation systems. Numerous infiltration models are in use for estimation of infiltration rates. The conventional graphical approach ...

Effects of land disposal of municipal sewage sludge on soil, streambed sediment, and ground- and surface-water quality at a site near Denver, Colorado

Energy Technology Data Exchange (ETDEWEB)

Gaggiani, N.G.

1991-01-01

The report describes the effects of burial and land application of municipal sewage sludge on soil and streambed sediment and water quality in the underlying aquifers and surface water within and around the Lowry sewage-sludge-disposal area. The existing ground-water observation-well network at the disposal area was expanded for the study. Surface-water-sampling sites were selected so that runoff could be sampled from intense rainstorms or snowmelt. The sampling frequency for ground-water and surface-water runoff was changed from yearly to quarterly, and soil samples were collected. Four years of data were collected from 1984 to 1987 during the expanded monitoring program at the Lowry sewage-sludge-disposal area. These data, in addition to the data collected by the U.S. Geological Survey from 1981 to 1983, were used to determine effects of sewage-sludge-disposal on soil and streambed sediment and surface- and ground-water quality at the disposal area.

Observations on infiltration of silicon carbide compacts with an aluminium alloy

Science.gov (United States)

Asthana, R.; Rohatgi, P. K.

1992-01-01

The melt infiltration of ceramic particulates permits an opportunity to observe such fundamental materials phenomena as nucleation, dynamic wetting and growth in constrained environments. Experimental observations are presented on the infiltration behavior and matrix microstructures that form when porous compacts of platelet-shaped single crystals of alpha- (hexagonal) silicon carbide are infiltrated with a liquid 2014 Al alloy. The infiltration process involved counter gravity infiltration of suitably tamped and preheated compacts of silicon carbide platelets under an external pressure in a special pressure chamber for a set period, then by solidification of the infiltrant metal in the interstices of the bed at atmospheric pressure.

Stormwater infiltration and surface runoff pollution reduction performance of permeable pavement layers.

Science.gov (United States)

Niu, Zhi-Guang; Lv, Zhi-Wei; Zhang, Ying; Cui, Zhen-Zhen

2016-02-01

In this paper, the laboratory-scale permeable pavement layers, including a surface permeable brick layer, coarse sand bedding layers (thicknesses = 2, 3.5, and 5 cm), and single-graded gravel sub-base layers (thicknesses = 15, 20, 25, and 30 cm), were built to evaluate stormwater infiltration and surface runoff pollution reduction performance. And, the infiltration rate (I) and concentrations of suspended solids (SS), total phosphorus (TP), chemical oxygen demand (COD), ammonia nitrogen, and total nitrogen (TN) were measured under the simulated rainfall intensity of 72.4 mm/h over duration of 60 min. The results indicate that the thickness factor primarily influences the infiltration rate and pollutant removal rate. The highest steady infiltration rate was for surface brick layer 51.0 mm/h, for 5-cm sand bedding layer 32.3 mm/h, and for 30-cm gravel sub-base layer 42.3 mm/h, respectively. The SS average removal rate was relative higher (79.8 ∼ 98.6 %) for all layers due to the interception and filtration. The average removal rates of TP and COD were for surface layer 71.2 and 24.1 %, for 5-cm bedding layer 54.8 and 9.0 %, and for 20-cm sub-base layer 72.2 and 26.1 %. Ammonia nitrogen and TN cannot steadily be removed by layers according to the experiment results. The optimal thickness of bedding sands was 5 cm, and that of sub-base gravels was 20 ∼ 30 cm.

Ground-water hydrology and radioactive waste disposal at the Hanford Site

International Nuclear Information System (INIS)

Law, A.G.

1979-02-01

This paper is a summary of the hydrologic activities conducted at the Hanford Site as a part of the environmental protection effort. The Site encompasses 1,480 square kilometers in the arid, southeastern part of Washington State. Precipitation averages about 160 millimeters per year with a negligible amount, if any, recharging the water table, which is from 50 to 100 meters below the ground surface. An unconfined aquifer occurs in the upper and middle Ringold Formations. The lower Ringold Formation along with interbed and interflow zones in the Saddle Mountain and Wanapum basalts forms a confined aquifer system. A potential exists for the interconnection of the unconfined and confined aquifer systems, especially near Gable Mountain where the anticlinal ridge was eroded by the catastrophic floods of the ancestral Columbia River system. Liquid wastes from chemical processing operations have resulted in large quantities of processing and cooling water disposed to ground via ponds, cribs, and ditches. The ground-water hydrology program at Hanford is designed: (1) to define and quantify the ground-water flow systems, (2) to evaluate the impact of the liquid waste discharges on these flow systems, and (3) to predict the impact on the ground-water systems of changes in system inputs. This work is conducted through a drilling, sampling, testing, and modeling program

Control of water infiltration into near surface LLW disposal units - Progress report on field experiments at a humid region site, Beltsville, Maryland

Energy Technology Data Exchange (ETDEWEB)

O' Donnell, Edward [U.S. Nuclear Regulatory Commission, Washington, DC (United States); Ridky, Robert W [University of Maryland, College Park, MD (United States); Schulz, Robert K [University of California, Berkeley, CA (United States)

1992-07-01

The study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters (75x45x10') at Beltsville, MD, and results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated. They are: 1) resistive layer barrier, 2) conductive layer barrier, and 3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry into waste and without institutional care. As mentioned in the preceding paragraph, a bioengineering management cover might well be the cover of choice during tho active subsidence phase of a waste disposal unit. Some maintenance is required during that period. Final

Control of water infiltration into near surface LLW disposal units - Progress report on field experiments at a humid region site, Beltsville, Maryland

International Nuclear Information System (INIS)

O'Donnell, Edward; Ridky, Robert W.; Schulz, Robert K.

1992-01-01

The study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters (75x45x10') at Beltsville, MD, and results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated. They are: 1) resistive layer barrier, 2) conductive layer barrier, and 3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry into waste and without institutional care. As mentioned in the preceding paragraph, a bioengineering management cover might well be the cover of choice during tho active subsidence phase of a waste disposal unit. Some maintenance is required during that period. Final

Mineral sources of water and their influence on the safe disposal of radioactive wastes in bedded salt deposits

Energy Technology Data Exchange (ETDEWEB)

Fallis, S.M.

1973-12-01

With the increased use of nuclear energy, there will be subsequent increases in high-level radioactive wastes such as Sr/sup 90/, Cs/sup 137/, and Pu/sup 239/. Several agencies have considered the safest possible means to store or dispose of wastes in geologic environments such as underground storage in salt deposits, shale beds, abandoned dry mines, and in clay and shale pits. Salt deposits have received the most favorable attention because they exist in dry environments and because of other desirable properties of halite (its plasticity, gamma-ray shielding, heat dissipation ability, low mining cost, and worldwide abundance). Much work has been done on bedded salt deposits, particularly the Hutchinson Salt Member of the Wellington Formation at Lyons, Kansas. Salt beds heated by the decay of the radioactive wastes may release water by dehydration of hydrous minerals commonly present in evaporite sequences or water present in other forms such as fluid inclusions. More than 80 hydrous minerals are known to occur in evaporite deposits. The occurrences, total water contents (up to 63%) and dehydration temperatures (often less that 150/sup 0/C) of these minerals are given. Since it is desirable to dispose of radioactive wastes in a dry environment, care must be taken that large quantities of water are not released through the heating of hydrous minerals. Seventy-four samples from four cores taken at Lyons, Kansas, were analyzed by x-ray diffraction. The minerals detected were halite, anhydrite, gypsum, polyhalite, dolomite, magnesite, quartz, feldspar, and the clay minerals illite, chlorite, kaolinite, vermiculite, smectite, mixed-layer clay, and corrensite (interstratified chlorite-vermiculite). Of these, gypsum, polyhalite and the clay minerals are all capable of releasing water when heated.

An update of the distribution of selected radiochemical and chemical constituents in perched ground water, Idaho National Laboratory, Idaho, Emphasis 1999-2001

Science.gov (United States)

Davis, Linda C.

2006-01-01

Radiochemical and chemical wastes generated at facilities at the Idaho National Laboratory (INL) were discharged since 1952 to infiltration ponds at the Reactor Technology Complex (RTC) (known as the Test Reactor Area [TRA] until 2005), and the Idaho Nuclear Technology and Engineering Center (INTEC) and buried at the Radioactive Waste Management Complex (RWMC). Disposal of wastewater to infiltration ponds and infiltration of surface water at waste burial sites resulted in formation of perched ground water in basalts and in sedimentary interbeds above the Snake River Plain aquifer. Perched ground water is an integral part of the pathway for waste-constituent migration to the aquifer. The U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, maintains ground-water monitoring networks at the INL to determine hydrologic trends, and to monitor the movement of radiochemical and chemical constituents in wastewater discharged from facilities to both perched ground water and the aquifer. This report presents an analysis of water-quality and water-level data collected from wells completed in perched ground water at the INL during 1999-2001, and summarizes historical disposal data and water-level-and water-quality trends. At the RTC, tritium, strontium-90, cesium-137, dissolved chromium, chloride, sodium, and sulfate were monitored in shallow and deep perched ground water. In shallow perched ground water, no tritium was detected above the reporting level. In deep perched ground water, tritium concentrations generally decreased or varied randomly during 1999-2001. During October 2001, tritium concentrations ranged from less than the reporting level to 39.4?1.4 picocuries per milliliter (pCi/mL). Reportable concentrations of tritium during July-October 2001 were smaller than the reported concentrations measured during July-December 1998. Tritium concentrations in water from wells at the RTC were likely affected by: well's distance from the

Final closure of a low level waste disposal facility

International Nuclear Information System (INIS)

Potier, J.M.

1995-01-01

The low-level radioactive waste disposal facility operated by the Agence Nationale pour la Gestion des Dechets Radioactifs near La Hague, France was opened in 1969 and is scheduled for final closure in 1996. The last waste package was received in June 1994. The total volume of disposed waste is approximately 525,000 m 3 . The site closure consists of covering the disposal structures with a multi-layer impervious cap system to prevent rainwater from infiltrating the waste isolation system. A monitoring system has been set up to verify the compliance of infiltration rates with hydraulic performance objectives (less than 10 liters per square meter and per year)

The lessons learned from Andra's Experiences on the Leachate Collection System of the Surface Disposal Facility

International Nuclear Information System (INIS)

Chang, Keunpack; Na, Hanjeong; Lee, Joonho; Lee, Dongjae

2014-01-01

This paper is based on the lessons learned from Andra's experiences especially on the drainage system which are given in the references. This paper also presents key items which need to be looked into for the local design which might be adopted at the second phase of LILW disposal facility at Wolsong. It is widely known that Andra has demonstrated that low and intermediate level of waste can be managed in a safe and efficient manner and disposed of surface level of ground. This paper has reviewed upgraded. EBSs evolved by Andra's many years of experiences, especially the measures to deal with drainage system which is available information online published to the public. Andra's Centre de I'Aube has been used as a reference model for the surface disposal of radioactive waste by many countries worldwide. But, the detail design of this type of facility needs to be improved and developed suitably for local characteristics taking into account the radioactive waste properties, local site environment and regulatory requirements in each country. The main design scenario to handle radioactive material in surface or near-surface radioactive nuclides are leached from waste by dissolving into rainwater passed through the disposal cover and concrete slab, and the infiltrated rainwater with radioactive nuclides flows to the aquifer through the concrete slab, and the infiltrated rainwater with radioactive nuclides flows to the aquifer through the concrete mat and the vadose zone, finally they are reached east sea through the aquifer or fault zone according to the hydro-geological characteristics of the site. The design concept to tackle this scenario and to deal with infiltrated and rain water in the surface disposal facility is described herein

A rapid screening-level method to optimize location of infiltration ponds.

Science.gov (United States)

Fennemore, G G; Davis, A; Goss, L; Warrick, A W

2001-01-01

A rapid-screening technique was developed to identify lithologies that best disperse artificial recharge via surface infiltration and minimize effects on ground water chemistry. The technique prospectively evaluates basin infiltration rates and water chemistry influences by integrating geotechnical, hydraulic, and water quality data with column test data and numerical modeling. The technique was validated using field data collected from surface infiltration basins designed to recharge ground water pumped from the Pipeline pit gold mine in Nevada. Observed recharge rates at these infiltration sites correlated most significantly with depth to groundwater, with basins in coarse-grained lithologies performing better (0.45 to 0.85 m/day) than those with fine-grained layers ( 2000 mg/L) than coarse-grained soils (infiltration basins for a variety of lithologies. Sites for infiltration basins can be rapidly screened to include areas with greatest depth to groundwater and in coarsest alluvial sediments, and impact to ground water chemistry can be reliably predicted using computer modeling and column test results.

Control of water infiltration into near surface LLW disposal units. Progress report on field experiments at a humid region site, Beltsville, Maryland: Volume 8

International Nuclear Information System (INIS)

Schulz, R.K.; Ridky, R.W.

1995-04-01

This study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (75 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care

Estimates of relative areas for the disposal in bedded salt of LWR wastes from alternative fuel cycles

International Nuclear Information System (INIS)

Lincoln, R.C.; Larson, D.W.; Sisson, C.E.

1978-01-01

The relative mine-level areas (land use requirements) which would be required for the disposal of light-water reactor (LWR) radioactive wastes in a hypothetical bedded-salt formation have been estimated. Five waste types from alternative fuel cycles have been considered. The relative thermal response of each of five different site conditions to each waste type has been determined. The fuel cycles considered are the once-through (no recycle), the uranium-only recycle, and the uranium and plutonium recycle. The waste types which were considered include (1) unreprocessed spent reactor fuel, (2) solidified waste derived from reprocessing uranium oxide fuel, (3) plutonium recovered from reprocessing spent reactor fuel and doped with 1.5% of the accompanying waste from reprocessing uranium oxide fuel, (4) waste derived from reprocessing mixed uranium/plutonium oxide fuel in the third recycle, and (5) unreprocessed spent fuel after three recycles of mixed uranium/plutonium oxide fuels. The relative waste-disposal areas were determined from a calculated value of maximum thermal energy (MTE) content of the geologic formations. Results are presented for each geologic site condition in terms of area ratios. Disposal area requirements for each waste type are expressed as ratios relative to the smallest area requirement (for waste type No. 2 above). For the reference geologic site condition, the estimated mine-level disposal area ratios are 4.9 for waste type No. 1, 4.3 for No. 3, 2.6 for No. 4, and 11 for No. 5

Sorption/ desorption studies of some radionuclides between disposal soil fractions and ground water. Vol. 3

Energy Technology Data Exchange (ETDEWEB)

El-Reefy, S A; Ali, A [Hot Lab. Centre, Atomic Energy Authority, Cairo (Egypt)

1996-03-01

The radioactive waste management program in egypt includes shallow land disposal area for waste package disposal. The proposed site is located to the east of the Hot laboratory centre at Inchas. Assessment of the efficiency of the different sediments and rocks found in this area as a barrier against release of radioactive nuclide to the environment is of major importance. This study is related to evaluate the migration of Cs, Co, and Am within the environment of this site. In this concern, seven soil fractions were taken from a digging well from the proposed disposal site at different depths down to the basalt sheets. A column was constructed containing the soil fractions representing the stratigraphic successions taken from the site. The radionuclides; Cs-137, Co-60, and Am-241 were in this investigation representatives for mono, di- and tri-valent elements and also represented the radionuclides which are mostly associated with radioactive wastes. The sorption/ desorption studies of these radionuclides with the different soil fractions and ground water from the proposed disposal site were carried out. The results obtained were used to predict the migration pathways of these radionuclides within the disposal environment. 2 figs., 1 tab.

Sorption/ desorption studies of some radionuclides between disposal soil fractions and ground water. Vol. 3

International Nuclear Information System (INIS)

El-Reefy, S.A.; Ali, A.

1996-01-01

The radioactive waste management program in egypt includes shallow land disposal area for waste package disposal. The proposed site is located to the east of the Hot laboratory centre at Inchas. Assessment of the efficiency of the different sediments and rocks found in this area as a barrier against release of radioactive nuclide to the environment is of major importance. This study is related to evaluate the migration of Cs, Co, and Am within the environment of this site. In this concern, seven soil fractions were taken from a digging well from the proposed disposal site at different depths down to the basalt sheets. A column was constructed containing the soil fractions representing the stratigraphic successions taken from the site. The radionuclides; Cs-137, Co-60, and Am-241 were in this investigation representatives for mono, di- and tri-valent elements and also represented the radionuclides which are mostly associated with radioactive wastes. The sorption/ desorption studies of these radionuclides with the different soil fractions and ground water from the proposed disposal site were carried out. The results obtained were used to predict the migration pathways of these radionuclides within the disposal environment. 2 figs., 1 tab

Disposal of radioactive waste material

International Nuclear Information System (INIS)

Cairns, W.J.; Burton, W.R.

1984-01-01

A method of disposal of radioactive waste consists in disposing the waste in trenches dredged in the sea bed beneath shallow coastal waters. Advantageously selection of the sites for the trenches is governed by the ability of the trenches naturally to fill with silt after disposal. Furthermore, this natural filling can be supplemented by physical filling of the trenches with a blend of absorber for radionuclides and natural boulders. (author)

MRI-guided and CT-guided cervical nerve root infiltration therapy. A cost comparison

Energy Technology Data Exchange (ETDEWEB)

Maurer, M.H.; Froeling, V.; Roettgen, R.; Bucourt, M. de; Hamm, B.; Streitparth, F. [Charite University Medicine Berlin (Germany). Dept. of Diagnostic and Interventional Radiology; Bretschneider, T. [Magdeburg Univ. (Germany). Dept. of Radiology and Nuclear Medicine; Hartwig, T.; Disch, A.C. [Charite University Medicine Berlin (Germany). Center for Musculoskeletal Surgery

2014-06-15

Purpose: To evaluate and compare the costs of MRI-guided and CT-guided cervical nerve root infiltration for the minimally invasive treatment of radicular neck pain. Materials and Methods: Between September 2009 and April 2012, 22 patients (9 men, 13 women; mean age: 48.2 years) underwent MRI-guided (1.0 Tesla, Panorama HFO, Philips) single-site periradicular cervical nerve root infiltration with 40 mg triamcinolone acetonide. A further 64 patients (34 men, 30 women; mean age: 50.3 years) were treated under CT fluoroscopic guidance (Somatom Definition 64, Siemens). The mean overall costs were calculated as the sum of the prorated costs of equipment use (purchase, depreciation, maintenance, and energy costs), personnel costs and expenditure for disposables that were identified for MRI- and CT-guided procedures. Additionally, the cost of ultrasound guidance was calculated. Results: The mean intervention time was 24.9 min. (range: 12-36 min.) for MRI-guided infiltration and 19.7 min. (range: 5-54 min.) for CT-guided infiltration. The average total costs per patient were EUR 240 for MRI-guided interventions and EUR 124 for CT-guided interventions. These were (MRI/CT guidance) EUR 150/60 for equipment use, EUR 46/40 for personnel, and EUR 44/25 for disposables. The mean overall cost of ultrasound guidance was EUR 76. Conclusion: Cervical nerve root infiltration using MRI guidance is still about twice as expensive as infiltration using CT guidance. However, since it does not involve radiation exposure for patients and personnel, MRI-guided nerve root infiltration may become a promising alternative to the CT-guided procedure, especially since a further price decrease is expected for MRI devices and MR-compatible disposables. In contrast, ultrasound remains the less expensive method for nerve root infiltration guidance. (orig.)

MRI-guided and CT-guided cervical nerve root infiltration therapy. A cost comparison

International Nuclear Information System (INIS)

Maurer, M.H.; Froeling, V.; Roettgen, R.; Bucourt, M. de; Hamm, B.; Streitparth, F.; Bretschneider, T.; Hartwig, T.; Disch, A.C.

2014-01-01

Purpose: To evaluate and compare the costs of MRI-guided and CT-guided cervical nerve root infiltration for the minimally invasive treatment of radicular neck pain. Materials and Methods: Between September 2009 and April 2012, 22 patients (9 men, 13 women; mean age: 48.2 years) underwent MRI-guided (1.0 Tesla, Panorama HFO, Philips) single-site periradicular cervical nerve root infiltration with 40 mg triamcinolone acetonide. A further 64 patients (34 men, 30 women; mean age: 50.3 years) were treated under CT fluoroscopic guidance (Somatom Definition 64, Siemens). The mean overall costs were calculated as the sum of the prorated costs of equipment use (purchase, depreciation, maintenance, and energy costs), personnel costs and expenditure for disposables that were identified for MRI- and CT-guided procedures. Additionally, the cost of ultrasound guidance was calculated. Results: The mean intervention time was 24.9 min. (range: 12-36 min.) for MRI-guided infiltration and 19.7 min. (range: 5-54 min.) for CT-guided infiltration. The average total costs per patient were EUR 240 for MRI-guided interventions and EUR 124 for CT-guided interventions. These were (MRI/CT guidance) EUR 150/60 for equipment use, EUR 46/40 for personnel, and EUR 44/25 for disposables. The mean overall cost of ultrasound guidance was EUR 76. Conclusion: Cervical nerve root infiltration using MRI guidance is still about twice as expensive as infiltration using CT guidance. However, since it does not involve radiation exposure for patients and personnel, MRI-guided nerve root infiltration may become a promising alternative to the CT-guided procedure, especially since a further price decrease is expected for MRI devices and MR-compatible disposables. In contrast, ultrasound remains the less expensive method for nerve root infiltration guidance. (orig.)

Ground-water flow and transport modeling of the NRC-licensed waste disposal facility, West Valley, New York

International Nuclear Information System (INIS)

Kool, J.B.; Wu, Y.S.

1991-10-01

This report describes a simulation study of groundwater flow and radionuclide transport from disposal at the NRC licensed waste disposal facility in West Valley, New York. A transient, precipitation driven, flow model of the near-surface fractured till layer and underlying unweathered till was developed and calibrated against observed inflow data into a recently constructed interceptor trench for the period March--May 1990. The results suggest that lateral flow through the upper, fractured till layer may be more significant than indicated by previous, steady state flow modeling studies. A conclusive assessment of the actual magnitude of lateral flow through the fractured till could however not be made. A primary factor contributing to this uncertainty is the unknown contribution of vertical infiltration through the interceptor trench cap to the total trench inflow. The second part of the investigation involved simulation of the migration of Sr-90, Cs-137 and Pu-239 from the one of the fuel hull disposal pits. A first-order radionuclide leach rate with rate coefficient of 10 -6 /day was assumed to describe radionuclide release into the disposal pit. The simulations indicated that for wastes buried below the fractured till zone, no significant migration would occur. However, under the assumed conditions, significant lateral migration could occur for radionuclides present in the upper, fractured till zone. 23 refs., 68 figs., 12 tabs

Method of ground disposal of radioactive waste

International Nuclear Information System (INIS)

Harashina, Heihachi.

1991-01-01

Rock bases are drilled to form a disposal hole, an overhanging hole and a burying hole each as a shaft. An appropriate number of canisters prepared by vitrification of high level radioactive wastes are charged in the disposal hole with a gap to the inner wall of the hole. Shock absorbers each made of bentonite are filled between each of the canisters and between the canister and the inner wall of the disposal hole, and the canisters are entirely covered with the layer of the shock absorbers. Further, plucking materials having water sealing property such as cement mortar are filled thereover. With such a constitution, in a case if water should intrude into the overhung portion, since the disposal hole is covered with the large flange portion in addition to the water sealing performance of the plucking, the shock absorbers and the canisters undergo no undesirable effects. Further, in a case if water should intrude to the disposal hole, the shock absorber layers are swollen by water absorption, to suppress the intrusion of water. (T.M.)

Oceanography related to deep sea waste disposal

International Nuclear Information System (INIS)

1978-09-01

In connection with studies on the feasibility of the safe disposal of radioactive waste, from a large scale nuclear power programme, either on the bed of the deep ocean or within the deep ocean bed, preparation of the present document was commissioned by the (United Kingdom) Department of the Environment. It attempts (a) to summarize the present state of knowledge of the deep ocean environment relevant to the disposal options and assess the processes which could aid or hinder dispersal of material released from its container; (b) to identify areas of research in which more work is needed before the safety of disposal on, or beneath, the ocean bed can be assessed; and (c) to indicate which areas of research can or should be undertaken by British scientists. The programmes of international cooperation in this field are discussed. The report is divided into four chapters dealing respectively with geology and geophysics, geochemistry, physical oceanography and marine biology. (U.K.)

A MODFLOW Infiltration Device Package for Simulating Storm Water Infiltration.

Science.gov (United States)

Jeppesen, Jan; Christensen, Steen

2015-01-01

This article describes a MODFLOW Infiltration Device (INFD) Package that can simulate infiltration devices and their two-way interaction with groundwater. The INFD Package relies on a water balance including inflow of storm water, leakage-like seepage through the device faces, overflow, and change in storage. The water balance for the device can be simulated in multiple INFD time steps within a single MODFLOW time step, and infiltration from the device can be routed through the unsaturated zone to the groundwater table. A benchmark test shows that the INFD Package's analytical solution for stage computes exact results for transient behavior. To achieve similar accuracy by the numerical solution of the MODFLOW Surface-Water Routing (SWR1) Process requires many small time steps. Furthermore, the INFD Package includes an improved representation of flow through the INFD sides that results in lower infiltration rates than simulated by SWR1. The INFD Package is also demonstrated in a transient simulation of a hypothetical catchment where two devices interact differently with groundwater. This simulation demonstrates that device and groundwater interaction depends on the thickness of the unsaturated zone because a shallow groundwater table (a likely result from storm water infiltration itself) may occupy retention volume, whereas a thick unsaturated zone may cause a phase shift and a change of amplitude in groundwater table response to a change of infiltration. We thus find that the INFD Package accommodates the simulation of infiltration devices and groundwater in an integrated manner on small as well as large spatial and temporal scales. © 2014, National Ground Water Association.

EFFECTIVENESS OF RECLAMATION OF SODA WASTE DISPOSAL SITE AT JANIKOWO USING SEWAGE SLUDGE

Directory of Open Access Journals (Sweden)

Jan Siuta

2014-10-01

Full Text Available There are numerous reclamation technologies based on sewage sludge treatment, however, one that is most purposeful consists in applying the sludge in order to achieve green cover (bioremediation with plants on fine grained waste disposal sites which have a high potential for soil formation on the one hand, but on the other, are highly vulnerable to erosive action of wind and atmospheric precipitation. The technological waste at the Janikowo Soda Plant has liquid consistence, contains fine-grained (dust-like and water soluble calcium compounds, and is highly alkaline and saline. The waste was disposed and dehydrated in the large-area earthen ponds elevated beyond the ground level. The combined surface of all the exploited settling ponds (with roads and escarpments jointly exceeds 105 ha. Dehydration by infiltration and evaporation was a source of unrestricted dust emissions from the drying and dry surfaces of the waste site. Urgent action was then deemed necessary to manage the high risk of nuisance dust to the local population, technical infrastructure, engines and cars. Consequently, it was decided that the best way to manage nuisance dust would be to create a thick and permanent vegetal cover on the waste site. The vegetal cover would also limit salt infiltration from the disposal site to groundwater and to adjacent agricultural land, and contribute to improving the local landscape values. Treatment with adequately high (appropriate for reclamation purposes doses of sewage sludge and sowing of plants which have a high growth potential and nutrient demand resulted in the quick establishment of green cover on the waste disposal site. The contents of mineral elements in plants and in the top layer of the ground reclaimed were analyzed starting from the year 2000 onwards until the year 2013. The chemical composition of sewage sludge was systematically analyzed as well. No excessive contents were found of main elements neither of heavy metals in

Effects Disposal Condition and Ground Water to Leaching Rate of Radionuclides from Solidification Products

International Nuclear Information System (INIS)

Herlan Martono; Wati

2008-01-01

Effects disposal condition and ground water to leaching rate of radionuclides from solidification products have been studied. The aims of leaching test at laboratory to get the best composition of solidified products for continuous process or handling. The leaching rate of radionuclides from the many kinds of matrix from smallest to bigger are glass, thermosetting plastic, urea formaldehyde, asphalt, and cement. Glass for solidification of high level waste, thermosetting plastic and urea formaldehyde for solidification of low and intermediate waste, asphalt and cement for solidification of low and intermediate level waste. In shallow land burial, ground water rate is fast, debit is high, and high permeability, so the probability contact between solidification products and ground water is occur. The pH of ground water increasing leaching rate, but cation in the ground water retard leaching rate. Effects temperature radiation and radiolysis to solidification products is not occur. In the deep repository, ground water rate is slow, debit is small, and low permeability, so the probability contact between solidification products and ground water is very small. There are effect cooling time and distance between pits to rock temperature. Alfa radiation effects can be occur, but there is no contact between solidification products and ground water, so that there is not radiolysis. (author)

Disposable products in the hospital waste stream.

OpenAIRE

Gilden, D. J.; Scissors, K. N.; Reuler, J. B.

1992-01-01

Use of disposable products in hospitals continues to increase despite limited landfill space and dwindling natural resources. We analyzed the use and disposal patterns of disposable hospital products to identify means of reducing noninfectious, nonhazardous hospital waste. In a 385-bed private teaching hospital, the 20 disposable products of which the greatest amounts (by weight) were purchased, were identified, and total hospital waste was tabulated. Samples of trash from three areas were so...

The effect of liner hydraulic conductivity on disposal cell performance

International Nuclear Information System (INIS)

Yu, C.; Yuan, Y.C.; Chia, Y.P.

1988-01-01

Multilayered disposal cells are frequently used for the disposal of radioactive and hazardous wastes. These disposal cells consist of materials with different permeabilities that are placed in various thicknesses at the bottom as well as in the cover of the cell. Typically, a layer of permeable material is placed above a layer with low permeability; the permeable layer functions as a drainage/leachate collection system and the low-permeability layer functions as a migration barrier/liner. This paper analyzes the effects of infiltration through unsaturated soil liners on the long-term performance of the disposal cell. Based on the results of this study, it is concluded that the long-term performance of a disposal cell is dependent on a well-designed cell cover. The design should emphasize a cap with less permeable material to prevent water from infiltrating the disposal cell. An impermeable bottom liner is effective only in the short term; however, it can eventually result in saturation of the wastes and cause the bathtub effect over the long term

Computer simulation of an internally pressurized radioactive waste disposal room in a bedded salt formation

International Nuclear Information System (INIS)

Brown, W.T.; Weatherby, J.R.

1991-01-01

The Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico was created by the U.S. Department of Energy as an underground research and development facility to demonstrate the safe storage of transuranic waste generated from defense activities. This facility consists of storage rooms mined from a bedded salt formation at a depth of about 650 meters. Each room will accommodate about 6800 55-gallon drums filled with waste. After waste containers are emplaced, the storage rooms are to be backfilled with mined salt or other backfill materials. As time passes, reconsolidation of this backfill will reduce the hydraulic conductivity of the room. However, gases produced by decomposition and corrosion of waste and waste containers may cause a slow build-up of pressure which can retard consolidation of the waste and backfilled salt. The authors have developed a finite-element model of an idealized disposal room which is assumed to be perfectly sealed. The assumption that no gas escapes from the disposal room is a highly idealized and extreme condition which does not account for leakage paths, such as interbeds, that exist in the surrounding salt formation. This model has been used in a parametric study to determine how reconsolidation is influenced by various assumed gas generation rates and total amounts of gas generated. Results show that reductions in the gas generation, relative to the baseline case, can increase the degree of consolidation and reduce the peak gas pressure in disposal rooms. Even higher degrees of reconsolidation can be achieved by reducing both amounts and rates of gas generation. 8 refs., 4 figs., 1 tab

Seepage patterns of Diuron in a ditch bed during a sequence of flood events

International Nuclear Information System (INIS)

Dages, C.; Samouëlian, A.; Negro, S.; Storck, V.; Huttel, O.; Voltz, M.

2015-01-01

Although ditches limit surface water contamination, groundwater recharge through ditches in Mediterranean catchments may result in groundwater contamination. We analysed the dynamics of pesticide percolation in ditches by conducting an original lab experiment that mimicked the successive percolation processes that occur during a flood season. Nine successive percolation events were operated on an undisturbed soil column collected from a ditch bed. The infiltrating water was doped with 14 C-Diuron at concentrations that were chosen to decrease between the events so as to correspond to values observed during actual flood events. The water and solute fluxes were monitored during each event, and the final extractable and non-extractable Diuron residues in the column were determined. Two main observations were made. First, a high leaching potential was observed through the ditch bed over a succession of infiltrating flood events, with 58.9% of the infiltrated Diuron and its metabolites leaching. Second, compared with the contamination of surface water circulating in the ditches, the contamination of seepage water exhibited smaller peak values and persisted much longer because of the desorption of Diuron residues stored in the ditch bed. Thus, ditches serve as buffering zones between surface and groundwater. However, compared with field plots, ditches appear to be a preferential location for the percolation of pesticides into groundwater at the catchment scale. - Highlights: • Diuron percolation in a ditch bed during flood events was mimicked in a column setup. • Diuron percolation can represent up to 50% of the infiltrated Diuron. • The ditch bed exhibits a high buffering capacity due to its high sorption properties. • Contamination period of percolation water lasts longer than that of infiltrating water. • Diuron residues stored in ditch bed move deeper than in field topsoils.

Seepage patterns of Diuron in a ditch bed during a sequence of flood events

Energy Technology Data Exchange (ETDEWEB)

Dages, C., E-mail: cecile.dages@supagro.inra.fr; Samouëlian, A.; Negro, S.; Storck, V.; Huttel, O.; Voltz, M.

2015-12-15

Although ditches limit surface water contamination, groundwater recharge through ditches in Mediterranean catchments may result in groundwater contamination. We analysed the dynamics of pesticide percolation in ditches by conducting an original lab experiment that mimicked the successive percolation processes that occur during a flood season. Nine successive percolation events were operated on an undisturbed soil column collected from a ditch bed. The infiltrating water was doped with {sup 14}C-Diuron at concentrations that were chosen to decrease between the events so as to correspond to values observed during actual flood events. The water and solute fluxes were monitored during each event, and the final extractable and non-extractable Diuron residues in the column were determined. Two main observations were made. First, a high leaching potential was observed through the ditch bed over a succession of infiltrating flood events, with 58.9% of the infiltrated Diuron and its metabolites leaching. Second, compared with the contamination of surface water circulating in the ditches, the contamination of seepage water exhibited smaller peak values and persisted much longer because of the desorption of Diuron residues stored in the ditch bed. Thus, ditches serve as buffering zones between surface and groundwater. However, compared with field plots, ditches appear to be a preferential location for the percolation of pesticides into groundwater at the catchment scale. - Highlights: • Diuron percolation in a ditch bed during flood events was mimicked in a column setup. • Diuron percolation can represent up to 50% of the infiltrated Diuron. • The ditch bed exhibits a high buffering capacity due to its high sorption properties. • Contamination period of percolation water lasts longer than that of infiltrating water. • Diuron residues stored in ditch bed move deeper than in field topsoils.

A performance assessment methodology for high-level radioactive waste disposal in unsaturated, fractured tuff

International Nuclear Information System (INIS)

Gallegos, D.P.

1991-07-01

Sandia National Laboratories, has developed a methodology for performance assessment of deep geologic disposal of high-level nuclear waste. The applicability of this performance assessment methodology has been demonstrated for disposal in bedded salt and basalt; it has since been modified for assessment of repositories in unsaturated, fractured tuff. Changes to the methodology are primarily in the form of new or modified ground water flow and radionuclide transport codes. A new computer code, DCM3D, has been developed to model three-dimensional ground-water flow in unsaturated, fractured rock using a dual-continuum approach. The NEFTRAN 2 code has been developed to efficiently model radionuclide transport in time-dependent velocity fields, has the ability to use externally calculated pore velocities and saturations, and includes the effect of saturation dependent retardation factors. In order to use these codes together in performance-assessment-type analyses, code-coupler programs were developed to translate DCM3D output into NEFTRAN 2 input. Other portions of the performance assessment methodology were evaluated as part of modifying the methodology for tuff. The scenario methodology developed under the bedded salt program has been applied to tuff. An investigation of the applicability of uncertainty and sensitivity analysis techniques to non-linear models indicate that Monte Carlo simulation remains the most robust technique for these analyses. No changes have been recommended for the dose and health effects models, nor the biosphere transport models. 52 refs., 1 fig

Performance assessment for the disposal of low-level waste in the 200 West Area Burial Grounds

Energy Technology Data Exchange (ETDEWEB)

Wood, M.I.; Khaleel, R.; Rittmann, P.D.; Lu, A.H.; Finfrock, S.H.; DeLorenzo, T.H. [Westinghouse Hanford Co., Richland, WA (United States); Serne, R.J.; Cantrell, K.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-06-01

This document reports the findings of a performance assessment (PA) analysis for the disposal of solid low-level radioactive waste (LLW) in the 200 West Area Low-Level Waste Burial Grounds (LLBG) in the northwest corner of the 200 West Area of the Hanford Site. This PA analysis is required by US Department of Energy (DOE) Order 5820.2A (DOE 1988a) to demonstrate that a given disposal practice is in compliance with a set of performance objectives quantified in the order. These performance objectives are applicable to the disposal of DOE-generated LLW at any DOE-operated site after the finalization of the order in September 1988. At the Hanford Site, DOE, Richland Operations Office (RL) has issued a site-specific supplement to DOE Order 5820.2A, DOE-RL 5820.2A (DOE 1993), which provides additiona I ce objectives that must be satisfied.

Performance assessment for the disposal of low-level waste in the 200 West Area Burial Grounds

International Nuclear Information System (INIS)

Wood, M.I.; Khaleel, R.; Rittmann, P.D.; Lu, A.H.; Finfrock, S.H.; DeLorenzo, T.H.; Serne, R.J.; Cantrell, K.J.

1995-06-01

This document reports the findings of a performance assessment (PA) analysis for the disposal of solid low-level radioactive waste (LLW) in the 200 West Area Low-Level Waste Burial Grounds (LLBG) in the northwest corner of the 200 West Area of the Hanford Site. This PA analysis is required by US Department of Energy (DOE) Order 5820.2A (DOE 1988a) to demonstrate that a given disposal practice is in compliance with a set of performance objectives quantified in the order. These performance objectives are applicable to the disposal of DOE-generated LLW at any DOE-operated site after the finalization of the order in September 1988. At the Hanford Site, DOE, Richland Operations Office (RL) has issued a site-specific supplement to DOE Order 5820.2A, DOE-RL 5820.2A (DOE 1993), which provides additiona I ce objectives that must be satisfied

Pathway analysis for alternate low-level waste disposal methods

International Nuclear Information System (INIS)

Rao, R.R.; Kozak, M.W.; McCord, J.T.; Olague, N.E.

1992-01-01

The purpose of this paper is to evaluate a complete set of environmental pathways for disposal options and conditions that the Nuclear Regulatory Commission (NRC) may analyze for a low-level radioactive waste (LLW) license application. The regulations pertaining In the past, shallow-land burial has been used for the disposal of low-level radioactive waste. However, with the advent of the State Compact system of LLW disposal, many alternative technologies may be used. The alternative LLW disposal facilities include below- ground vault, tumulus, above-ground vault, shaft, and mine disposal This paper will form the foundation of an update of the previously developed Sandia National Laboratories (SNL)/NRC LLW performance assessment methodology. Based on the pathway assessment for alternative disposal methods, a determination will be made about whether the current methodology can satisfactorily analyze the pathways and phenomena likely to be important for the full range of potential disposal options. We have attempted to be conservative in keeping pathways in the lists that may usually be of marginal importance. In this way we can build confidence that we have spanned the range of cases likely to be encountered at a real site. Results of the pathway assessment indicate that disposal methods can be categorized in groupings based on their depth of disposal. For the deep disposal options of shaft and mine disposal, the key pathways are identical. The shallow disposal options, such as tumulus, shallow-land, and below-ground vault disposal also may be grouped together from a pathway analysis perspective. Above-ground vault disposal cannot be grouped with any of the other disposal options. The pathway analysis shows a definite trend concerning depth of disposal. The above-ground option has the largest number of significant pathways. As the waste becomes more isolated, the number of significant pathways is reduced. Similar to shallow-land burial, it was found that for all

Effectiveness of a ground-surface polymer membrane covering as a method for limiting infiltration into burial trenches at Maxey Flats, Kentucky

International Nuclear Information System (INIS)

Lyverse, M.A.

1987-01-01

The Maxey Flats Disposal Site (MFDS) was operated as a shallow land burial site for low-level radioactive wastes for a period of 14 years (1963-1977). In 1977, radionuclides were found to be migrating from a closed disposal trench into an adjacent newly constructed trench. This discovery prompted closure of the site. Over time, deterioration of the shale and clay cover on the trenches had resulted from subsidence due to the collapse of buried metallic containers and the decomposition of various organic wastes within the trenches. This subsidence increased infiltration of water into the trenches as surface water was retained over the waste in potholes and small ponds. Although infiltration rates to the waste increased, seepage rates of leachate out of the bottom and sides of the trenches were very slow due to the low permeability of surrounding native shale soils (average hydraulic conductivity 4 x 10 -3 ft/day). In 1981, a program was implemented to correct deficiencies and stabilize the site. This paper describes the effectiveness of one design method where a low permeable (hydraulic conductivity -9 ft/sec) polyvinylchloride membrane cover (PVC) 0.015 to 0.020 inches thick was placed over the burial trenches. The covers were installed over trenches beginning in the fall of 1981. Each trench is equipped with several sumps for the collection and removal of leachate. Water-level data were collected on sumps from five trenches during the study period May 1978 to October 1984, which spanned a period prior to and after installation of the PVC cover. 3 references, 4 figures, 1 table

Fluorine disposal processes for nuclear applications

International Nuclear Information System (INIS)

Netzer, W.D.

1977-01-01

A study was performed to determine the best method for disposing of waste fluorine in the effluent from a uranium oxide conversion facility. After reviewing the fluorine disposal literature and upon considering the nuclear safety constraints, it was determined that the two most promising processes were the fluidized alumina bed and the caustic scrubber. To obtain more design data for the latter process, a 3-stage, 5-in. I.D. spray tower was constructed and operated. This unit used a 10% potassium hydroxide solution at flows of 1.5 to 3 gpm and achieved a 90% fluorine efficiency at fluorine flowrates as high as 4 scfm. However, two toxic by-products, oxygen difluoride and nitroxy fluoride, were detected in the effluent gases. After considering the relative merits of both disposal processes, it is concluded that the fluidized bed is superior, especially if the contaminated waste material were salable

Fluorine disposal processes for nuclear applications

Energy Technology Data Exchange (ETDEWEB)

Netzer, W.D.

1977-04-08

A study was performed to determine the best method for disposing of waste fluorine in the effluent from a uranium oxide conversion facility. After reviewing the fluorine disposal literature and upon considering the nuclear safety constraints, it was determined that the two most promising processes were the fluidized alumina bed and the caustic scrubber. To obtain more design data for the latter process, a 3-stage, 5-in. I.D. spray tower was constructed and operated. This unit used a 10% potassium hydroxide solution at flows of 1.5 to 3 gpm and achieved a 90% fluorine efficiency at fluorine flowrates as high as 4 scfm. However, two toxic by-products, oxygen difluoride and nitroxy fluoride, were detected in the effluent gases. After considering the relative merits of both disposal processes, it is concluded that the fluidized bed is superior, especially if the contaminated waste material were salable.

Pilot-scale fluidized-bed combustor testing cofiring animal-tissue biomass with coal as a carcass disposal option

Energy Technology Data Exchange (ETDEWEB)

Bruce G. Miller; Sharon Falcone Miller; Elizabeth M. Fedorowicz; David W. Harlan; Linda A. Detwiler; Michelle L. Rossman [Pennsylvania State University, University Park, PA (United States). Energy Institute

2006-10-15

This study was performed to demonstrate the technical viability of cofiring animal-tissue biomass (ATB) in a coal-fired fluidized-bed combustor (FBC) as an option for disposing of specified risk materials (SRMs) and carcasses. The purpose of this study was to assess the technical issues of feeding/combusting ATB and not to investigate prion deactivation/pathogen destruction. Overall, the project successfully demonstrated that carcasses and SRMs can be cofired with coal in a bubbling FBC. Feeding ATB into the FBC did, however, present several challenges. Specifically, handling/feeding issues resulting from the small scale of the equipment and the extremely heterogeneous nature of the ATB were encountered during the testing. Feeder modifications and an overbed firing system were necessary. Through statistical analysis, it was shown that the ATB feed location had a greater effect on CO emissions, which were used as an indication of combustion performance, than the fuel type due to the feeding difficulties. Baseline coal tests and tests cofiring ATB into the bed were statistically indistinguishable. Fuel feeding issues would not be expected at the full scale since full-scale units routinely handle low-quality fuels. In a full-scale unit, the disproportionate ratio of feed line size to unit diameter would be eliminated thereby eliminating feed slugging. Also, the ATB would either be injected into the bed, thereby ensuring uniform mixing and complete combustion, or be injected directly above the bed with overfire air ports used to ensure complete combustion. Therefore, it is anticipated that a demonstration at the full scale, which is the next activity in demonstrating this concept, should be successful. As the statistical analysis shows, emissions cofiring ATB with coal would be expected to be similar to that when firing coal only. 14 refs., 5 figs., 6 tabs.

Risk methodology for geologic disposal of radioactive waste

International Nuclear Information System (INIS)

Cranwell, R.M.; Campbell, J.E.; Ortiz, N.R.; Guzowski, R.V.

1990-04-01

This report contains the description of a procedure for selecting scenarios that are potentially important to the isolation of high- level radioactive wastes in deep geologic formations. In this report, the term scenario is used to represent a set of naturally occurring and/or human-induced conditions that represent realistic future states of the repository, geologic systems, and ground-water flow systems that might affect the release and transport of radionuclides from the repository to humans. The scenario selection procedure discussed in this report is demonstrated by applying it to the analysis of a hypothetical waste disposal site containing a bedded-salt formation as the host medium for the repository. A final set of 12 scenarios is selected for this site. 52 refs., 48 figs., 5 tabs

Bacterial Colonization of Disposable Soft Contact Lenses Is Greater during Corneal Infiltrative Events than during Asymptomatic Extended Lens Wear

Science.gov (United States)

Sankaridurg, Padmaja R.; Sharma, Savitri; Willcox, Mark; Naduvilath, Thomas J.; Sweeney, Deborah F.; Holden, Brien A.; Rao, Gullapalli N.

2000-01-01

Microorganisms, especially gram-negative bacteria, are considered to play a role in the etiology of certain corneal infiltrative events (CIEs) observed during soft contact lens wear. This study explored the possibility of microbial colonization of soft contact lenses as a risk factor leading to CIEs. In a clinical trial conducted from March 1993 to January 1996, 330 subjects wore disposable soft contact lenses on a 6-night extended-wear and disposal schedule. During this period, 4,321 lenses (118 during CIEs; 4,203 during asymptomatic lens wear) were recovered aseptically and analyzed for microbial colonization. A greater percentage of lenses were free from microbial colonization during asymptomatic wear than during CIEs (42 versus 23%; P bacteria, gram-negative bacteria and fungi was greater during CIEs than during asymptomatic lens wear (P bacteria were isolated most frequently and were usually normal external ocular microbiota. Of the gram-positive bacteria, the incidence of Streptococcus pneumoniae was greater during CIE than during asymptomatic wear (7.6 versus 0.6%; P bacteria were seen in few cases during asymptomatic wear, their incidence during CIE in comparison to asymptomatic wear was substantial and significant (23.7 versus 3.8%; P bacteria or S. pneumoniae. Colonization of soft contact lenses with pathogenic bacteria, especially gram-negative bacteria and S. pneumoniae, appears to be a significant risk factor leading to CIE. PMID:11101574

Panel session: Disposal of HLW - ready for implementation

International Nuclear Information System (INIS)

Heremans, R.; Come, B.; Barbreau, A.; Girardi, F.

1986-01-01

The paper is a report of a panel session at the European Community conference on radioactive waste management and disposal, Luxembourg 1985, concerning the safe and long-term disposal of high-activity and long-lived waste. The subjects discussed include: geological barriers including deep sea-bed sediments, engineered barriers, technological problems (repository construction, waste emplacement, backfilling and sealing), safety analysis, performance assessment of disposal system components, and finally institutional, legal and financial aspects of geological disposal. (U.K.)

Geology and coal-bed methane resources of the northern San Juan Basin, Colorado and New Mexico

International Nuclear Information System (INIS)

Fassett, J.E.

1988-01-01

This guidebook is the first of its kind: A focused look at coal-bed methane in a large Rocky Mountain Laramide basin. The papers in this volume cover every aspect of coal-bed methane in the San Juan Basin, including: The geology, environments of deposition, and geometry of the coal beds that contain the resource; the origin and migration history of the gas; basin-wide resource estimates; the engineering aspects of getting the gas out of the ground; the marketing and economics of producing coal-bed methane in the San Juan Basin; the legal ownership of the gas; state regulations governing well spacing and field rules; disposal of produced water; and land and mineral ownership patterns in the northern part of the basin. Also included are detailed papers on all of the major coal-bed methane fields in the basin, and in a paper on the history of Fruitland gas production, a discussion of most of the not-so-major fields. A small section of the book deals with geophysical methods, as yet still experimental, for surface detection of underground hydrocarbon resources. Individual papers have been processed separately for inclusion on the data base

Effects of waste-disposal practices on ground-water quality at five poultry (broiler) farms in north-central Florida, 1992-93

Science.gov (United States)

Hatzell, H.H.

1995-01-01

Waste-disposal areas such as chicken-house floors, litter stockpiles, fields that receive applications of litter, and dead-chicken pits are potential sources of nitrates and other chemical constituents in downward-percolating recharge water. Broiler- farms in north-central Florida are concentrated in a region where the Upper Floridan aquifer is unconfined and susceptible to contamination. Eighteen monitoring wells installed at five sites were sampled quarterly from March 1992 through January 1993. Increases in median concentrations of constituents relative to an upgradient well were used to determine the source of the nitrate at two sites. At these sites, increases in the median concentrations of nitrate as nitrogen in ground water in the vicinity of waste-disposal areas at these sites were: 5.4 mg/L for one chicken house; 9.0 mg/L for a second chicken house; 2.0 mg/L for a fallow field that received an application of litter; and, 2.0 mg/L for a dead-chicken pit. At the three remaining sites where the direction of local ground-water flow could not be ascertained, the sources of concentrations of nitrate and other constituents could not be determined. However, median nitrate concentrations in the vicinity of waste-disposal areas at these sites were: 45.5 mg/L for a set of two chicken houses; 3.0 mg/L for a stockpile area; and 2.1 mg/L for a hayfield that received an application of litter. The nitrate concentration in ground water in the vicinity of a field that had previously received heavy applications of litter increased from 3.0 mg/L to 105 mg/L approximately 4 months after receiving an application of commercial fertilizer. Increases in concentrations of organic nitrogen in ground water in the vicinity of waste-disposal areas may be related to the decomposition of litter and subsequent movement with downward percolating recharge water.(USGS)

Controlled disposal of domestic effluent sewage in the ground to reduce fecal coliforms

Directory of Open Access Journals (Sweden)

Paulo Fortes Neto

2008-12-01

Full Text Available The indiscriminate launching in water bodies of domestic sewage without treatment, or even treated, but without appropriate disinfection, contributes with significant amount of organisms of the called "coliform group” that can carry specific illnesses agents propagated through the water. The application of effluent in the ground, instead of direct disposal in water courses, in addition to being an alternative way for the disposal of residues and biological control of pollutants, constitutes an adequate way of nutrients supply to the soil and plants. So, this work had as objective the evaluation of the reduction of fecal coliforms, after controlled applications of 60 days treated effluent in cultivated soil, by analyzing the increase of fluorescent rhizobacterias Pseudomonas fluorescens and Bacillus spp. present in the rhizospheres of different crops. The experiment was developed in field conditions in the Experimental Farm of Department of Agrarian Sciences of the University of Taubaté, municipality of Taubaté, SP. The Experimental design consisted of random blocks, with five treatments including annual crops (Oats, Barley, Triticale - a cross between wheat and rye, Black Beans and non-cultivated soil as witness - blank reference and four repetitions, totalizing 20 ground plots with area of 2 m x 1 m with 50 cm space among plots on a Dystrophic Red-Yellow Latossol. Results from the microbial analyses of rhizosphere and non-rhizosphere soil indicated that the rhizosphere of oats had denser rhizobacterias than the other crops. However, the greatest efficiency was found in the reduction of thermo-tolerant coliforms for both black beans and non-cultivated soil.

Multi-offset ground-penetrating radar imaging of a lab-scale infiltration test

Directory of Open Access Journals (Sweden)

A. R. Mangel

2012-11-01

Full Text Available A lab scale infiltration experiment was conducted in a sand tank to evaluate the use of time-lapse multi-offset ground-penetrating radar (GPR data for monitoring dynamic hydrologic events in the vadose zone. Sets of 21 GPR traces at offsets between 0.44–0.9 m were recorded every 30 s during a 3 h infiltration experiment to produce a data cube that can be viewed as multi-offset gathers at unique times or common offset images, tracking changes in arrivals through time. Specifically, we investigated whether this data can be used to estimate changes in average soil water content during wetting and drying and to track the migration of the wetting front during an infiltration event. For the first problem we found that normal-moveout (NMO analysis of the GPR reflection from the bottom of the sand layer provided water content estimates ranging between 0.10–0.30 volumetric water content, which underestimated the value determined by depth averaging a vertical array of six moisture probes by 0.03–0.05 volumetric water content. Relative errors in the estimated depth to the bottom of the 0.6 m thick sand layer were typically on the order of 2%, though increased as high as 25% as the wetting front approached the bottom of the tank. NMO analysis of the wetting front reflection during the infiltration event generally underestimated the depth of the front with discrepancies between GPR and moisture probe estimates approaching 0.15 m. The analysis also resulted in underestimates of water content in the wetted zone on the order of 0.06 volumetric water content and a wetting front velocity equal to about half the rate inferred from the probe measurements. In a parallel modeling effort we found that HYDRUS-1D also underestimates the observed average tank water content determined from the probes by approximately 0.01–0.03 volumetric water content, despite the fact that the model was calibrated to the probe data. This error suggests that the assumed conceptual

Spatial and temporal infiltration dynamics during managed aquifer recharge.

Science.gov (United States)

Racz, Andrew J; Fisher, Andrew T; Schmidt, Calla M; Lockwood, Brian S; Los Huertos, Marc

2012-01-01

Natural groundwater recharge is inherently difficult to quantify and predict, largely because it comprises a series of processes that are spatially distributed and temporally variable. Infiltration ponds used for managed aquifer recharge (MAR) provide an opportunity to quantify recharge processes across multiple scales under semi-controlled conditions. We instrumented a 3-ha MAR infiltration pond to measure and compare infiltration patterns determined using whole-pond and point-specific methods. Whole-pond infiltration was determined by closing a transient water budget (accounting for inputs, outputs, and changes in storage), whereas point-specific infiltration rates were determined using heat as a tracer and time series analysis at eight locations in the base of the pond. Whole-pond infiltration, normalized for wetted area, rose rapidly to more than 1.0 m/d at the start of MAR operations (increasing as pond stage rose), was sustained at high rates for the next 40 d, and then decreased to less than 0.1 m/d by the end of the recharge season. Point-specific infiltration rates indicated high spatial and temporal variability, with the mean of measured values generally being lower than rates indicated by whole-pond calculations. Colocated measurements of head gradients within saturated soils below the pond were combined with infiltration rates to calculate soil hydraulic conductivity. Observations indicate a brief period of increasing saturated hydraulic conductivity, followed by a decrease of one to two orders of magnitude during the next 50 to 75 d. Locations indicating the most rapid infiltration shifted laterally during MAR operation, and we suggest that infiltration may function as a "variable source area" processes, conceptually similar to catchment runoff. © 2011, The Author(s). Ground Water © 2011, National Ground Water Association.

Effects on radionuclide concentrations by cement/ground-water interactions in support of performance assessment of low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Krupka, K.M.; Serne, R.J.

1998-05-01

The US Nuclear Regulatory Commission is developing a technical position document that provides guidance regarding the performance assessment of low-level radioactive waste disposal facilities. This guidance considers the effects that the chemistry of the vault disposal system may have on radionuclide release. The geochemistry of pore waters buffered by cementitious materials in the disposal system will be different from the local ground water. Therefore, the cement-buffered environment needs to be considered within the source term calculations if credit is taken for solubility limits and/or sorption of dissolved radionuclides within disposal units. A literature review was conducted on methods to model pore-water compositions resulting from reactions with cement, experimental studies of cement/water systems, natural analogue studies of cement and concrete, and radionuclide solubilities experimentally determined in cement pore waters. Based on this review, geochemical modeling was used to calculate maximum concentrations for americium, neptunium, nickel, plutonium, radium, strontium, thorium, and uranium for pore-water compositions buffered by cement and local ground-water. Another literature review was completed on radionuclide sorption behavior onto fresh cement/concrete where the pore water pH will be greater than or equal 10. Based on this review, a database was developed of preferred minimum distribution coefficient values for these radionuclides in cement/concrete environments

Effects on radionuclide concentrations by cement/ground-water interactions in support of performance assessment of low-level radioactive waste disposal facilities

Energy Technology Data Exchange (ETDEWEB)

Krupka, K.M.; Serne, R.J. [Pacific Northwest National Lab., Richland, WA (United States)

1998-05-01

The US Nuclear Regulatory Commission is developing a technical position document that provides guidance regarding the performance assessment of low-level radioactive waste disposal facilities. This guidance considers the effects that the chemistry of the vault disposal system may have on radionuclide release. The geochemistry of pore waters buffered by cementitious materials in the disposal system will be different from the local ground water. Therefore, the cement-buffered environment needs to be considered within the source term calculations if credit is taken for solubility limits and/or sorption of dissolved radionuclides within disposal units. A literature review was conducted on methods to model pore-water compositions resulting from reactions with cement, experimental studies of cement/water systems, natural analogue studies of cement and concrete, and radionuclide solubilities experimentally determined in cement pore waters. Based on this review, geochemical modeling was used to calculate maximum concentrations for americium, neptunium, nickel, plutonium, radium, strontium, thorium, and uranium for pore-water compositions buffered by cement and local ground-water. Another literature review was completed on radionuclide sorption behavior onto fresh cement/concrete where the pore water pH will be greater than or equal 10. Based on this review, a database was developed of preferred minimum distribution coefficient values for these radionuclides in cement/concrete environments.

Application of spreadsheet to estimate infiltration parameters

Directory of Open Access Journals (Sweden)

Mohammad Zakwan

2016-09-01

Full Text Available Infiltration is the process of flow of water into the ground through the soil surface. Soil water although contributes a negligible fraction of total water present on earth surface, but is of utmost importance for plant life. Estimation of infiltration rates is of paramount importance for estimation of effective rainfall, groundwater recharge, and designing of irrigation systems. Numerous infiltration models are in use for estimation of infiltration rates. The conventional graphical approach for estimation of infiltration parameters often fails to estimate the infiltration parameters precisely. The generalised reduced gradient (GRG solver is reported to be a powerful tool for estimating parameters of nonlinear equations and it has, therefore, been implemented to estimate the infiltration parameters in the present paper. Field data of infiltration rate available in literature for sandy loam soils of Umuahia, Nigeria were used to evaluate the performance of GRG solver. A comparative study of graphical method and GRG solver shows that the performance of GRG solver is better than that of conventional graphical method for estimation of infiltration rates. Further, the performance of Kostiakov model has been found to be better than the Horton and Philip's model in most of the cases based on both the approaches of parameter estimation.

Ground penetrating radar results at the Box Canyon Site - 1996 survey as part of infiltration test

International Nuclear Information System (INIS)

Peterson, J.E. Jr.; Williams, K.H.

1997-08-01

This data report presents a discussion of the borehole radar tomography experiment conducted at Box Canyon, Idaho. Discussion concentrates on the survey methodology, data acquisition procedures, and the resulting tomographic images and interpretations. The entire geophysics field effort for FY96 centered around the collection of the borehole radar data within the inclined boreholes R1, R2, R3, and R4 before, during, and after the ponded infiltration experiment. The well pairs R1-R2, R2-R4, and R3-R4 comprised the bulk of the field survey; however, additional data were collected between vertical boreholes within and around the infiltration basin. The intent of the inclined boreholes was to allow access beneath the infiltration basin and to enhance the ability of the radar method to image both vertical and horizontal features where flow may dominate. This data report will concentrate on the inclined borehole data and the resulting tomograms. The borehole radar method is one in which modified ground penetrating radar antennas are lowered into boreholes and high frequency electromagnetic signals are transmitted through subsurface material to a receiving antenna. The transmitted signals may be represented as multiple raypaths crossing through the zone of interest. If sufficient raypaths are recorded, a tomographic image may be obtained through computer processing. The data normally recorded are signal amplitude versus time. The information extracted from such data includes the following: (a) the transit time which depends on the wave velocity, (b) the amplitude which depends on the wave attenuation, the dispersion which indicates a change in velocity and attenuation with frequency

Control of water infiltration into near surface LLW [low-level radioactive waste] disposal units

International Nuclear Information System (INIS)

Schulz, R.K.; Ridky, R.W.; O'Donnell, E.O.

1990-12-01

Three kinds of waste disposal unit covers a barriers to water infiltration are being investigated. They are: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g. clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained the conductive layer will wick water around the capillary break. Below grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry to waste and without institutional care. These various concepts are being assessed in six large (70ft x 45ft x 10ft each) lysimeters at Beltsville, Maryland. 6 refs., 20 figs.,

Impact Force Applied on the Spent Nuclear Fuel Disposal Canister that Accidentally Drops and Collides onto the Ground

International Nuclear Information System (INIS)

Kwon, Young Joo

2016-01-01

In this paper, a mathematical methodology was theoretically studied to obtain the impact force caused by the collision between rigid bodies. This theoretical methodology was applied to compute the impact force applied on the spent nuclear fuel disposal canister that accidentally drops and collides onto the ground. From this study, the impact force required to ensure a structurally safe canister design was theoretically formulated. The main content of the theoretical study concerns the rigid body kinematics and equation of motion during collision between two rigid bodies. On the basis of this study, a general impact theory to compute the impact force caused by the collision between two bodies was developed. This general impact theory was applied to theoretically formulate the approximate mathematical solution of the impact force that affects the spent nuclear fuel disposal canister that accidentally falls to the ground. Simultaneously, a numerical analysis was performed using the computer code to compute the numerical solution of the impact force, and the numerical result was compared with the approximate mathematical solution

Preliminary estimates of spatially distributed net infiltration and recharge for the Death Valley region, Nevada-California

International Nuclear Information System (INIS)

Hevesi, J.A.; Flint, A.L.; Flint, L.E.

2002-01-01

A three-dimensional ground-water flow model has been developed to evaluate the Death Valley regional flow system, which includes ground water beneath the Nevada Test Site. Estimates of spatially distributed net infiltration and recharge are needed to define upper boundary conditions. This study presents a preliminary application of a conceptual and numerical model of net infiltration. The model was developed in studies at Yucca Mountain, Nevada, which is located in the approximate center of the Death Valley ground-water flow system. The conceptual model describes the effects of precipitation, runoff, evapotranspiration, and redistribution of water in the shallow unsaturated zone on predicted rates of net infiltration; precipitation and soil depth are the two most significant variables. The conceptual model was tested using a preliminary numerical model based on energy- and water-balance calculations. Daily precipitation for 1980 through 1995, averaging 202 millimeters per year over the 39,556 square kilometers area of the ground-water flow model, was input to the numerical model to simulate net infiltration ranging from zero for a soil thickness greater than 6 meters to over 350 millimeters per year for thin soils at high elevations in the Spring Mountains overlying permeable bedrock. Estimated average net infiltration over the entire ground-water flow model domain is 7.8 millimeters per year. To evaluate the application of the net-infiltration model developed on a local scale at Yucca Mountain, to net-infiltration estimates representing the magnitude and distribution of recharge on a regional scale, the net-infiltration results were compared with recharge estimates obtained using empirical methods. Comparison of model results with previous estimates of basinwide recharge suggests that the net-infiltration estimates obtained using this model may overestimate recharge because of uncertainty in modeled precipitation, bedrock permeability, and soil properties for

Radionuclide migration in ground water at a low-level waste disposal site: a comparison of predicted radionuclide transport modeling versus field observations

International Nuclear Information System (INIS)

Bergeron, M.P.; Robertson, D.E.; Champ, D.R.; Killey, R.W.D.; Moltyaner, G.L.

1987-01-01

At the Chalk River Nuclear Laboratories (CRNL), in Ontario, Canada, a number of LLW shallow-land burial facilities have existed for 25-30 years. These facilities are useful for testing the concept of site modelability. In 1984, CRNL and the Pacific Northwest Laboratory (PNL) established a cooperative research program to examine two disposal sites having plumes of slightly contaminated ground water for study. This report addresses the LLW Nitrate Disposal Pit site, which received liquid wastes containing approximately 1000-1500 curies of mixed fission products during 1953-54. The objective of this study is to test the regulatory requirement that a site be modeled and to use the Nitrate Disposal Pit site as a field site for testing the reliability of models in predicting radionuclide movement in ground water. The study plan was to approach this site as though it were to be licensed under the requirements of 10 CFR 61. Under the assumption that little was known about this site, a characterization plan was prepared describing the geologic, hydrologic, and geochemical information needed to assess site performance. After completion of the plan, site data generated by CRNL were selected to fill the plan data requirements. This paper describes the site hydrogeology, modeling of ground water flow, the comparison of observed and predicted radionuclide movement, and summarizes the conclusions and recommendations. 3 references, 10 figures

A study of Ground Source Heat Pump based on a heat infiltrates coupling model established with FEFLOW

Science.gov (United States)

Chen, H.; Hu, C.; Chen, G.; Zhang, Q.

2017-12-01

Geothermal heat is a viable source of energy and its environmental impact in terms of CO2 emissions is significantly lower than conventional fossil fuels. it is vital that engineers acquire a proper understanding about the Ground Source Heat Pump (GSHP). In this study, the model of the borehole exchanger under conduction manners and heat infiltrates coupling manners was established with FEFLOW. The energy efficiency, heat transfer endurance and heat transfer in the unit depth were introduced to quantify the energy efficient and the endurance period. The performance of a the Borehole Exchanger (BHE) in soil with and without groundwater seepage was analyzed of heat transfer process between the soil and the working fluid. Basing on the model, the varied regularity of energy efficiency performance an heat transfer endurance with the conditions including the different configuration of the BHE, the soil properties, thermal load characteristic were discussed. Focus on the heat transfer process in multi-layer soil which one layer exist groundwater flow. And an investigation about thermal dispersivity was also analyzed its influence on heat transfer performance. The final result proves that the model of heat infiltrates coupling model established in this context is reasonable, which can be applied to engineering design.

Analysis of Ship Groundings on Soft Sea Beds

DEFF Research Database (Denmark)

Simonsen, Bo Cerup; Pedersen, Preben Terndrup

1997-01-01

it influences the ship heave and pitch motions as well as the friction between the ship and the soil.In this paper a rational calculation model is presented for the sea bed soil reaction forces on the ship bottom. The model is based on the assumption that the penetration of the ship bow generates a flow of pore......The consequences associated with ships running aground depend very much on the soil characteristics of the sea bed and the geometrical shape of the ship bow. The penetration into the sea bed depends on these factors and the penetration is an important factor for the ship motion because...... by the theory of frictional soils in rupture. Frictional stresses on the bow surface are assumed to be related to the normal pressure by a simple Coulumb relation. The total soil reaction as a function of velocity and penetration is found by integration of normal pressure and frictional stresses over...

On the role of infiltration and exfiltration in swash zone boundary layer dynamics

Science.gov (United States)

Pintado-Patiño, José Carlos; Torres-Freyermuth, Alec; Puleo, Jack A.; Pokrajac, Dubravka

2015-09-01

Boundary layer dynamics are investigated using a 2-D numerical model that solves the Volume-Averaged Reynolds-Averaged Navier-Stokes equations, with a VOF-tracking scheme and a k - ɛ turbulence closure. The model is validated with highly resolved data of dam break driven swash flows over gravel impermeable and permeable beds. The spatial gradients of the velocity, bed shear stress, and turbulence intensity terms are investigated with reference to bottom boundary layer (BL) dynamics. Numerical results show that the mean vorticity responds to flow divergence/convergence at the surface that result from accelerating/decelerating portions of the flow, bed shear stress, and sinking/injection of turbulence due to infiltration/exfiltration. Hence, the zero up-crossing of the vorticity is employed as a proxy of the BL thickness inside the shallow swash zone flows. During the uprush phase, the BL develops almost instantaneously with bore arrival and fluctuates below the surface due to flow instabilities and related horizontal straining. In contrast, during the backwash phase, the BL grows quasi-linearly with less influence of surface-induced forces. However, the infiltration produces a reduction of the maximum excursion and duration of the swash event. These effects have important implications for the BL development. The numerical results suggest that the BL growth rate deviates rapidly from a quasi-linear trend if the infiltration is dominant during the initial backwash phase and the flat plate boundary layer theory may no longer be applicable under these conditions.

Fluidized bed and pulverized coal combustion residues for secondary pavements

International Nuclear Information System (INIS)

Ghafoori, N.; Diawara, H.; Wang, L.

2009-01-01

The United States produced nearly 125 million tons of coal combustion products in 2006. These by-products include fly ash, flue gas desulphurization materials, bottom ash, boiler slag, and other power plant by-products. The expense associated with waste disposal, lack of disposal sites, and significant environmental damage linked with the disposal of coal combustion residues have encouraged innovative utilization strategies such as the fluidized bed combustion (FBC) unit. This paper presented the results of a laboratory investigation that examined the properties of composites developed with different proportions of pre-conditioned FBC spent bed, pulverized coal combustion fly ash, natural fine aggregate, and Portland cement. The purpose of the study was to examine the extent to which the by-product composites could replace currently used materials in secondary roads. The paper presented the research objectives and experimental programs, including matrix constituent and proportions; mixture proportions; and mixing, curing, sampling, and testing. The discussion of results centered around compressive strength and expansion by internal sulfate attack. It was concluded that with proper proportioning, by-products of pulverized and fluidized bed combustion promote binding of sand particles and provide adequate strength under various curing and moisture conditions 4 refs., 6 tabs.

Salt disposal: Paradox Basin, Utah

International Nuclear Information System (INIS)

1983-04-01

This report presents the findings of a study conducted for the National Waste Terminal Storage (NWTS) Program. Permanent disposal options are examined for salt resulting from the excavation of a waste repository in the bedded salt deposits of the Paradox Basin of southeastern Utah. The study is based on a repository salt backfill compaction of 60% of the original density which leaves a total of 8 million tons of 95% pure salt to be disposed of over a 30-year period. The feasibility, impacts, and mitigation methods are examined for five options: commercial disposal, permanent onsite surface disposal, permanent offsite disposal, deepwell injection, and ocean and Great Salt Lake disposal. The study concludes the following: Commercial marketing of all repository salt would require a subsidy for transportation to major salt markets. Permanent onsite surface storage is both economically and technically feasible. Permanent offsite disposal is technically feasible but would incur additional transportation costs. Selection of an offsite location would provide a means of mitigating impacts associated with surface storage at the repository site. Deepwell injection is an attractive disposal method; however, the large water requirement, high cost of development, and poor performance of similar operating brine disposal wells eliminates this option from consideration as the primary means of disposal for the Paradox Basin. Ocean disposal is expensive because of high transportation cost. Also, regulatory approval is unlikely. Ocean disposal should be eliminated from further consideration in the Paradox Basin. Great Salt Lake disposal appears to be technically feasible. Great Salt Lake disposal would require state approval and would incur substantial costs for salt transportation. Permanent onsite disposal is the least expensive method for disposal of all repository salt

The combined use of chemical and isotopic information to model the effects of stormwater infiltration on groundwater quality in an urban fractured rock aquifer, Auckland, New Zealand

International Nuclear Information System (INIS)

Rosen, M.R.; Hong, Y.S.; Reeves, R.; Sheppard, D.; Roberts, K.; Viljevac, Z.; Smaill, A.

2002-01-01

Disposal of storm water in the Mt Eden area of Auckland, New Zealand, is via 'soak holes' drilled directly into the top of fractured basalt. Although this method of disposal has been used for at least 60 years, its sustainability with respect to groundwater quality has not been addressed. The groundwater has relatively low concentrations of dissolved heavy metals, although total metals are higher suggesting that the metals are bound to mobile particulates within the aquifer. PAH concentrations are also low in the aquifer, although sampling after rainfall events show small increases in PAH. Tritium measurements of the groundwater showed that all of the groundwater south of Chamberlin Park is less than 2 years old. This area has many soak holes. The data suggest that infiltration is very rapid and occurs throughout the area almost simultaneously after rainfall events. One well north of Chamberlin Park, where soak holes are absent has an age of 47 years ± 2 years. The groundwater here is low in dissolved oxygen and appears to be slow moving. CFC measurements indicate that all wells sampled south of Chamberlin Park are contaminated by excess CFCs. However, this result indicates rapid recharge from the surface via storm water. The same well north of Chamberlin Park that was dated using tritium, also has a CFC age of approximately 30 years. Thus, CFC dating may be useful in urban areas that are separated from atmospheric contamination by confining beds or slow circulation. A Kohonen self-organising feature maps (KSOFM) neural network was used to analyse the effect on storm water infiltration on groundwater quality, and determine the inter-relationship of the groundwater quality variables. The model shows that where the land use type is industrial or residential with many soak holes, there is a strong correlation of increased concentrations of heavy metals and storm water infiltration. (author)

Coal-bed methane water: effects on soil properties and camelina productivity

Science.gov (United States)

Every year the production of coal-bed natural gas in the Powder River Basin results in the discharge of large amounts of coal-bed methane water (CBMW) in Wyoming; however, no sustainable disposal methods for CBMW are currently available. A greenhouse study was conducted to evaluate the potential to ...

Annual Status Report (FY2015) Performance Assessment for the Disposal of Low-Level Waste in the 200 West Area Burial Grounds

Energy Technology Data Exchange (ETDEWEB)

Khaleel, R. [INTERA, Inc., Austin, TX (United States); Mehta, S. [CH2M Hill Plateau Remediation Company, Richland, WA (United States); Nichols, W. E. [CH2M Hill Plateau Remediation Company, Richland, WA (United States)

2016-02-01

This annual review provides the projected dose estimates of radionuclide inventories disposed in the active 200 West Area Low-Level Burial Grounds (LLBGs) since September 26, 1988. These estimates area calculated using the original does methodology developed in the performance assessment (PA) analysis (WHC-EP-0645).

Demonstration of a performance assessment methodology for high-level radioactive waste disposal in basalt formations

International Nuclear Information System (INIS)

Bonano, E.J.; Davis, P.A.; Shipers, L.R.; Brinster, K.F.; Beyler, W.E.; Updegraff, C.D.; Shepherd, E.R.; Tilton, L.M.; Wahi, K.K.

1989-06-01

This document describes a performance assessment methodology developed for a high-level radioactive waste repository mined in deep basalt formations. This methodology is an extension of an earlier one applicable to bedded salt. The differences between the two methodologies arise primarily in the modeling of round-water flow and radionuclide transport. Bedded salt was assumed to be a porous medium, whereas basalt formations contain fractured zones. Therefore, mathematical models and associated computer codes were developed to simulate the aforementioned phenomena in fractured media. The use of the methodology is demonstrated at a hypothetical basalt site by analyzing seven scenarios: (1) thermohydrological effects caused by heat released from the repository, (2) mechanohydrological effects caused by an advancing and receding glacier, (3) normal ground-water flow, (4) pumping of ground water from a confined aquifer, (5) rerouting of a river near the repository, (6) drilling of a borehole through the repository, and (7) formation of a new fault intersecting the repository. The normal ground-water flow was considered the base-case scenario. This scenario was used to perform uncertainty and sensitivity analyses and to demonstrate the existing capabilities for assessing compliance with the ground-water travel time criterion and the containment requirements. Most of the other scenarios were considered perturbations of the base case, and a few were studied in terms of changes with respect to initial conditions. The potential impact of these scenarios on the long-term performance of the disposal system was ascertained through comparison with the base-case scenario or the undisturbed initial conditions. 66 refs., 106 figs., 27 tabs

Stormwater infiltration and the 'urban karst' - A review

Science.gov (United States)

Bonneau, Jeremie; Fletcher, Tim D.; Costelloe, Justin F.; Burns, Matthew J.

2017-09-01

The covering of native soils with impervious surfaces (e.g. roofs, roads, and pavement) prevents infiltration of rainfall into the ground, resulting in increased surface runoff and decreased groundwater recharge. When this excess water is managed using stormwater drainage systems, flow and water quality regimes of urban streams are severely altered, leading to the degradation of their ecosystems. Urban streams restoration requires alternative approaches towards stormwater management, which aim to restore the flow regime towards pre-development conditions. The practice of stormwater infiltration-achieved using a range of stormwater source-control measures (SCMs)-is central to restoring baseflow. Despite this, little is known about what happens to the infiltrated water. Current knowledge about the impact of stormwater infiltration on flow regimes was reviewed. Infiltration systems were found to be efficient at attenuating high-flow hydrology (reducing peak magnitudes and frequencies) at a range of scales (parcel, streetscape, catchment). Several modelling studies predict a positive impact of stormwater infiltration on baseflow, and empirical evidence is emerging, but the fate of infiltrated stormwater remains unclear. It is not known how infiltrated water travels along the subsurface pathways that characterise the urban environment, in particular the 'urban karst', which results from networks of human-made subsurface pathways, e.g. stormwater and sanitary sewer pipes and associated high permeability trenches. Seepage of groundwater into and around such pipes is possible, meaning some infiltrated stormwater could travel along artificial pathways. The catchment-scale ability of infiltration systems to restore groundwater recharge and baseflow is thus ambiguous. Further understanding of the fate of infiltrated stormwater is required to ensure infiltration systems deliver optimal outcomes for waterway flow regimes.

Mixed artificial grasslands with more roots improved mine soil infiltration capacity

Science.gov (United States)

Wu, Gao-Lin; Yang, Zheng; Cui, Zeng; Liu, Yu; Fang, Nu-Fang; Shi, Zhi-Hua

2016-04-01

Soil water is one of the critical limiting factors in achieving sustainable revegetation. Soil infiltration capacity plays a vital role in determining the inputs from precipitation and enhancing water storage, which are important for the maintenance and survival of vegetation patches in arid and semi-arid areas. Our study investigated the effects of different artificial grasslands on soil physical properties and soil infiltration capacity. The artificial grasslands were Medicago sativa, Astragalus adsurgens, Agropyron mongolicum, Lespedeza davurica, Bromus inermis, Hedysarum scoparium, A. mongolicum + Artemisia desertorum, A. adsurgens + A. desertorum and M. sativa + B. inermis. The soil infiltration capacity index (SICI), which was based on the average infiltration rate of stage I (AIRSI) and the average infiltration rate of stage III (AIRS III), was higher (indicating that the infiltration capacity was greater) under the artificial grasslands than that of the bare soil. The SICI of the A. adsurgens + A. desertorum grassland had the highest value (1.48) and bare soil (-0.59) had the lowest value. It was evident that artificial grassland could improve soil infiltration capacity. We also used principal component analysis (PCA) to determine that the main factors that affected SICI were the soil water content at a depth of 20 cm (SWC20), the below-ground root biomasses at depths of 10 and 30 cm (BGB10, BGB30), the capillary porosity at a depth of 10 cm (CP10) and the non-capillary porosity at a depth of 20 cm (NCP20). Our study suggests that the use of Legume-poaceae mixtures and Legume-shrub mixtures to create grasslands provided an effective ecological restoration approach to improve soil infiltration properties due to their greater root biomasses. Furthermore, soil water content, below-ground root biomass, soil capillary porosity and soil non-capillary porosity were the main factors that affect the soil infiltration capacity.

Radiological protection criteria risk assessments for waste disposal options

International Nuclear Information System (INIS)

Hill, M.D.

1982-01-01

Radiological protection criteria for waste disposal options are currently being developed at the National Radiological Protection Board (NRPB), and, in parallel, methodologies to be used in assessing the radiological impact of these options are being evolved. The criteria and methodologies under development are intended to apply to all solid radioactive wastes, including the high-level waste arising from reprocessing of spent nuclear fuel (because this waste will be solidified prior to disposal) and gaseous or liquid wastes which have been converted to solid form. It is envisaged that the same criteria will be applied to all solid waste disposal options, including shallow land burial, emplacement on the ocean bed (sea dumping), geological disposal on land and sub-seabed disposal

Possible salt mine and brined cavity sites for radioactive waste disposal in the northeastern southern peninsula of Michigan

International Nuclear Information System (INIS)

Landes, K.K.; Bourne, H.L.

1976-01-01

A reconnaissance report on the possibilities for disposal of radioactive waste covers Michigan only, and is more detailed than an earlier one involving the northeastern states. Revised ''ground rules'' for pinpointing both mine and dissolved salt cavern sites for waste disposal include environmental, geologic, and economic factors. The Michigan basin is a structural bowl of Paleozoic sediments resting on downwarped Precambrian rocks. The center of the bowl is in Clare and Gladwin Counties, a short distance north of the middle of the Southern Peninsula. The strata dip toward this central area, and some stratigraphic sequences, including especially the salt-containing Silurian section, increase considerably in thickness in that direction. Lesser amounts of salt are also present in the north central part of the Lower Peninsula. Michigan has been an oil and gas producing state since 1925 and widespread exploration has had two effects on the selection of waste disposal sites: (1) large areas are leased for oil and gas; and (2) the borehole concentrations, whether producing wells, dry holes, or industrial brine wells that penetrated the salt section, should be avoided. Two types of nuclear waste, low level and high level, can be stored in man-made openings in salt beds. The storage facilities are created by (1) the development of salt mines where the depths are less than 3000 ft, and (2) cavities produced by pumping water into a salt bed, and bringing brine back out. The high level waste disposal must be confined to mines of limited depth, but the low level wastes can be accommodated in brine cavities at any depth. Seven potential prospects have been investigated and are described in detail

Home Sewage Disposal. Special Circular 212.

Science.gov (United States)

Wooding, N. Henry

This circular provides current information for homeowners who must repair or replace existing on-lot sewage disposal systems. Site requirements, characteristics and preparation are outlined for a variety of alternatives such as elevated sand mounds, sand-lined beds and trenches, and oversized absorption area. Diagrams indicating construction…

Fabrication of Cu-riched W–Cu composites by combustion synthesis and melt-infiltration in ultrahigh-gravity field

Energy Technology Data Exchange (ETDEWEB)

Zhao, Pei [Technical Institute of Physics and Chemistry, Chinese Academy of Sciences, Beijing 100190 (China); Graduate School of the Chinese Academy of Sciences, Beijing 100039 (China); Guo, Shibin; Liu, Guanghua; Chen, Yixiang [Technical Institute of Physics and Chemistry, Chinese Academy of Sciences, Beijing 100190 (China); Li, Jiangtao, E-mail: ljt0012@vip.sina.com [Technical Institute of Physics and Chemistry, Chinese Academy of Sciences, Beijing 100190 (China)

2013-10-15

Unadulterated Cu-riched W–Cu composites of W27–Cu73, W34–Cu66, W40–Cu60, W49–Cu51 and W56–Cu44 have been prepared by a novel method called combustion synthesis and melt-infiltration in ultrahigh-gravity field, of which W27–Cu73 and W34–Cu66 showed good ductility and W40–Cu60, W49–Cu51 and W56–Cu44 were brittle. In this technique, Cu melt accompanied with a great amount of heat was produced by thermit reaction and infiltrated into W–Cu powder bed. When the powder bed was Cu-riched powder bed such as W50–Cu50 or W60–Cu40, Cu melt would go through the powder bed, reach the bottom of the graphite crucible and then form a heat dissipation channel. Thus the cooling rate was so fast that the product was mixed up with impurity. The problem can be solved by putting some W powders under W50–Cu50 or W60–Cu40 powder bed to prevent the formation of heat dissipation channel.

Disposal of waste by hydraulic fracturing

International Nuclear Information System (INIS)

Tamura, T.; Weeren, H.

1984-01-01

Liquid radioactive waste solutions at the Oak Ridge National Laboratory (ORNL) have been disposed of for nearly 20 years by preparing a slurry, injecting it into bedding plane fractures formed in low-permeability shale, and allowing the slurry to set into a solid. Three major considerations are required for this method: a rock formation that forms horizontal or bedding plane fractures and is highly impermeable, a plant facility that can develop sufficient hydraulic pressure to fracture the rock and to inject the slurry, and a slurry that can be pumped into the fracture and that will set, preferably, into a low-leaching solid. The requirements and desirable conditions of the formation, the process and facility as used for radioactive waste disposal, and the mix formulation and slurry properties that were required for injection and solidification are described. The intent of this paper is to stimulate interest in this technique for possible application to nonnuclear wastes

Estimation of natural ground water recharge for the performance assessment of a low-level waste disposal facility at the Hanford Site

International Nuclear Information System (INIS)

Rockhold, M.L.; Fayer, M.J.; Kincaid, C.T.; Gee, G.W.

1995-03-01

In 1994, the Pacific Northwest Laboratory (PNL) initiated the Recharge Task, under the PNL Vitrification Technology Development (PVTD) project, to assist Westinghouse Hanford Company (WHC) in designing and assessing the performance of a low-level waste (LLW) disposal facility for the US Department of Energy (DOE). The Recharge Task was established to address the issue of ground water recharge in and around the LLW facility and throughout the Hanford Site as it affects the unconfined aquifer under the facility. The objectives of this report are to summarize the current knowledge of natural ground water recharge at the Hanford Site and to outline the work that must be completed in order to provide defensible estimates of recharge for use in the performance assessment of this LLW disposal facility. Recharge studies at the Hanford Site indicate that recharge rates are highly variable, ranging from nearly zero to greater than 100 mm/yr depending on precipitation, vegetative cover, and soil types. Coarse-textured soils without plants yielded the greatest recharge. Finer-textured soils, with or without plants, yielded the least. Lysimeters provided accurate, short-term measurements of recharge as well as water-balance data for the soil-atmosphere interface and root zone. Tracers provided estimates of longer-term average recharge rates in undisturbed settings. Numerical models demonstrated the sensitivity of recharge rates to different processes and forecast recharge rates for different conditions. All of these tools (lysimetry, tracers, and numerical models) are considered vital to the development of defensible estimates of natural ground water recharge rates for the performance assessment of a LLW disposal facility at the Hanford Site

Hanford's Radioactive Mixed Waste Disposal Facility

International Nuclear Information System (INIS)

McKenney, D.E.

1995-01-01

The Radioactive Mixed Waste Disposal Facility, is located in the Hanford Site Low-Level Burial Grounds and is designated as Trench 31 in the 218-W-5 Burial Ground. Trench 31 is a Resource Conservation and Recovery Act compliant landfill and will receive wastes generated from both remediation and waste management activities. On December 30, 1994, Westinghouse Hanford Company declared readiness to operate Trench 31, which is the Hanford Site's (and the Department of Energy complex's) first facility for disposal of low-level radioactive mixed wastes

‘Sticky business’: The influence of streambed periphyton on particle deposition and infiltration

Science.gov (United States)

Salant, Nira L.

2011-03-01

Strong feedbacks exist between physical and ecological components of aquatic systems. Aquatic plants can alter flow and sedimentation patterns, in turn influencing habitat condition and organism responses. In this study, I investigate the interactions between streambed periphyton, particle deposition and infiltration, and flow hydraulics to determine the influence of these organisms on the local environment. In a series of flume experiments, I measured the effects of two contrasting forms of periphyton at several densities and growth stages on near-bed hydraulics, particle loss from the water column, surface deposition, and subsurface infiltration. Data show that periphyton assemblages altered the rate and quantity of particle deposition via several mechanisms, including shear stress modification, surface adhesion, and bed clogging. Although trends varied for different size classes within a suspension of fine sediment, diatoms and algae had distinctly different effects on hydraulics, deposition, and infiltration. In general, diatoms increased the rate of decline in suspended particle concentrations relative to non-periphyton surfaces by reducing shear stresses and enhancing surface deposition via adhesion. Increases in diatom biomass, however, reduced the quantity and depth of particle infiltration, presumably by clogging interstitial pore spaces, in turn lowering rates of concentration decline. In contrast, all algal growth stages had slower or similar rates of concentration decline compared to non-periphyton conditions, due to partial clogging by high biomass and a lack of adhesion at the bed surface. Clogging effects were counteracted at later growth stages, however, as late-stage algal structures increased shear stresses and downward advection, in turn increasing amounts of infiltration. Compiled data from several field studies and experiments demonstrate a positive relation between periphyton biomass and inorganic mass, but also show a wide range in the

Estimated ground-water recharge from streamflow in Fortymile Wash near Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Savard, C.S.

1998-01-01

The two purposes of this report are to qualitatively document ground-water recharge from stream-flow in Fortymile Wash during the period 1969--95 from previously unpublished ground-water levels in boreholes in Fortymile Canyon during 1982--91 and 1995, and to quantitatively estimate the long-term ground-water recharge rate from streamflow in Fortymile Wash for four reaches of Fortymile Wash (Fortymile Canyon, upper Jackass Flats, lower Jackass Flats, and Amargosa Desert). The long-term groundwater recharge rate was estimated from estimates of the volume of water available for infiltration, the volume of infiltration losses from streamflow, the ground-water recharge volume from infiltration losses, and an analysis of the different periods of data availability. The volume of water available for infiltration and ground-water recharge in the four reaches was estimated from known streamflow in ephemeral Fortymile Wash, which was measured at several gaging station locations. The volume of infiltration losses from streamflow for the four reaches was estimated from a streamflow volume loss factor applied to the estimated streamflows. the ground-water recharge volume was estimated from a linear relation between infiltration loss volume and ground-water recharge volume for each of the four reaches. Ground-water recharge rates were estimated for three different periods of data availability (1969--95, 1983--95, and 1992--95) and a long-term ground-water recharge rate estimated for each of the four reaches

Estimated ground-water recharge from streamflow in Fortymile Wash near Yucca Mountain, Nevada

Energy Technology Data Exchange (ETDEWEB)

Savard, C.S.

1998-10-01

The two purposes of this report are to qualitatively document ground-water recharge from stream-flow in Fortymile Wash during the period 1969--95 from previously unpublished ground-water levels in boreholes in Fortymile Canyon during 1982--91 and 1995, and to quantitatively estimate the long-term ground-water recharge rate from streamflow in Fortymile Wash for four reaches of Fortymile Wash (Fortymile Canyon, upper Jackass Flats, lower Jackass Flats, and Amargosa Desert). The long-term groundwater recharge rate was estimated from estimates of the volume of water available for infiltration, the volume of infiltration losses from streamflow, the ground-water recharge volume from infiltration losses, and an analysis of the different periods of data availability. The volume of water available for infiltration and ground-water recharge in the four reaches was estimated from known streamflow in ephemeral Fortymile Wash, which was measured at several gaging station locations. The volume of infiltration losses from streamflow for the four reaches was estimated from a streamflow volume loss factor applied to the estimated streamflows. the ground-water recharge volume was estimated from a linear relation between infiltration loss volume and ground-water recharge volume for each of the four reaches. Ground-water recharge rates were estimated for three different periods of data availability (1969--95, 1983--95, and 1992--95) and a long-term ground-water recharge rate estimated for each of the four reaches.

Waste Water Disposal Design And Management II

International Nuclear Information System (INIS)

Yang, Sang Hyeon; Lee, Jung Su

2004-04-01

This book is written about design and management of waste water disposal like settling, floating, aeration and filtration. It explains in detail solo settling, flocculant settling, zone settling, multi-level settling, floating like PPI oil separator, structure of skimming tank and design of skimming tank, water treatment and aeration, aeration device, deaeration like deaeration device for disposal processing of sewage, filtration such as structure and design of Micro-floc filtration, In-line filtration and design of slow sand filter bed.

Report on radioactive waste disposal

International Nuclear Information System (INIS)

1993-01-01

The safe management of radioactive wastes constitutes an essential part of the IAEA programme. A large number of reports and conference proceedings covering various aspects of the subject have been issued. The Technical Review Committee on Underground Disposal (February 1988) recommended that the Secretariat issue a report on the state of the art of underground disposal of radioactive wastes. The Committee recommended the need for a report that provided an overview of the present knowledge in the field. This report covers the basic principles associated with the state of the art of near surface and deep geological radioactive waste disposal, including examples of prudent practice, and basic information on performance assessment methods. It does not include a comprehensive description of the waste management programmes in different countries nor provide a textbook on waste disposal. Such books are available elsewhere. Reviewing all the concepts and practices of safe radioactive waste disposal in a document of reasonable size is not possible; therefore, the scope of this report has been limited to cover essential parts of the subject. Exotic disposal techniques and techniques for disposing of uranium mill tailings are not covered, and only brief coverage is provided for disposal at sea and in the sea-bed. The present report provides a list of references to more specialized reports on disposal published by the IAEA as well as by other bodies, which may be consulted if additional information is sought. 108 refs, 22 figs, 2 tabs

Nutrient transport and transformation beneath an infiltration basin

Science.gov (United States)

Sumner, D.M.; Rolston, D.E.; Bradner, L.A.

1998-01-01

Field experiments were conducted to examine nutrient transport and transformation beneath an infiltration basin used for the disposal of treated wastewater. Removal of nitrogen from infiltrating water by denitrification was negligible beneath the basin, probably because of subsurface aeration as a result of daily interruptions in basin loading. Retention of organic nitrogen in the upper 4.6 m of the unsaturated zone (water table depth of approximately 11 m) during basin loading resulted in concentrations of nitrate as much as 10 times that of the applied treated wastewater, following basin 'rest' periods of several weeks, which allowed time for mineralization and nitrification. Approximately 90% of the phosphorus in treated wastewater was removed within the upper 4.6 m of the subsurface, primarily by adsorption reactions, with abundant iron and aluminum oxyhydroxides occurring as soil coatings. A reduction in the flow rate of infiltrating water arriving at the water table may explain the accumulation of relatively coarse (>0.45 ??m), organic forms of nitrogen and phosphorus slightly below the water table. Mineralization and nitrification reactions at this second location of organic nitrogen accumulation contributed to concentrations of nitrate as much as three times that of the applied treated wastewater. Phosphorus, which accumulated below the water table, was immobilized by adsorption or precipitation reactions during basin rest periods.Field experiments were conducted to examine nutrient transport and transformation beneath an infiltration basin used for the disposal of treated wastewater. Removal of nitrogen from infiltrating water by denitrification was negligible beneath the basin, probably because of subsurface aeration as a result of daily interruptions in basin loading. Retention of organic nitrogen in the upper 4.6 m of the unsaturated zone (water table depth of approximately 11 m) during basin loading resulted in concentrations of nitrate as much as 10

Alternative concepts for Low-Level Radioactive Waste Disposal: Conceptual design report

International Nuclear Information System (INIS)

1987-06-01

This conceptual design report is provided by the Department of Energy's Nuclear Energy Low-Level Waste Management Program to assist states and compact regions in developing new low-level radioactive waste (LLW) disposal facilities in accordance with the Low-Level Radioactive Waste Policy Amendment Act of 1985. The report provides conceptual designs and evaluations of six widely considered concepts for LLW disposal. These are shallow land disposal (SLD), intermediate depth disposal (IDD), below-ground vaults (BGV), above-ground vaults (AGV), modular concrete canister disposal (MCCD), earth-mounded concrete bunker (EMCB). 40 refs., 45 figs., 77 tabs

NRC perspective on alternative disposal methods

International Nuclear Information System (INIS)

Pittiglio, C.L.; Tokar, M.

1987-01-01

In this paper is discussed an NRC staff strategy for the development of technical criteria and procedures for the licensing of various alternatives for disposal of low-level radioactive waste. Steps taken by the staff to identify viable alternative disposal methods and to comply with the requirements of the Low-Level Radioactive Waste Policy Amendments Act (LLRWPAA) of 1985 are also discussed. The strategy proposed by the NRC staff is to focus efforts in FY 87 on alternative concepts that incorporate concrete materials with soil or rock cover (e.g., below ground vaults and earth-mounded concrete bunkers), which several State and State Compacts have identified as preferred disposal options. While the NRC staff believes that other options, such as above ground vaults and mined cavities, are workable and licensable, the staff also believes, for reasons addressed in the paper, that it is in the best interest of the industry and the public to encourage standardization and to focus limited resources on a manageable number of alternative options. Therefore, guidance on above ground vaults, which are susceptible to long-term materials degradation due to climatological effects, and mined cavities, which represent a significant departure from the current experience base for low-level radioactive waste disposal, will receive minimal attention. 6 references

Geosphere migration studies as support for the comparison of candidate sites for disposal of radioactive waste in rock-salt

International Nuclear Information System (INIS)

Glasbergen, P.; Hassanizadeh, S.M.; Noordijk, H.; Sauter, F.

1988-01-01

The Dutch research program on the geological disposal of radioactive waste was designed to supply a basis for the selection of combinations of three factors, i.e., type of rock-salt formation, site, and disposal technique, satisfying radiological standards and other criteria for final disposal. The potential sites have been grouped according to the type of rock-salt formation (e.g. bedded salt and salt domes) and two classes of depth below the surface of the ground. Values for geohydrological parameters were obtained by extrapolation of data from existing boreholes and analysis of the sedimentary environment. A three-dimensional model of groundwater flow and contaminant transport, called METROPOL, has been developed. To investigate the effect of high salinity on nuclide transport properly, a theoretical experimental study was carried out. Use of a thermodynamic approach showed that terms related to salt mass fraction have to be added to Darcy's and Fick's laws. An experimental study to investigate effects of these modifications is in progress. 8 refs.; 8 figs.; 1 table

Recycling And Disposal Of Waste

Energy Technology Data Exchange (ETDEWEB)

Choi, Ui So

1987-01-15

This book introduces sewage disposal sludge including properties of sludge and production amount, stabilization of sludge by anaerobic digestion stabilization of sludge by aerobic digestion, stabilization of sludge by chemical method, and dewatering, water process sludge, human waste and waste fluid of septic tank such as disposal of waste fluid and injection into the land, urban waste like definition of urban waste, collection of urban waste, recycling, properties and generation amount, and disposal method and possibility of injection of industrial waste into the ground.

SIMULATION OF NET INFILTRATION FOR MODERN AND POTENTIAL FUTURE CLIMATES

Energy Technology Data Exchange (ETDEWEB)

J.A. Heveal

2000-06-16

This Analysis/Model Report (AMR) describes enhancements made to the infiltration model documented in Flint et al. (1996) and documents an analysis using the enhanced model to generate spatial and temporal distributions over a model domain encompassing the Yucca Mountain site, Nevada. Net infiltration is the component of infiltrated precipitation, snowmelt, or surface water run-on that has percolated below the zone of evapotranspiration as defined by the depth of the effective root zone, the average depth below the ground surface (at a given location) from which water is removed by evapotranspiration. The estimates of net infiltration are used for defining the upper boundary condition for the site-scale 3-dimensional Unsaturated-Zone Ground Water Flow and Transport (UZ flow and transport) Model (CRWMS M&O 2000a). The UZ flow and transport model is one of several process models abstracted by the Total System Performance Assessment model to evaluate expected performance of the potential repository at Yucca Mountain, Nevada, in terms of radionuclide transport (CRWMS M&O 1998). The net-infiltration model is important for assessing potential repository-system performance because output from this model provides the upper boundary condition for the UZ flow and transport model that is used to generate flow fields for evaluating potential radionuclide transport through the unsaturated zone. Estimates of net infiltration are provided as raster-based, 2-dimensional grids of spatially distributed, time-averaged rates for three different climate stages estimated as likely conditions for the next 10,000 years beyond the present. Each climate stage is represented using a lower bound, a mean, and an upper bound climate and corresponding net-infiltration scenario for representing uncertainty in the characterization of daily climate conditions for each climate stage, as well as potential climate variability within each climate stage. The set of nine raster grid maps provide spatially

SIMULATION OF NET INFILTRATION FOR MODERN AND POTENTIAL FUTURE CLIMATES

International Nuclear Information System (INIS)

J.A. Heveal

2000-01-01

This Analysis/Model Report (AMR) describes enhancements made to the infiltration model documented in Flint et al. (1996) and documents an analysis using the enhanced model to generate spatial and temporal distributions over a model domain encompassing the Yucca Mountain site, Nevada. Net infiltration is the component of infiltrated precipitation, snowmelt, or surface water run-on that has percolated below the zone of evapotranspiration as defined by the depth of the effective root zone, the average depth below the ground surface (at a given location) from which water is removed by evapotranspiration. The estimates of net infiltration are used for defining the upper boundary condition for the site-scale 3-dimensional Unsaturated-Zone Ground Water Flow and Transport (UZ flow and transport) Model (CRWMS M and O 2000a). The UZ flow and transport model is one of several process models abstracted by the Total System Performance Assessment model to evaluate expected performance of the potential repository at Yucca Mountain, Nevada, in terms of radionuclide transport (CRWMS M and O 1998). The net-infiltration model is important for assessing potential repository-system performance because output from this model provides the upper boundary condition for the UZ flow and transport model that is used to generate flow fields for evaluating potential radionuclide transport through the unsaturated zone. Estimates of net infiltration are provided as raster-based, 2-dimensional grids of spatially distributed, time-averaged rates for three different climate stages estimated as likely conditions for the next 10,000 years beyond the present. Each climate stage is represented using a lower bound, a mean, and an upper bound climate and corresponding net-infiltration scenario for representing uncertainty in the characterization of daily climate conditions for each climate stage, as well as potential climate variability within each climate stage. The set of nine raster grid maps provide

THE POSSIBILITY OF DISPOSING OF SPENT COFFEE GROUND WITH ENERGY RECYCLING

Directory of Open Access Journals (Sweden)

Tomasz Ciesielczuk

2015-09-01

Full Text Available The current policy of waste management requires, above all, a gradual reduction of waste amount and, to a larger extent, forces us to seek new methods of waste disposal. Recycling the energy contained in biomass waste is a more and more universally applied method of thermal converting. Biomass combustion allows saving fossil fuels which fits into sustainable development. This paper checks the possibility of using spent coffee ground (SCG in energy recycling using a combustion process. This particular biomass type up to now has not been widely examined, which inclines to consider its usage as a potential additive to alternative fuels. In the study, we examined the quality of fuel, which was in a form of briquette, made of beech shavings with 10 and 25% of post-exploitation waste obtained during the process of coffee infusion. This waste, if fresh, is distinguished by its high hydration. However, after drying it may constitute a valuable additive to alternative fuels. It increases the calorific value of fuel and reduces briquettes’ hardness what contributes to reducing resistance of conveying screw in stoves.

Assessment of Westinghouse Hanford Company methods for estimating radionuclide release from ground disposal of waste water at the N Reactor sites

International Nuclear Information System (INIS)

1988-09-01

This report summarizes the results of an independent assessment by Golder Associates, Inc. of the methods used by Westinghouse Hanford Company (Westinghouse Hanford) and its predecessors to estimate the annual offsite release of radionuclides from ground disposal of cooling and other process waters from the N Reactor at the Hanford Site. This assessment was performed by evaluating the present and past disposal practices and radionuclide migration data within the context of the hydrology, geology, and physical layout of the N Reactor disposal site. The conclusions and recommendations are based upon the available data and simple analytical calculations. Recommendations are provided for conducting more refined analyses and for continued field data collection in support of estimating annual offsite releases. Recommendations are also provided for simple operational and structural measures that should reduce the quantities of radionuclides leaving the site. 5 refs., 9 figs., 1 tab

Investigation on CO2 property and its geological disposal in coal bed

International Nuclear Information System (INIS)

Liang Weiguo; Wu Di; Hao Shuping

2008-01-01

Carbon dioxide is main green house gas, and it has been increased greatly in the atmosphere since the industrial revolution. The human living environment has been worsened with more and more carbon dioxide in the air. In this paper, the authors analyzed the physical property of carbon dioxide and green house gas effect, then studied the disposal measures for carbon dioxide. At last it was pointed out that various measures should be taken to carry out the carbon dioxide disposal, more economic benefit can be anticipated along with carbon dioxide disposal by EOR, CO 2 -ECBM, CAES, et al, of which CO 2 -ECBM is one of the way with best benefits. (authors)

Characterizing Heterogeneity in Infiltration Rates During Managed Aquifer Recharge.

Science.gov (United States)

Mawer, Chloe; Parsekian, Andrew; Pidlisecky, Adam; Knight, Rosemary

2016-11-01

Infiltration rate is the key parameter that describes how water moves from the surface into a groundwater aquifer during managed aquifer recharge (MAR). Characterization of infiltration rate heterogeneity in space and time is valuable information for MAR system operation. In this study, we utilized fiber optic distributed temperature sensing (FO-DTS) observations and the phase shift of the diurnal temperature signal between two vertically co-located fiber optic cables to characterize infiltration rate spatially and temporally in a MAR basin. The FO-DTS measurements revealed spatial heterogeneity of infiltration rate: approximately 78% of the recharge water infiltrated through 50% of the pond bottom on average. We also introduced a metric for quantifying how the infiltration rate in a recharge pond changes over time, which enables FO-DTS to be used as a method for monitoring MAR and informing maintenance decisions. By monitoring this metric, we found high-spatial variability in how rapidly infiltration rate changed during the test period. We attributed this variability to biological pore clogging and found a relationship between high initial infiltration rate and the most rapid pore clogging. We found a strong relationship (R 2  = 0.8) between observed maximum infiltration rates and electrical resistivity measurements from electrical resistivity tomography data taken in the same basin when dry. This result shows that the combined acquisition of DTS and ERT data can improve the design and operation of a MAR pond significantly by providing the critical information needed about spatial variability in parameters controlling infiltration rates. © 2016, National Ground Water Association.

Demonstration of an infiltration evaluation methodology

International Nuclear Information System (INIS)

Smyth, J.D.; Gee, G.W.; Kincaid, C.T.; Nichols, W.M.; Bresler, E.

1990-07-01

An Infiltration Evaluation Methodology (IEM) was developed for the US Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL) to provide a consistent, well formulated approach for evaluating drainage through engineered covers at low-level radioactive waste (LLW) sites. The methodology is designed to help evaluate the ability of proposed waste site covers to minimize drainage for LLW site license applications and for sites associated with the Uranium Mill Tailings Remedial Action (UMTRA) program. The objective of this methodology is to estimate the drainage through an engineered burial site cover system. The drainage estimate can be used as an input to a broader performance assessment methodology currently under development by the NRC. The methodology is designed to simulate, at the field scale, significant factors and hydrologic conditions which determine or influence estimates of infiltration, long-term moisture content profiles, and drainage from engineered covers and barriers. The IEM developed under this study acknowledges the uncertainty inherent in soil properties and quantifies the influence of such uncertainty on the estimates of drainage in engineered cover systems at waste disposal sites. 6 refs., 1 fig

Unidirectional infiltration method to produce crown for dental prosthesis application

International Nuclear Information System (INIS)

Pontes, F.H.D.; Taguchi, S.P.; Machado, J.P.B.; Santos, C.

2009-01-01

Alumina ceramics have been used in dental prosthesis because it is inert, presents higher corrosion and shear resistance when compared to metals, excellent aesthetic, and mechanical resistance. In this work it was produced an infrastructure material for applications in dental crowns, obtained by glass infiltration in alumina preform. Various oxides, among that, rare-earth oxide produced by Xenotime, were melted at 1450 deg C and heat treatment at 700 deg C to obtain the glass (REglass). The alumina was pre-sintered at 1100 deg C cut and machined to predetermine format (unidirectional indirect infiltration) and finally conducted to infiltration test. The alumina was characterized by porosity (Hg-porosity and density) and microstructure (SEM). The glass wettability in alumina was determined as function of temperature, and the contact angle presented a low value (θ<90 deg), showing that glass can be infiltrated spontaneously in alumina. The infiltration test was conducted at glass melting temperature, during 30, 60, 180, 360 minutes. After infiltration, the samples were cut in longitudinal section, ground and polished, and analyzed by XRD (crystalline phases), SEM (microstructure) and EDS (composition).The REglass presents higher infiltration height when compared to current processes (direct infiltration), and homogeneous microstructure, showing that it is a promising method used by prosthetics and dentists. (author)

Unidirectional infiltration method to produce crown for dental prosthesis application

Energy Technology Data Exchange (ETDEWEB)

Pontes, F.H.D.; Taguchi, S.P. [Universidade de Sao Paulo (EEL/DEMAR/USP), Lorena, SP (Brazil). Escola de Engenharia; Borges Junior, L.A. [Centro Universitario de Volta Redonda, RJ (Brazil); Machado, J.P.B. [Instituto Nacional de Pesquisas Espaciais (INPE), Sao Jose dos Campos, SP (Brazil); Santos, C. [ProtMat Materiais Avancados, Guaratingueta, SP (Brazil)

2009-07-01

Alumina ceramics have been used in dental prosthesis because it is inert, presents higher corrosion and shear resistance when compared to metals, excellent aesthetic, and mechanical resistance. In this work it was produced an infrastructure material for applications in dental crowns, obtained by glass infiltration in alumina preform. Various oxides, among that, rare-earth oxide produced by Xenotime, were melted at 1450 deg C and heat treatment at 700 deg C to obtain the glass (REglass). The alumina was pre-sintered at 1100 deg C cut and machined to predetermine format (unidirectional indirect infiltration) and finally conducted to infiltration test. The alumina was characterized by porosity (Hg-porosity and density) and microstructure (SEM). The glass wettability in alumina was determined as function of temperature, and the contact angle presented a low value (θ<90 deg), showing that glass can be infiltrated spontaneously in alumina. The infiltration test was conducted at glass melting temperature, during 30, 60, 180, 360 minutes. After infiltration, the samples were cut in longitudinal section, ground and polished, and analyzed by XRD (crystalline phases), SEM (microstructure) and EDS (composition).The REglass presents higher infiltration height when compared to current processes (direct infiltration), and homogeneous microstructure, showing that it is a promising method used by prosthetics and dentists. (author)

On selection of geological medium for disposal of high-level radwaste

International Nuclear Information System (INIS)

Min Maozhong

1991-01-01

The present paper briefly reviews the suitability of some rocks as geological disposal repositories of high-level radwaste (HLW). The suitable rocks for geological ogi disposal of HLW are rock salt (salt diapir, bedded salt), granite, argillaceous rocks, tuff, basalt, gabbro, diabase, anhydrite, marine sedimentary rocks etc., especially, rock salt, granite, and argillaceous rocks. The data of principal hydraulic properties, mechanical-physical properties for various rocks in typical environment which might be considered for disposal purposes are also given in this paper. These data give a reference to China's geological disposal of HLW in the future

Pyramiding tumuli waste disposal site and method of construction thereof

Science.gov (United States)

Golden, Martin P.

1989-01-01

An improved waste disposal site for the above-ground disposal of low-level nuclear waste as disclosed herein. The disposal site is formed from at least three individual waste-containing tumuli, wherein each tumuli includes a central raised portion bordered by a sloping side portion. Two of the tumuli are constructed at ground level with adjoining side portions, and a third above-ground tumulus is constructed over the mutually adjoining side portions of the ground-level tumuli. Both the floor and the roof of each tumulus includes a layer of water-shedding material such as compacted clay, and the clay layer in the roofs of the two ground-level tumuli form the compacted clay layer of the floor of the third above-ground tumulus. Each tumulus further includes a shield wall, preferably formed from a solid array of low-level handleable nuclear wate packages. The provision of such a shield wall protects workers from potentially harmful radiation when higher-level, non-handleable packages of nuclear waste are stacked in the center of the tumulus.

The trends of radioactive waste disposal

International Nuclear Information System (INIS)

Nomi, Mitsuhiko

1977-01-01

The disposal of radioactive wastes instead of their treatment has come to be important problem. The future development of nuclear fuel can not be expected unless the final disposal of nuclear fuel cycle is determined. Research and development have been made on the basis of the development project on the treatment of radioactive wastes published by Japan Atomic Energy Commission in 1976. The high level wastes produced by the reprocessing installations for used nuclear fuel are accompanied by strong radioactivity and heat generation. The most promising method for their disposal is to keep them in holes dug at the sea bottom after they are solidified. Middle or low level wastes are divided into two groups; one contains transuranium elements and the other does not. These wastes are preserved on the ground or in shallow strata, while the safe abandonment into the ground or the sea has been discussed about the latter. The co-operations among nations are necessary not only for peaceful utilization of atomic energy but also for radioactive waste disposal. (Kobatake, H.)

Safety of geologic disposal of high level radioactive waste

International Nuclear Information System (INIS)

Zaitsu, Tomohisa; Ishiguro, Katsuhiko; Masuda, Sumio

1992-01-01

This article introduces current concepts of geologic disposal of high level radioactive waste and its safety. High level radioactive waste is physically stabilized by solidifying it in a glass form. Characteristics of deep geologic layer are presented from the viewpoint of geologic disposal. Reconstruction of multi-barrier system receives much attention to secure the safety of geologic disposal. It is important to research performance assessment of multi-barrier system for preventing dissolution or transfer of radionuclides into the ground water. Physical and chemical modeling for the performance assessment is outlined in the following terms: (1) chemical property of deep ground water, (2) geochemical modeling of artificial barrier spatial water, (3) hydrology of deep ground water, (4) hydrology of the inside of artificial barrier, and (5) modeling of radionuclide transfer from artificial barrier. (N.K.)

Modified technology in new constructions, and cost effective remedial action in existing structures, to prevent infiltration of soil gas carrying radon

International Nuclear Information System (INIS)

Ericson, S.O.; Schmied, H.; Clavensjoe, B.

1984-01-01

The general principles and mechanism of how soil gas infiltrates and carries radon from the foundation bed and subsoil into buildings are discussed. The Swedish Building Research Council has funded experiments and evaluation of cost effective remedial actions. The work has concerned existing dwellings with high concentration of radon, resulting from infiltrating soil gas and/or exhalation from building materials. A review and evaluation is given of experience and results acquired up to the summer of 1984. 100 dwellings have been constructed with consideration of possible infiltration of soil gas. In general minor modifications are sufficient to prevent infiltration. (Author)

Source term analysis for a RCRA mixed waste disposal facility

International Nuclear Information System (INIS)

Jordan, D.L.; Blandford, T.N.; MacKinnon, R.J.

1996-01-01

A Monte Carlo transport scheme was used to estimate the source strength resulting from potential releases from a mixed waste disposal facility. Infiltration rates were estimated using the HELP code, and transport through the facility was modeled using the DUST code, linked to a Monte Carlo driver

Influence of the extreme millennial values of the physical data of the natural environment on the ground and near underground. Application to waste disposal sites

International Nuclear Information System (INIS)

Guinle-Thenevin, I.

1998-01-01

This study deals with effects of extreme climatic events in France on perenniality of radioactive or toxic waste disposal coverings or of tailing storage barriers. Three phenomena are quantified: erosion or scraping produced by storm showers, ground freezing depth caused by harsh winters and ground drying resulted from arid summers. To quantify this phenomena, we need statistical evaluation of the climatic events (erosivity of rain showers, frost severity index, drought severity indices), a study of the soil characteristics (petrography, thermal and hydraulic properties) and numeric models of soils (finite elements or finite differences methods). Last but not least, each method is applied to French sites chosen for their climate and their proximity to real or possible storage. Therefore, we show critical parameters for the design of waste disposal covering which takes into account extreme climatic events. (author)

Managing Vegetation on Peat-Sand Filter Beds for Wastewater Disposal

Science.gov (United States)

Arthur E. Elling

1985-01-01

Five species of grass, one sedge, and cattail were grown on a peat-sand filter bed irrigated with sewage effluent. Yields, uptake of nitrogen and phosphorus, and lodging problems were determined for all species when grown to various heights ranging from 5 to 75 cm.

Contamination of ground water as a consequence of land disposal of dye waste mixed sewage effluents: a case study of Panipat district of Haryana, India.

Science.gov (United States)

Dubey, S K; Yadav, Rashmi; Chaturvedi, R K; Yadav, R K; Sharma, V K; Minhas, P S

2010-09-01

Spatial samples of surface and ground water collected from land disposal site of dye waste mixed sewage effluents at Binjhole, in Haryana, India were analyzed to evaluate its effect on quality of pond, hand pumps and ground waters for human health and irrigation purposes. It was found that average COD and TDS of dye houses discharge (310 and 3,920 mg/L) and treated sewage (428 and 1,470 mg/L) on mixing acquired the values of 245 and 1,780 mg/L and only Pb (0.24 microg/L) was above the permissible limit for irrigation purpose. Disposal of this mixed water to village pond changes the COD and TDS to 428 and 1,470 mg/L, respectively. COD and TDS of hand pump water samples were 264 and 1,190 mg/L, where as in tube well water these values were 151 and 900 mg/L. Though the ground water contamination seemed to decrease with the increasing distance from the pond but COD, TDS and BOD values continued to be quite high in water samples drawn from the hand pumps up to a distance of 500 m from pond. However, the major cause of the concern in these waters was Pb (0.11-0.45 ppm). Crops grown with this water shows accumulation of heavy metals like Pb,Cd, Fe, Mn, Ni, Cu, and Zn but in few crops they (Zn, Pb and Cd) exceed the safe limits. Regular consumption of these crop products may lead heavy metal toxicity. It was concluded from this study that the deep seepage of effluents led to deterioration of ground water quality for drinking purposes and the well waters rendered unfit for irrigation purposes within a span of 2 years. This warrants appropriate disposal measures for sewage and dye industry effluents in order to prevent deterioration of ground water and health of human and animals.

Measurement of flow and direction of ground water by radioactive tracers: hydrological evaluation of a waste disposal site at 'Instituto de Pesquisas Energeticas e Nucleares (IPEN)'

International Nuclear Information System (INIS)

Chandra, U.; Aoki, P.E.; Ramos e Silva, J.A.; Castagnet, A.C.G.

1981-05-01

The method of determining flow and drection of ground water by using radioactive tracers in ground water borings is described. Various parameters controlling the measurements are discussed in detail. Application of the method in studying a variety of geohydrological problems, in view of the hydrological evaluation of the waste disposal site at IPEN, is indicated. Comparison of the method with conventional pumping tests is made. (I.C.R.) [pt

Environmental isotopes assist in the site assessment of Vaalputs radioactive waste disposal facility

International Nuclear Information System (INIS)

Verhagen, B.T.; Levin, M.

1986-01-01

The first South African nuclear waste disposal facility is to be sited in an arid environment with an average annual rainfall of about 78mm. The ground water might therefore be virtually stationary, making the geohydrology of the area crucial in the assessment of radionuclide dispersal difficult to study with standard hydraulic methods. Environmental isotopes, which label the water itself and some of its dissolved constituents are able to give synoptic information about the ground water; from this, some projections about future mobility can be made. Tritium profiles in the unsaturated zone show the limited extent of rain water infiltration, which generally extends down to 3-4 metres, with sporadic evidence of deeper penetration through cracks and rootholes in the thick clay cover. Soil moisture therefore seems to occur in tightly bound and more mobile components. This is confirmed by occasionally measurable tritium observed in the saturated zone. Radiocarbon in the ground water cannot be simply interpreted on account of the nature of the granite aquifer. Although suggesting ages of several thousands of years, radiocarbon proves that the water is not 'fossil' or derived from the last pluvial period, postulated to have occurred some 12 000 years ago. Recharge appears to be more ongoing and to occur periodically and locally as a result of outliers within the present climatological regime. Regional movement of ground water is however very limited, as spatial variations seen in the radiocarbon data of the ground water are non-systematic. These conclusions are supported by the distribution of the non-radioactive isotopes, such as oxygen-18

Aquifer recharge from infiltration basins in a highly urbanized area: the river Po Plain (Italy)

Science.gov (United States)

Masetti, M.; Nghiem, S. V.; Sorichetta, A.; Stevenazzi, S.; Santi, E. S.; Pettinato, S.; Bonfanti, M.; Pedretti, D.

2015-12-01

Due to the extensive urbanization in the Po Plain in northern Italy, rivers need to be managed to alleviate flooding problems while maintaining an appropriate aquifer recharge under an increasing percentage of impermeable surfaces. During the PO PLain Experiment field campaign in July 2015 (POPLEX 2015), both active and under-construction infiltration basins have been surveyed and analyzed to identify appropriate satellite observations that can be integrated to ground based monitoring techniques. A key strategy is to have continuous data time series on water presence and level within the basin, for which ground based monitoring can be costly and difficult to be obtained consistently.One of the major and old infiltration basin in the central Po Plain has been considered as pilot area. The basin is active from 2003 with ground based monitoring available since 2009 and supporting the development of a calibrated unsaturated-saturated two-dimensional numerical model simulating the infiltration dynamics through the basin.A procedure to use satellite data to detect surface water change is under development based on satellite radar backscatter data with an appropriate incidence angle and polarization combination. An advantage of satellite radar is that it can observe surface water regardless of cloud cover, which can be persistent during rainy seasons. Then, the surface water change is correlated to the reservoir water stage to determine water storage in the basin together with integrated ground data and to give quantitative estimates of variations in the local water cycle.We evaluated the evolution of the infiltration rate, to obtain useful insights about the general recharge behavior of basins that can be used for informed design and maintenance. Results clearly show when the basin becomes progressively clogged by biofilms that can reduce the infiltration capacity of the basin by as much as 50 times compared to when it properly works under clean conditions.

Hydraulic fracturing tests in anhydrite interbeds in the WIPP, Marker Beds 139 and 140

Energy Technology Data Exchange (ETDEWEB)

Howard, C L [RE/SPEC Inc., Albuquerque, NM (United States); Wawersik, W. R.; Carlson, L. V.; Henfling, J. A.; Borns, D. J.; Beauheim, R. L.; Roberts, R. M.

1997-05-01

Hydraulic fracturing tests were integrated with hydrologic tests to estimate the conditions under which gas pressure in the disposal rooms in the Waste Isolation Pilot Plant, Carlsbad, NM (WIPP) will initiate and advance fracturing in nearby anhydrite interbeds. The measurements were made in two marker beds in the Salado formation, MB139 and MB140, to explore the consequences of existing excavations for the extrapolation of results to undisturbed ground. The interpretation of these measurements is based on the pressure-time records in two injection boreholes and several nearby hydrologic observation holes. Data interpretations were aided by post-test borehole video surveys of fracture traces that were made visible by ultraviolet illumination of fluorescent dye in the hydraulic fracturing fluid. The conclusions of this report relate to the upper- and lower-bound gas pressures in the WIPP, the paths of hydraulically and gas-driven fractures in MB139 and MB140, the stress states in MB139 and MB140, and the probable in situ stress states in these interbeds in undisturbed ground far away from the WIPP.

Risk analysis methodology for unreprocessed spent fuel disposal in bedded salt

International Nuclear Information System (INIS)

Pepping, R.E.; Chu, M.S.Y.; Cranwell, R.M.

1982-01-01

In accordance with the decision to defer the reprocessing of commercially generated spent fuel, we are investigating the implications on risk of direct disposal of spent fuel assemblies. To the extent possible, we are using the methodology developed at Sandia for the NRC to evaluate risks from the disposal of wastes from reprocessing of spent fuel. This allows direct comparison of the risks calculated for the two waste forms. A number of differences between the two waste forms with implications on risk have been identified and investigation of their effects has begun. Among these are the presence of gases and additional plutonium and uranium isotopes, the potential for differing leach behavior, and the difference in the decay heat source which determines the overall thermomechanical response of the host media. We have analyzed a number of scenarios for a hypothetical geologic repository that have been identified as important contributors to risk from the disposal of both reprocessed and unreprocessed spent fuel. For each scenario, we employ the Groundwater Transport, Pathways to Man, and Dosimetry and Health Effects models of the High Level Waste Methodology. Risks are compared for the reprocessed and unreprocessed spent fuel wastes and the effects of uncertainty in the parameters of the various models are compared

History of disposal of radioactive wastes into the ground at Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Coobs, J.H.; Gissel, J.R.

1986-10-01

Since the beginning of operations at the Oak Ridge National Laboratory (ORNL) in 1943, shallow land burial has been used for the disposal of solid low-level radioactive waste. These wastes have originated from nearly every operating facility, and from 1955 to 1963, ORNL's solid waste storage areas were designated by the Atomic Energy Commission (AEC) as the Southern Regional Burial Ground. During this period, about one million cubic feet of solid waste from various off-site installations were buried in solid waste storage areas (SWSAs) 4 and 5. Six SWSAs have been used since land burial operations began at ORNL in early 1944. ORNL has generated liquid radioactive waste since the separation of plutonium began in 1944. The majority of these wastes are classified as process (low-level) waste and are derived from evaporator condensate and cooling water from process vessels, and from building drains and surface drainage from contaminated areas. Process wastes are monitored at sampling stations located strategicially throughout the plant, and for nearly 15 years (1944 to 1957) they were discharged directly into White Oak Creek without being treated chemically to remove radionuclides. A smaller quantity of intermediate-level wastes (ILW) originate from the radiochemical separation process and from test reactors. The collection, treatment, and methods of disposal of ILW from the years 1943 to 1981 are described. Over this period of time there was a great deal of variation in the amounts and types of radioactive liquid wastes generated.

History of disposal of radioactive wastes into the ground at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Coobs, J.H.; Gissel, J.R.

1986-10-01

Since the beginning of operations at the Oak Ridge National Laboratory (ORNL) in 1943, shallow land burial has been used for the disposal of solid low-level radioactive waste. These wastes have originated from nearly every operating facility, and from 1955 to 1963, ORNL's solid waste storage areas were designated by the Atomic Energy Commission (AEC) as the Southern Regional Burial Ground. During this period, about one million cubic feet of solid waste from various off-site installations were buried in solid waste storage areas (SWSAs) 4 and 5. Six SWSAs have been used since land burial operations began at ORNL in early 1944. ORNL has generated liquid radioactive waste since the separation of plutonium began in 1944. The majority of these wastes are classified as process (low-level) waste and are derived from evaporator condensate and cooling water from process vessels, and from building drains and surface drainage from contaminated areas. Process wastes are monitored at sampling stations located strategicially throughout the plant, and for nearly 15 years (1944 to 1957) they were discharged directly into White Oak Creek without being treated chemically to remove radionuclides. A smaller quantity of intermediate-level wastes (ILW) originate from the radiochemical separation process and from test reactors. The collection, treatment, and methods of disposal of ILW from the years 1943 to 1981 are described. Over this period of time there was a great deal of variation in the amounts and types of radioactive liquid wastes generated

Topic III - Infiltration and Drainage: A section in Joint US Geological Survey, US Nuclear Regulatory Commission workshop on research related to low-level radioactive waste disposal, May 4-6, 1993, National Center, Reston, Virginia; Proceedings (WRI 95-4015)

Science.gov (United States)

Prudic, David E.; Gee, Glendon; Stevens, Peter R.; Nicholson, Thomas J.

1996-01-01

Infiltration into and drainage from facilities for the disposal of low-level radioactive wastes is considered the major process by which non-volatile contaminants are transported away from the facilities. The session included 10 papers related to the processes of infiltration and drainage, and to the simulation of flow and transport through the unsaturated zone. The first paper, presented by David Stonestrom, was an overview regarding the application of unsaturated flow theory to infiltration and drainage. Stonestrom posed three basic questions, which are:How well do we know the relevant processes affecting flow and transport?How well can we measure the parametric functions used to quantify flow and transport?How do we treat complexities inherent in field settings?The other nine papers presented during the session gave some insight to these questions. Topics included: laboratory measurement of unsaturated hydraulic conductivities at low water contents, by John Nimmo; use of environmental tracers to identify preferential flow through fractured media and to quantify drainage, by Edmund Prych and Edwin Weeks; field experiments to evaluate relevant processes affecting infiltration and drainage, by Brian Andraski, Glendon Gee, and Peter Wierenga; and the use of determinist'c and stochastic models for simulating flow and transport through heterogeneous sediments, by Richard Hills, Lynn Gelhar, and Shlomo Neuman.

Underground disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

NONE

1979-08-15

Disposal of low- and intermediate-level radioactive wastes by shallow land burial, emplacement in suitable abandoned mines, or by deep well injection and hydraulic fracturing has been practised in various countries for many years. In recent years considerable efforts have been devoted in most countries that have nuclear power programmes to developing and evaluating appropriate disposal systems for high-level and transuranium-bearing waste, and to studying the potential for establishing repositories in geological formations underlaying their territories. The symposium, organized jointly by the IAEA and OECD's Nuclear Energy Agency in cooperation with the Geological Survey of Finland, provided an authoritative account of the status of underground disposal programmes throughout the world in 1979. It was evidence of the experience that has been gained and the comprehensive investigations that have been performed to study various options for the underground disposal of radioactive waste since the last IAEA/NEA symposium on this topic (Disposal of Radioactive Waste into the Ground) was held in 1967 in Vienna. The 10 sessions covered the following topics: National programme and general studies, Disposal of solid waste at shallow depth and in rock caverns, underground disposal of liquid waste by deep well injection and hydraulic fracturing, Disposal in salt formations, Disposal in crystalline rocks and argillaceous sediments, Thermal aspects of disposal in deep geological formations, Radionuclide migration studies, Safety assessment and regulatory aspects.

Main approaches to solving the problems of radioactive waste processing and disposal

International Nuclear Information System (INIS)

Tarasov, V.M.; Syrkus, M.N.

1989-01-01

papers devoted to the problems of processing and disposal of radioactive wastes, formed during nuclear facility operation and after decommissioning are reviewed. Techniques for gaseous and liquid waste solidification, as well as solid waste processing by mechanical fragmentation and combustion are considered. Possibilities of radioactive waste disposal in cosmic space, their burial at the bed of seas ansd oceans, in geological storages are discussed. Special attention disposal. The conclusion is made that today there are no any uniform way for radiactive waste disposal and standard technical means for its realization. Solution of the problems considered should be of a complex character and it is carried out within international research programs

Environmental control aspects for fabrication, reprocessing and waste disposal of alternative LWR and LMFBR fuels

International Nuclear Information System (INIS)

Nolan, A.M.; Lewallen, M.A.; McNair, G.W.

1979-11-01

Environmental control aspects of alternative fuel cycles have been analyzed by evaluating fabrication, reprocessing, and waste disposal operations. Various indices have been used to assess potential environmental control requirements. For the fabrication and reprocessing operations, 50-year dose commitments were used. Waste disposal was evaluated by comparing projected nuclide concentrations in ground water at various time periods with maximum permissible concentrations (MPCs). Three different fabrication plants were analyzed: a fuel fabrication plant (FFP) to produce low-activity uranium and uranium-thorium fuel rods; a plutonium fuel refabrication plant (PFRFP) to produce plutonium-uranium and plutonium-thorium fuel rods; and a uranium fuel refabrication plant (UFRFP) to produce fuel rods containing the high-activity isotopes 232 U and 233 U. Each plant's dose commitments are discussed separately. Source terms for the analysis of effluents from the fuel reprocessing plant (FRP) were calculated using the fuel burnup codes LEOPARD, CINDER and ORIGEN. Effluent quantities are estimated for each fuel type. Bedded salt was chosen for the waste repository analysis. The repository site is modeled on the Waste Isolation Pilot Program site in New Mexico. Wastes assumed to be stored in the repository include high-level vitrified waste from the FRP, packaged fuel residue from the FRP, and transuranic (TRU) contaminated wastes from the FFP, PFRFP, and UFRFP. The potential environmental significance was determined by estimating the ground-water concentrations of the various nuclides over a time span of a million years. The MPC for each nuclide was used along with the estimated ground-water concentration to generate a biohazard index for the comparison among fuel compositions

Long-term surveillance plan for the Burro Canyon disposal cell, Slick Rock, Colorado

International Nuclear Information System (INIS)

1996-11-01

This long-term surveillance plant (LTSP) describes the US Department of energy's (DOE) long-term care program for the Uranium Mill Tailings Remediation Action (UMTRA) Project's burro Canyon disposal cell in San Miguel County, Colorado. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Burro Canyon disposal cell performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. No ground water monitoring will be required at the Burro Canyon disposal cell because the ground water protection strategy is supplemental standards based on low-yield from the upper-most aquifer

Hydrodynamic studies in designing of fluidized bed system

International Nuclear Information System (INIS)

Mohamad Puad Abu; Muhd Noor Muhd Yunus; Syed Nasaruddin Syed Idris

2002-01-01

Fluidized bed process have been used mostly in the petroleum and paper industries, and for processing nuclear wastes, spent cook liquor, wood chips, and sewage sludge disposal. Even at MINT some of the equipment available used this principal. Before we use or purchase this equipment, it is very grateful if we could understand how the system has been designed. The hydrodynamic fluidization studies is very important in designing of fluidized bed system especially in determining the minimum fluidizing velocity, terminal velocity, flexibility of operation, slugging condition, bubble size and velocity, and transport disengaging height. They can be determined either by calculation or experimentation. This paper will highlight the hydrodynamic study that need to be performed in designing of fluidized bed system so that its can be used appropriately. (Author)

Measurement of the heat transfer parameters in infiltrated binary beryllium beds. Comparison between the results with PEHTRA and SUPER-PEHTRA

International Nuclear Information System (INIS)

Donne, M. dalle; Piazza, G.; Scaffidi-Argentina, F.

2000-01-01

For the next generation fusion reactors with a ceramic breeder blanket the use, as a neutron multiplier, of either a binary bed of large (∼ 2 mm) and small (∼ 0.1-0.2 mm) beryllium pebbles or a single size bed made of 1 mm or 2 mm pebbles is foreseen. The heat transfer parameters of such a binary pebble bed, namely the thermal conductivity and the heat transfer coefficient to the containing wall, have been investigated previously in the experimental device PEHTRA available at FZK. The experiments allowed to measure the effect of the bed temperature and of constraint exerted by the containing walls. The constraint is defined by the bed interference, i.e. the difference in the radial expansion between bed and the constraining walls related to the bed thickness (Δl/l). However, with the PEHTRA experiments, it was only possible to achieve a Δl/l value of 0.1%. A new experimental rig (SUPER-PEHTRA) has been constructed at FZK, which allows to achieve Δl/l values of 0.3% and to measure the pressure of the expanding bed on the containing walls. First experiments with a binary bed have been performed. The present paper reports on further experiments with binary beds and the establishing of equations correlating the data obtained for the present binary beds and for the binary bed experiments described. (orig.)

Underground disposal of radioactive wastes

International Nuclear Information System (INIS)

1981-01-01

This report is an overview document for the series of IAEA reports dealing with underground waste disposal to be prepared in the next few years. It provides an introduction to the general considerations involved in implementing underground disposal of radioactive wastes. It suggests factors to be taken into account for developing and assessing waste disposal concepts, including the conditioned waste form, the geological containment and possible additional engineered barriers. These guidelines are general so as to cover a broad range of conditions. They are generally applicable to all types of underground disposal, but the emphasis is on disposal in deep geological formations. Some information presented here may require slight modifications when applied to shallow ground disposal or other types of underground disposal. Modifications may also be needed to reflect local conditions. In some specific cases it may be that not all the considerations dealt with in this book are necessary; on the other hand, while most major considerations are believed to be included, they are not meant to be all-inclusive. The book primarily concerns only underground disposal of the wastes from nuclear fuel cycle operations and those which arise from the use of isotopes for medical and research activities

Disposal of solid radioactive waste of nuclear power plant

International Nuclear Information System (INIS)

YU Shichen.

1986-01-01

The contaminations of marine enviroment by the disposal of radwastes should not been expected, then ocean disposal has been stoped in some countries, and land disposal of solid radwastes should been a better method for mankind and environment protection. Ground burial near the surface is currently considered to be feasible. Storage in spent pit or in plant area also should been adapted in several countries

Geologic disposal as optimal solution of managing the spent nuclear fuel and high-level radioactive waste

International Nuclear Information System (INIS)

Ilie, P.; Didita, L.; Ionescu, A.; Deaconu, V.

2002-01-01

To date there exist three alternatives for the concept of geological disposal: 1. storing the high-level waste (HLW) and spent nuclear fuel (SNF) on ground repositories; 2. solutions implying advanced separation processes including partitioning and transmutation (P and T) and eventual disposal in outer space; 3. geological disposal in repositories excavated in rocks. Ground storing seems to be advantageous as it ensures a secure sustainable storing system over many centuries (about 300 years). On the other hand ground storing would be only a postponement in decision making and will be eventually followed by geological disposal. Research in the P and T field is expected to entail a significant reduction of the amount of long-lived radioactive waste although the long term geological disposal will be not eliminated. Having in view the high cost, as well as the diversity of conditions in the countries owning power reactors it appears as a reasonable regional solution of HLW disposal that of sharing a common geological disposal. In Romania legislation concerning of radioactive waste is based on the Law concerning Spent Nuclear Fuel and Radioactive Waste Management in View of Final Disposal. One admits at present that for Romania geological disposal is not yet a stressing issue and hence intermediate ground storing of SNF will allow time for finding a better final solution

Underground radioactive waste disposal concept

International Nuclear Information System (INIS)

Frgic, L.; Tor, K.; Hudec, M.

2002-01-01

The paper presents some solutions for radioactive waste disposal. An underground disposal of radioactive waste is proposed in deep boreholes of greater diameter, fitted with containers. In northern part of Croatia, the geological data are available on numerous boreholes. The boreholes were drilled during investigations and prospecting of petroleum and gas fields. The available data may prove useful in defining safe deep layers suitable for waste repositories. The paper describes a Russian disposal design, execution and verification procedure. The aim of the paper is to discuss some earlier proposed solutions, and present a solution that has not yet been considered - lowering of containers with high level radioactive waste (HLW) to at least 500 m under the ground surface.(author)

Water infiltration in an aquifer recharge basin affected by temperature and air entrapment

Directory of Open Access Journals (Sweden)

Loizeau Sébastien

2017-09-01

Full Text Available Artificial basins are used to recharge groundwater and protect water pumping fields. In these basins, infiltration rates are monitored to detect any decrease in water infiltration in relation with clogging. However, miss-estimations of infiltration rate may result from neglecting the effects of water temperature change and air-entrapment. This study aims to investigate the effect of temperature and air entrapment on water infiltration at the basin scale by conducting successive infiltration cycles in an experimental basin of 11869 m2 in a pumping field at Crepieux-Charmy (Lyon, France. A first experiment, conducted in summer 2011, showed a strong increase in infiltration rate; which was linked to a potential increase in ground water temperature or a potential dissolution of air entrapped at the beginning of the infiltration. A second experiment was conducted in summer, to inject cold water instead of warm water, and also revealed an increase in infiltration rate. This increase was linked to air dissolution in the soil. A final experiment was conducted in spring with no temperature contrast and no entrapped air (soil initially water-saturated, revealing a constant infiltration rate. Modeling and analysis of experiments revealed that air entrapment and cold water temperature in the soil could substantially reduce infiltration rate over the first infiltration cycles, with respective effects of similar magnitude. Clearly, both water temperature change and air entrapment must be considered for an accurate assessment of the infiltration rate in basins.

Utilizing the fluidized bed to initiate water treatment on site

International Nuclear Information System (INIS)

Ahmadvand, H.; Germann, G.; Gandee, J.P.; Buehler, V.T.

1995-01-01

Escalating wastewater disposal costs coupled with enforcement of stricter regulations push industrial sites previously without water treatment to treat on site. These sites, inexperienced in water treatment, require a treatment technology that is easily installed, operated, and maintained. The aerobic granular activated carbon (GAC) fluidized bed incorporates biological and adsorptive technologies into a simple, cost-effective process capable of meeting strict effluent requirements. Two case studies at industrial sites illustrate the installation and operation of the fluidized bed and emphasize the ability to use the fluidized bed singularly or as an integral component of a treatment system capable of achieving treatment levels that allow surface discharge and reinjection. Attention is focused on BTEX (benzene, toluene, ethylbenzene, and xylenes)

Effect of 2 Bedding Materials on Ammonia Levels in Individually Ventilated Cages.

Science.gov (United States)

Koontz, Jason M; Kumsher, David M; Kelly, Richard; Stallings, Jonathan D

2016-01-01

This study sought to identify an optimal rodent bedding and cage-change interval to establish standard procedures for the IVC in our rodent vivarium. Disposable cages were prefilled with either corncob or α-cellulose bedding and were used to house 2 adult Sprague-Dawley rats (experimental condition) or contained no animals (control). Rats were observed and intracage ammonia levels measured daily for 21 d. Intracage ammonia accumulation became significant by day 8 in experimental cages containing α-cellulose bedding, whereas experimental cages containing corncob bedding did not reach detectable levels of ammonia until day 14. In all 3 experimental cages containing α-cellulose, ammonia exceeded 100 ppm (our maximum acceptable limit) by day 11. Two experimental corncob cages required changing at days 16 and 17, whereas the remaining cage containing corncob bedding lasted the entire 21 d without reaching the 100-ppm ammonia threshold. These data suggests that corncob bedding provides nearly twice the service life of α-cellulose bedding in the IVC system.

Microwave-assisted synthesis of geopolymers from fluidised bed gasifier bottom ash

CSIR Research Space (South Africa)

Oboirien, BO

2013-09-01

Full Text Available Fluidised bed gasification (FBG) is a clean coal technology suitable for power and fuel generation from low grade coals. However, the resulting bottom ash presents some disposal challenges to the power plants and the environment. The production...

Methodology of safety evaluation about land disposal of low level radioactive wastes

International Nuclear Information System (INIS)

Suzuki, Atsuyuki

1986-01-01

Accompanying the progress of the construction project of low level radioactive waste storage facilities in Aomori Prefecture, the full scale land disposal of low level radioactive wastes shows its symptom also in Japan. In this report, the scientific methodology to explain the safety about the land disposal of low level radioactive wastes is discussed. The land disposal of general wastes by shallow burying has already had sufficient results. In the case of low level radioactive wastes, also the land disposal by shallow burying is considered. Low level radioactive wastes can be regarded as one form of industrial wastes, as there are many common parts in the scientific and theoretical base of the safety. Attention is paid most to the contamination of ground water. Low level radioactive wastes are solid wastes, accordingly the degree of contamination should be less. The space in which ground water existes, the phenomena of ground water movement, the phenomena of ground water dispersion and Fick's law, the adsorption effect of strata, and the evaluation of source term are explained. These are the method to analyze the degree of contamination from safety evaluation viewpoint. (Kako, I.)

Ground rubber: Sorption media for ground water containing benzene and O-xylene

International Nuclear Information System (INIS)

Kershaw, D.S.; Pamukcu, S.

1997-01-01

The purpose of the current study is to examine the ability of ground rubber to sorb benzene and O-xylene from water contained with aromatic hydrocarbons. The study consisted of running both batch and packed bed column tests to determine the sorption capacity, the required sorption equilibration time, and the flow through utilization efficiency of ground rubber under various contact times when exposed to water contaminated with various amounts of benzene or O-xylene. Initial batch test results indicate that ground rubber can attain equilibrium sorption capacities up to 1.3 or 8.2 mg of benzene or O-xylene, respectively, per gram of tire rubber at solution equilibrium concentrations of 10 mg/L. Packed bed column tests indicate that ground tire rubber has on the average a 40% utilization rate when a hydraulic residence time of 15 min is used. Possible future uses of round rubber as a sorption media could include, but are not limited to, the use of ground rubber as an aggregate in slurry cutoff walls that are in contact with petroleum products. Ground rubber could also be used as a sorption media in pump-and-treat methodologies or as a sorption media in in-situ reactive permeable barriers

Analytical Analyses of Spatial and Temporal Characteristics of Infiltrated Water for Managed Aquifer Recharge

Science.gov (United States)

Zlotnik, V. A.; Ledder, G.; Kacimov, A. R.

2014-12-01

Disposal of excessive runoff or treated sewage into wadis and ephemeral streams is a common practice and an important hydrological problem in many Middle Eastern countries. While chemical and biological properties of the injected treated wastewater may be different from those of the receiving aquifer, the density contrast between the two fluids can be small. Therefore, studies of the fluid interface for variable density fluids or water intrusion are not directly relevant in many Managed Aquifer Recharge (MAR) problems. Other factors, such as the transient nature of injection and lack of detailed aquifer information must be considered. The disposed water reaching the water table through the vadose zone creates groundwater mounds, deforms the original water table, and develops finite-size convex-concave lenses of treated water over receiving water. After cessation of infiltration, these mounds flatten, water levels become horizontal, and infiltrated water becomes fully embedded in the receiving aquifer. The shape of the treated water body is controlled by the aquifer parameters, the magnitude of ambient flow, and the duration, rate, and cyclicity of infiltration. In case of limited aquifer data, advective transport modeling offers the most appropriate tools for predicting plume shapes over time, but surprisingly little work has been done on this important 3D flow problem. We investigate the lateral and vertical spreading of infiltrated water combining techniques of spatial velocity analyses by Zlotnik and Ledder (1992, 1993) with particle tracking. This approach allows for evaluating the geometry of the plume and the protection zone, the flow development phases, and other temporal and spatial effects and results can be used in conditions of limited data availability and quality. (Funding was provided by the USAID, DAI Subcontract 1001624-12S-19745)

Guidelines for the selection of sites for disposal of radioactive waste on or beneath the ocean floor

International Nuclear Information System (INIS)

Searle, R.C.

1979-01-01

An assessment of factors which will probably need to be taken into account in selecting potential sites for the disposal of high-level radioactive wastes into geological formations beneath the ocean floor is presented based in part on a survey of available published and unpublished literature. Since present quantitative knowledge concerning the properties and processes of the sea bed and oceanic waters is poor the guidelines are generally stated in qualitative terms and it is hoped that future research will determine acceptable quantitative values for the parameters involved. The subject is dealt with under the headings; introduction, emplacement below the sea-bed, emplacement on the sea-bed, identification of oceanic areas that might prove suitable for disposal of high-level radioactive wastes (discussion limited to the North Atlantic). 30 references. (U.K.)

Selection and investigation of sites for the disposal of radioactive wastes in hydraulically induced subsurface fractures

International Nuclear Information System (INIS)

Sun, R.J.

1982-01-01

Injection of intermediate-level radioactive wastes (specific activity of less than 6 x 10 3 μCi/mL, consisting mainly of radionuclides, such as strontium and cesium, having half-lives of less than 50 years) mixed with cement into a thick shale formation is a promising and feasible disposal method. Hydraulic fracturing provides openings in the shale to accommodate the wastes. Ion exchange and radionuclide-adsorption materials can be added to the grout during mixing to further increase the radionuclide-retaining capacity of the grout. After solidification of the grout, the injected wastes become an integral part of the shale formation, and therefore the wastes will remain at depth and in place as long as the injection zone is not subjected to erosion and dissolution. Problems concerning safety of the disposal method are (1) the potential for inducing vertical fractures, (2) phase separation during and after the injections, (3) the reliability of methods for determining the orientation of induced fractures, (4) the possibility of triggering earthquakes, and (5) radionuclides being leached and transported by ground water. Theoretical considerations about inducing nearly horizontal bedding-plane fractures in shale are discussed, as are field procedures for site selection, safety, and the monitoring and operation of radioactive waste disposal. Case histories are used as examples to demonstrate the application of the theory and techniques of field operations

Greater Confinement Disposal trench and borehole operations status

International Nuclear Information System (INIS)

Harley, J.P. Jr.; Wilhite, E.L.; Jaegge, W.J.

1987-01-01

Greater Confinement Disposal (GCD) facilities have been constructed within the operating burial ground at the Savannah River Plant (SRP) to dispose of the higher activity fraction of SRP low-level waste. GCD practices of waste segregation, packaging, emplacement below the root zone, and waste stabilization are being used in the demonstration. 2 refs., 2 figs., 2 tabs

Biodiversity of seagrass bed in Balanan Resort - Baluran National Park

Science.gov (United States)

Soedarti, T.; Hariyanto, S.; Wedayanti, A.; Rahmawati, A. D.; Safitri, D. P.; Alificia, R. I.; Suwono

2017-09-01

Seagrass beds are flowering plants that live on the seabed. Seagrass provides a habitat for diverse flora and fauna, spawning ground, nursery ground, raising ground, and feeding ground. Balanan Resort - Baluran National Park has many beaches, such as Kajang Beach, Si Banjir Beach, Kakapa Beach, and Serondo Beach. This study was aimed to determine species composition, seagrass dominated, and the diversity index of seagrass and substrate in Resort Balanan - Baluran National Park. This research was carried out in Kajang Beach, Sibanjir Beach, Kakapa Beach, and Sirondo Beach from August to September 2015 using belt transect method, each transect consists of 15 plots (19 transects = 285 plots) and using the frame of 1x1 m. This research found seven genera and ten species : Cymodoce (C rotundata and C. serrulata), Syringodium (S. isoelifolium), Thallassodendron (T. ciliatum), Enhalus (E. acoroides) , Halodule (H. univernis and H. pinifolia), Halophila (H. ovalis and H. decipiens), and Thalassia (T. hemprichii). The diversity index of seagrass bed was moderate [H'=1.90] in Balanan Resort. The substrate of seagrass bed was mud, gravel, sand, clay sand and rubble in Balanan Resort. The dominance index was near zero [C = 0.194], that means no dominant species.

Environmental requirements for radioactive wastes final disposal in shallow ground repositories; Requisitos ambientais para disposicao final de rejeitos radioativos em repositorios de superficie

Energy Technology Data Exchange (ETDEWEB)

Raduan, Rosane Napolitano

1994-12-31

Low and intermediate level radioactive waste confinement have been a well know practice for about five decades. Wastes disposal in shallow ground repositories are originated in the nuclear fuel cycle and the application of isotopes in medicine, industry, research and education and other activities. An adequate choice of sites for repositories constructions is based on a criterions analysis of a series of requirements for environmental impact assessment. This analysis allows, together with physical and chemical parameters of the immobilized and packed radioactive wastes, to carry out this choice. The main objective of this work is to have an overview of principal topics that allows an environment impact analysis resulting from a controlled radioactive waste disposal. (author). 68 refs., 14 figs., 6 tabs.

BedMachine v3: Complete Bed Topography and Ocean Bathymetry Mapping of Greenland From Multibeam Echo Sounding Combined With Mass Conservation

DEFF Research Database (Denmark)

Morlighem, M.; Williams, C. N.; Rignot, E.

2017-01-01

Greenland's bed topography is a primary control on ice flow, grounding line migration, calving dynamics, and subglacial drainage. Moreover, fjord bathymetry regulates the penetration of warm Atlantic water (AW) that rapidly melts and undercuts Greenland's marine‐terminating glaciers. Here we...... present a new compilation of Greenland bed topography that assimilates seafloor bathymetry and ice thickness data through a mass conservation approach. A new 150 m horizontal resolution bed topography/bathymetric map of Greenland is constructed with seamless transitions at the ice/ocean interface...

Disposal of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-01-15

The problem of disposal can be tackled in two ways: the waste can be diluted and dispersed so that the radiation to which any single individual would be subjected would be negligible, or it can be concentrated and permanently isolated from man and his immediate environment. A variety of methods for the discharge of radioactive waste into the ground were described at the Monaco conference. They range from letting liquid effluent run into pits or wells at appropriately chosen sites to the permanent storage of high activity material at great depth in geologically suitable strata. Another method discussed consists in the incorporation of high level fission products in glass which is either buried or stored in vaults. Waste disposal into rivers, harbours, outer continental shelves and the open sea as well as air disposal are also discussed. Many of the experts at the Monaco conference were of the view that most of the proposed, or actually applied, methods of waste disposal were compatible with safety requirements. Some experts, felt that certain of these methods might not be harmless. This applied to the possible hazards of disposal in the sea. There seemed to be general agreement, however, that much additional research was needed to devise more effective and economical methods of disposal and to gain a better knowledge of the effects of various types of disposal operations, particularly in view of the increasing amounts of waste material that will be produced as the nuclear energy industry expands

Infiltration experiment for closure cap evaluation at the Savannah River Site

International Nuclear Information System (INIS)

Roddy, N.S.; Cook, J.R.

1990-01-01

This document discusses several large waste disposal facilities at the Savannah River Site which are being closed. These facilities include two seepage basins and the low-level waste disposal facility. The key element of the closures is the construction of a cap system to limit the infiltration of water which might reach the disposed waste. Cap designs have been modeled using the Hydrologic Evaluation of Landfill Performance (HELP) computer code. This code was developed by the US Army Corps of Engineers for the Environmental Protection Agency to model the effects of various cap and liner designs on the water balance at landfills. A field experiment has been set up which will allow the results of the HELP Code to be verified at the Savannah River Site (SRS) by measuring the actual water balance created by closure cap configurations which will be used in waste site closures at SRS. Two of the caps will be similar to those used for the planned closure activities. Each one has a specific closure arrangement. Once operational, the experiment will be evaluated for a five-year period

Disposal configuration options for future uses of greater confinement disposal at the Nevada Test Site

International Nuclear Information System (INIS)

Price, L.

1994-09-01

The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE's Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada Test Site (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS

On the validity of a Fickian diffusion model for the spreading of liquid infiltration plumes in partially saturated heterogeneous media

International Nuclear Information System (INIS)

Pruess, K.

1994-01-01

Localized infiltration of aqueous and -non-aqueous phase liquids (NAPLs) occurs in many circumstances. Examples include leaky underground pipelines and storage tanks, landfill and disposal sites, and surface spills. Because of ever-present heterogeneities on different scales such infiltration plumes are expected to disperse transversally and longitudinally. This paper examines recent suggestions that liquid plumes are being dispersed from medium heterogeneities in a manner that is analogous to Fickian diffusion. Numerical simulation experiments on liquid infiltration in heterogeneous media are performed to study the dispersive effects of small-scale heterogeneity. It is found that plume spreading indeed tends to be diffusive. Our results suggest that, as far as infiltration of liquids is concerned, broad classes of heterogeneous media behave as dispersive media with locally homogeneous (albeit anisotropic) permeability

Technical considerations in the design of near surface disposal facilities for radioactive waste

International Nuclear Information System (INIS)

2001-11-01

Good design is an important step towards ensuring operational as well as long term safety of low and intermediate level waste (LILW) disposal. The IAEA has produced this report with the objective of outlining the most important technical considerations in the design of near surface disposal facilities and to provide some examples of the design process in different countries. This guidance has been developed in light of experience gained from the design of existing near surface disposal facilities in a range of Member States. In particular the report provide information on design objective, design requirements, and design phases. The report focuses on: near surface disposal facilities accepting solidified LILW; disposal facilities on or just below the ground surface, where the final protective covering is of the order of a few metres thick; and disposal facilities several tens of metres below the ground surface (including rock cavern type facilities)

Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites

Energy Technology Data Exchange (ETDEWEB)

Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W. [Pacific Northwest Lab., Richland, WA (United States)

1996-01-01

This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated.

Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W.

1996-01-01

This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated

Experimental and modelling studies of infiltration

International Nuclear Information System (INIS)

Giudici, M.

2004-01-01

This presentation describes a study of infiltration in the unsaturated soil with the objective of estimating the recharge to a phreatic aquifer. The study area is at the border of the city of Milan (Northern Italy), which draws water for both domestic and industrial purposes from ground water resources located beneath the urban area. The rate of water pumping from the aquifer system has been varying during the XX century, depending upon the number of inhabitants and the development of industrial activities. This caused variations with time of the depth of the water table below the ground surface and in turn some emergencies: the two most prominent episodes correspond to the middle '70s, when the water table in the city centre was about 30 m below the undisturbed natural conditions, and to the last decade, when the water table has raised at a rate of approximately 1 m/year and caused infiltrations in deep constructions (garages and building foundations, the underground railways, etc.). We have developed four ground water flow models at different scales, which share some characteristics: they are based on quasi-3D approximation (horizontal flow in the aquifers and vertical flow in the aquitards), conservative finite-differences schemes for regular grid with square cells in the horizontal plane and are implemented with proprietary computer codes. Among the problems that were studied for the development of these models, I recall some numerical problems, related to the behaviour of the phreatic aquifer under conditions of strong exploitation. Model calibration and validation for ModMil has been performed with a two-stage process, i.e., using some of the available data for model calibration and the remaining data for model validation. The application of geophysical exploration techniques, in particular seismic and geo-electrical prospecting, has been very useful to complete the data and information on the hydro-geological structure obtained from stratigraphic logs

Hanford Site ground-water monitoring for 1993

International Nuclear Information System (INIS)

Dresel, P.E.; Luttrell, S.P.; Evans, J.C.

1994-09-01

This report presents the results of the Ground-Water Surveillance Project monitoring for calendar year 1993 on the Hanford Site, Washington. Hanford Site operations from 1943 onward produced large quantities of radiological and chemical waste that have impacted ground-water quality on the Site. Monitoring of water levels and ground-water chemistry is performed to track the extent of contamination and trends in contaminant concentrations. The 1993 monitoring was also designed to identify emerging ground-water quality problems. The information obtained is used to verify compliance with applicable environmental regulations and to evaluate remedial actions. Data from other monitoring and characterization programs were incorporated to provide an integrated assessment of Site ground-water quality. Additional characterization of the Site's geologic setting and hydrology was performed to support the interpretation of contaminant distributions. Numerical modeling of sitewide ground-water flow also supported the overall project goals. Water-level monitoring was performed to evaluate ground-water flow directions, to track changes in water levels, and to relate such changes to changes in site disposal practices. Water levels over most of the Hanford Site continued to decline between June 1992 and June 1993. The greatest declines occurred in the 200-West Area. These declines are part of the continued response to the cessation of discharge to U Pond and other disposal facilities. The low permeability in this area which enhanced mounding of waste-water discharge has also slowed the response to the reduction of disposal. Water levels remained nearly constant in the vicinity of B Pond, as a result of continued disposal to the pond. Water levels measured from wells in the unconfined aquifer north and east of the Columbia River indicate that the primary source of recharge is irrigation practices

Hanford Site ground-water monitoring for 1993

Energy Technology Data Exchange (ETDEWEB)

Dresel, P.E.; Luttrell, S.P.; Evans, J.C. [and others

1994-09-01

This report presents the results of the Ground-Water Surveillance Project monitoring for calendar year 1993 on the Hanford Site, Washington. Hanford Site operations from 1943 onward produced large quantities of radiological and chemical waste that have impacted ground-water quality on the Site. Monitoring of water levels and ground-water chemistry is performed to track the extent of contamination and trends in contaminant concentrations. The 1993 monitoring was also designed to identify emerging ground-water quality problems. The information obtained is used to verify compliance with applicable environmental regulations and to evaluate remedial actions. Data from other monitoring and characterization programs were incorporated to provide an integrated assessment of Site ground-water quality. Additional characterization of the Site`s geologic setting and hydrology was performed to support the interpretation of contaminant distributions. Numerical modeling of sitewide ground-water flow also supported the overall project goals. Water-level monitoring was performed to evaluate ground-water flow directions, to track changes in water levels, and to relate such changes to changes in site disposal practices. Water levels over most of the Hanford Site continued to decline between June 1992 and June 1993. The greatest declines occurred in the 200-West Area. These declines are part of the continued response to the cessation of discharge to U Pond and other disposal facilities. The low permeability in this area which enhanced mounding of waste-water discharge has also slowed the response to the reduction of disposal. Water levels remained nearly constant in the vicinity of B Pond, as a result of continued disposal to the pond. Water levels measured from wells in the unconfined aquifer north and east of the Columbia River indicate that the primary source of recharge is irrigation practices.

Production of renewable energy from biomass and waste materials using fluidized bed technologies

International Nuclear Information System (INIS)

Rozainee, M.; Rashid, M.; Looi, S.

2000-01-01

Malaysian industries generate substantial amount of biomass and waste materials such as wastes from agricultural and wood based industries, sludge waste from waste-water treatment plants and solid waste from municipals. Incinerating these waste materials not only produces renewable energy, but also solving their disposal problems. Fluidized bed combustors are widely used for incinerating these biomass materials. The significant advantages of fluidized bed incineration include simple design, efficient, and ability to reduce air pollution emissions. This paper discusses the opportunities and challenges of producing the green energy from biomass materials using the fluidized bed technologies. (Author)

Design of fluidized-bed, biological denitrification systems

International Nuclear Information System (INIS)

Patton, B.D.; Hancher, C.W.; Pitt, W.W.; Walker, J.F.

1982-01-01

Many commercial processes yield nitrate-containing wastewaters that are being discharged to the environment because traditional recovery or disposal methods are economically unacceptable. The anticipated discharge limits (i.e., 10 to 20 g (NO 3 - )/m 3 ) being considered by many states will not allow continued release of these wastewaters. The new discharge standards can be met economically by use of the fluidizied-bed, biological denitrification process. Research and development studies were conducted with 0.05-, 0.10-, 0.20-, and 0.50-m-diam fluidized-bed bioreactor systems. Feed nitrate concentrations were in the 0 to 10,000 g (NO 3 - )/m 3 range. Using the data from these studies, rate expressions were developed for the destruction of nitrate as a function of nitrate concentration. Methods were also developed for sizing bioreactors and biomass control systems. The sizing methods for fluidized-bed denitrification systems are described, and support systems such as sampling and analysis, instrumentation and controls, utilities, and bacteria storage are discussed. Operation of the process is also briefly discussed to aid the designer. Using the methods presented in this report, fluidized-bed, biological denitrification systems can be designed to treat nitrate wastewater streams

Seismic tomography Technology for the Water Infiltration Experiment

International Nuclear Information System (INIS)

Descour, J.

2001-01-01

NSA Engineering, Inc., conducted seismic tomography surveys in Niche No.3 in the Exploratory Studies Facility (ESF), Yucca Mountain, Nevada, and Alcove No.8 in the Enhanced Characterization of the Repository Block (ECRB) cross drift as part of the Infiltration Experiment being conducted in Niche No.3. NSA Engineering is a direct support contractor to the Yucca Mountain Project. This report documents the work performed from August 14 through 30, 2000, prior to the beginning of the infiltration experiment. The objective of the seismic tomography survey was to investigate the flow path of water between access drifts and more specifically to (Kramer 2000): (1) Conduct a baseline seismic tomography survey prior to the infiltration experiment; (2) Produce 2-D and 3-D tomographic images of the rock volume between Alcove No.8 and Niche No.3; (3) Correlate tomography results with published structural and lithological features, and with other geophysical data such as ground penetrating radar (GPR); and (4) Results of this survey will form a baseline with which to compare subsequent changes to the rock mass. These changes may be as a result of the water infiltration tests that could be conducted in Alcove No.8 in 2001. The scope of this reported work is to use the velocity tomograms to: (a) assess the structures and lithologic features within the surveyed area and/or volume between the two access drifts; and (b) provide information on the structural state of the rock mass as inferred by the velocity signatures of the rock prior to the beginning of the infiltration experiment

Bibliography of PNL publications in management of radioactive wastes, subject-indexed (alphabetically) and listed chronologically (latest issues first)

International Nuclear Information System (INIS)

Powell, J.A.

1976-07-01

The citations are arranged under: actinides, alpha particles, americium, beta particles, calcination, cements, ceramics, cesium, containers, decontamination, evaporation, fluidized bed, glass, ground release, high-level wastes, incinerators, liquid wastes, marine disposal, melting, nonradioactive waste disposal, Pu, radiation doses, radiation protection, disposal, processing, radionuclide migration, Ru, safety, separation processes, soils, solidification, solid wastes, stack disposal, temperature, thermal conductivity, transmutation, tritium, underground disposal, U, volatility, and waste disposal/management/processing/storage/transportation

Disposal phase experimental program plan

International Nuclear Information System (INIS)

1997-01-01

The Waste Isolation Pilot Plant (WIPP) facility comprises surface and subsurface facilities, including a repository mined in a bedded salt formation at a depth of 2,150 feet. It has been developed to safely and permanently isolate transuranic (TRU) radioactive wastes in a deep geological disposal site. On April 12, 1996, the DOE submitted a revised Resource Conservation and Recovery Act (RCRA) Part B permit application to the New Mexico Environment Department (NMED). The DOE anticipates receiving an operating permit from the NMED; this permit is required prior to the start of disposal operations. On October 29, 1996, the DOE submitted a Compliance Certification Application (CCA) to the US Environmental Protection Agency (EPA) in accordance with the WIPP land Withdrawal Act (LWA) of 1992 (Public Law 102-579) as amended, and the requirements of Title 40 of the Code of Federal Regulations (40 CFR) Parts 191 and 194. The DOE plans to begin disposal operations at the WIPP in November 1997 following receipt of certification by the EPA. The disposal phase is expected to last for 35 years, and will include recertification activities no less than once every five years. This Disposal Phase Experimental Program (DPEP) Plan outlines the experimental program to be conducted during the first 5-year recertification period. It also forms the basis for longer-term activities to be carried out throughout the 35-year disposal phase. Once the WIPP has been shown to be in compliance with regulatory requirements, the disposal phase gives an opportunity to affirm the compliance status of the WIPP, enhance the operations of the WIPP and the national TRU system, and contribute to the resolution of national and international nuclear waste management technical needs. The WIPP is the first facility of its kind in the world. As such, it provides a unique opportunity to advance the technical state of the art for permanent disposal of long-lived radioactive wastes

Ground-water levels and precipitation data at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky, October 1988-September 2000

Science.gov (United States)

Zettwoch, Douglas D.

2002-01-01

The U.S. Geological Survey, in cooperation with the Kentucky Natural Resources and Environmental Protection Cabinet--Department for Environmental Protection--Division of Waste Management, has an ongoing program to monitor water levels at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky. Ground-water-level and precipitation data were collected from 112 wells and 1 rain gage at the Maxey Flats low-level radioactive waste disposal site during October 1988-September 2000. Data were collected on a semi-annual basis from 62 wells, continuously from 6 wells, and monthly or bimonthly from 44 wells (13 of which had continuous recorders installed for the period October 1998-September 2000). One tipping-bucket rain gage was used to collect data at the Maxey Flats site for the period October 1988-September 2000.

Humic substances in ground waters

International Nuclear Information System (INIS)

Paxeus, N.; Allard, B.; Olofsson, U.; Bengtsson, M.

1986-01-01

The presence of naturally occurring complexing agents that may enhance the migration of disposed radionuclikes and thus facilitate their uptake by plantsis a problem associated with the underground disposal of radioactive wastes in bedrock. The main purpose of this work is to characterized humic substances from ground water and compare them with humic substances from surface water. The humic materials isolated from ground waters of a borehole in Fjaellveden (Sweden) were characterized by elemental and functional group analyses. Spectroscopic properties, molecular weight distributions as well as acid-base properties of the fulvic and humic fractions were also studied. The ground water humic substances were found to be quite similar in many respects (but not identical) to the Swedish surface water humics concentrated from the Goeta River but appeared to be quite different from the American ground water humics from Biscayne Florida Aquifer or Laramie Fox-Hills in Colorado. The physico-chemical properties of the isolated humic materials are discussed

Performance evaluation and phylogenetic characterization of anaerobic fluidized bed reactors using ground tire and pet as support materials for biohydrogen production.

Science.gov (United States)

Barros, Aruana Rocha; Adorno, Maria Angela Tallarico; Sakamoto, Isabel Kimiko; Maintinguer, Sandra Imaculada; Varesche, Maria Bernadete Amâncio; Silva, Edson Luiz

2011-02-01

This study evaluated two different support materials (ground tire and polyethylene terephthalate [PET]) for biohydrogen production in an anaerobic fluidized bed reactor (AFBR) treating synthetic wastewater containing glucose (4000 mg L(-1)). The AFBR, which contained either ground tire (R1) or PET (R2) as support materials, were inoculated with thermally pretreated anaerobic sludge and operated at a temperature of 30°C. The AFBR were operated with a range of hydraulic retention times (HRT) between 1 and 8h. The reactor R1 operating with a HRT of 2h showed better performance than reactor R2, reaching a maximum hydrogen yield of 2.25 mol H(2)mol(-1) glucose with 1.3mg of biomass (as the total volatile solids) attached to each gram of ground tire. Subsequent 16S rRNA gene sequencing and phylogenetic analysis of particle samples revealed that reactor R1 favored the presence of hydrogen-producing bacteria such as Clostridium, Bacillus, and Enterobacter. Copyright © 2010 Elsevier Ltd. All rights reserved.

Nuclear waste disposal: technology and environmental hazards

International Nuclear Information System (INIS)

Hare, F.K.; Aikin, A.M.

1980-01-01

The subject is discussed under the headings: introduction; the nature and origin of wastes (fuel cycles; character of wastes; mining and milling operations; middle stages; irradiated fuel; reprocessing (waste generation); reactor wastes); disposal techniques and disposal of reprocessing wastes; siting of repositories; potential environmental impacts (impacts after emplacement in a rock repository; catastrophic effects; dispersion processes (by migrating ground water); thermal effects; future security; environmental survey, monitoring and modelling); conclusion. (U.K.)

Sewage Sludge Disposal with Energy Recovery by Fluidized Bed Gasification and CHP-Units

Energy Technology Data Exchange (ETDEWEB)

Horst, J.; Gross, B.; Kimmerle, K. [Inst. fuer ZukunftsEnergieSysteme, Saarbruecken (Germany); Eder, C. [Christian Eder Technology e.K., Neunkirchen (Germany)

2006-07-15

Sewage sludge is a composition of by-products collected during the different stages of the waste water cleaning process of communal and industrial treatment plants. Because of its harmful impacts on environment as well as animals - and mankind - health sewage sludge has become a problem. Therefore disposal of sludge is today on a crossroad depending on the discussion about soil contamination by using the sludge as fertiliser. Some countries are now abandoning disposal to agriculture and are entering into thermal treatment with the argument: 'Harmful substances already separated with high financial effort should definitely be removed from the food cycle and should not return indirectly via the fields to food and water'. The SEDIS project - a project funded by the European Commission under the specific research and technological development programme 'Promotion of innovation and encouragement of SME participation' - is aimed at eliminating the rising disposal problem of sewage sludge by an energy-related use of the raw sludge directly on site of wastewater treatment plants. SEDIS is developing an innovative, self-sustaining system to process liquid and pasty waste such as sewage sludge and solid biomass to utilise product-gas for power-generation direct on site. This process is called ETVS-process and is patented by Christian Eder Technology e.K. Today, where each company has to look for sustainable savings, the SEDIS concept offers a decentralised process, self-sustaining from other energy sources and able to provide the whole treatment plant with energy. Furthermore the treatment plant would be independent of price policy of sludge disposers.

Investigation plan for infiltration experiment in Olkiluoto

International Nuclear Information System (INIS)

Lehtinen, A.; Lindgren, S.; Ikonen, A.

2008-11-01

A three-year field experiment to investigate potential changes in pH and redox conditions, and in buffering capacity as well as the hydrogeochemical processes related to groundwater infiltration is designed for implementation in the vicinity of ONKALO. The idea is to monitor the major infiltration flow path from the ground surface into the upper part of ONKALO at about 50 to 100 m depth depending on the observations made during the experiment. The geochemical evolution of the groundwater is strongly affected by infiltration from the surface. In natural conditions in Olkiluoto most of the geochemical reactions occur along the first few tens of metres of the flow path, in an interface between anaerobic and aerobic conditions. The dissolved aggressive agents, CO 2 and O 2 , of the infiltrating water are consumed and the hydrogeochemistry stabilises on neutral and anaerobic conditions due to weathering processes. As a consequence of this evolution, reaction fronts are formed in the flow channels between acid-neutral and aerobic-anaerobic interfaces. The construction of ONKALO may, however, increase the hydraulic gradient and flow into bedrock, which can move these fronts to deeper depths and decrease the buffering capacity of the rock fractures against surficial water infiltration. Detailed integration of hydrogeochemical (including microbiology), geological and hydrogeological studies is essential for a successful experiment. Accurate hydrogeochemical and hydrogeological data that will be collected during this experiment are used in coupled modelling exercises (P/O studies in site reports), which will be carried out to evaluate the movements of the reaction fronts and the buffering capacity of Olkiluoto bedrock against surficial water infiltration. Good quality information is also necessary for calibrating predictive calculations for the safety case estimating future evolution of the site. In addition to the geochemical targets, the experiment can be used in

Sensitivity of MRI in detecting alveolar infiltrates. Experimental studies

International Nuclear Information System (INIS)

Biederer, J.; Busse, I.; Grimm, J.; Reuter, M.; Heller, M.; Muhle, C.; Freitag, S.

2002-01-01

Purpose: An experimental study using porcine lung explants and a dedicated chest phantom to evaluate the signal intensity of artificial alveolar infiltrates with T 1 - and T 2 -weighted MRI sequences. Material and Methods: 10 porcine lung explants were intubated, transferred into the cavity of a MRI-compatible chest phantom and inflated by continuous evacuation of the artificial pleural space. All lungs were examined with MRI at 1.5 T before and after intra-tracheal instillation of either 100 or 200 ml gelatine-stabilised liquid to simulate alveolar infiltrates. MR-examination comprised gradient echo (2D- and 3D-GRE) and fast spin echo sequences (T 2 -TSE and T 2 -HASTE). The signal intensity of lung parenchyma was evaluated at representative cross sections using a standardised scheme. Control studies were acquired with helical CT. Results: The instilled liquid caused patchy confluent alveolar infiltrates resembling the findings in patients with pneumonia or ARDS. CT revealed typical ground-glass opacities. Before the application of the liquid, only T 2 -HASTE and T 2 -TSE displayed lung parenchyma signals with a signal/noise ratio of 3.62 and 1.39, respectively. After application of the liquid, both T 2 -weighted sequences showed clearly visible infiltrates with an increase in signal intensity of approx. 30% at 100 ml (p 2 -weighted sequences detects artificial alveolar infiltrates with high signal intensity and may be a highly sensitive tool to detect pneumonia in patients. (orig.) [de

Hanford Site ground-water monitoring for 1994

International Nuclear Information System (INIS)

Dresel, P.E.; Thorne, P.D.; Luttrell, S.P.

1995-08-01

This report presents the results of the Ground-Water Surveillance Project monitoring for calendar year 1994 on the Hanford Site, Washington. Hanford Site operations from 1943 onward produced large quantities of radiologic and chemical waste that have impacted ground-water quality on the Site. Monitoring of water levels and ground-water chemistry is performed to track the extent of contamination and trends in contaminant concentrations. The 1994 monitoring was also designed to identify emerging ground-water quality problems. The information obtained is used to verify compliance with applicable environmental regulations and to evaluate remedial actions. Data from other monitoring and characterization programs were incorporated to provide an integrated assessment of Site ground-water quality. Additional characterization of the Site's geologic setting and hydrology was performed to support the interpretation of contaminant distributions. Numerical modeling of sitewide ground-water flow also supported the overall project goals. Water-level monitoring was performed to evaluate ground-water flow directions, to track changes in water levels, and to relate such changes to changes in site disposal practices. Water levels over most of the Hanford Site continued to decline between June 1993 and June 1994. These declines are part of the continued response to the cessation of discharge to U Pond and other disposal facilities. The low permeability in this area which enhanced mounding of waste-water discharge has also slowed the response to the reduction of disposal

Hanford Site ground-water monitoring for 1994

Energy Technology Data Exchange (ETDEWEB)

Dresel, P.E.; Thorne, P.D.; Luttrell, S.P. [and others

1995-08-01

This report presents the results of the Ground-Water Surveillance Project monitoring for calendar year 1994 on the Hanford Site, Washington. Hanford Site operations from 1943 onward produced large quantities of radiologic and chemical waste that have impacted ground-water quality on the Site. Monitoring of water levels and ground-water chemistry is performed to track the extent of contamination and trends in contaminant concentrations. The 1994 monitoring was also designed to identify emerging ground-water quality problems. The information obtained is used to verify compliance with applicable environmental regulations and to evaluate remedial actions. Data from other monitoring and characterization programs were incorporated to provide an integrated assessment of Site ground-water quality. Additional characterization of the Site`s geologic setting and hydrology was performed to support the interpretation of contaminant distributions. Numerical modeling of sitewide ground-water flow also supported the overall project goals. Water-level monitoring was performed to evaluate ground-water flow directions, to track changes in water levels, and to relate such changes to changes in site disposal practices. Water levels over most of the Hanford Site continued to decline between June 1993 and June 1994. These declines are part of the continued response to the cessation of discharge to U Pond and other disposal facilities. The low permeability in this area which enhanced mounding of waste-water discharge has also slowed the response to the reduction of disposal.

The disposal of radioactive waste on land

Energy Technology Data Exchange (ETDEWEB)

None

1957-09-01

A committee of geologists and geophysicists was established by the National Academy of Sciences-National Research Council at the request of the Atomic Energy Commission to consider the possibilities of disposing of high level radioactive wastes in quantity within the continental limits of the United States. The group was charged with assembling the existing geologic information pertinent to disposal, delineating the unanswered problems associated with the disposal schemes proposed, and point out areas of research and development meriting first attention; the committee is to serve as continuing adviser on the geological and geophysical aspects of disposal and the research and development program. The Committee with the cooperation of the Johns Hopkins University organized a conference at Princeton in September 1955. After the Princeton Conference members of the committee inspected disposal installations and made individual studies. Two years consideration of the disposal problems leads to-certain general conclusions. Wastes may be disposed of safely at many sites in the United States but, conversely, there are many large areas in which it is unlikely that disposal sites can be found, for example, the Atlantic Seaboard. Disposal in cavities mined in salt beds and salt domes is suggested as the possibility promising the most practical immediate solution of the problem. In the future the injection of large volumes of dilute liquid waste into porous rock strata at depths in excess of 5,000 feet may become feasible but means of rendering, the waste solutions compatible with the mineral and fluid components of the rock must first be developed. The main difficulties, to the injection method recognized at present are to prevent clogging of pore space as the solutions are pumped into the rock and the prediction or control of the rate and direction of movement.

Alternative methods of salt disposal at the seven salt sites for a nuclear waste repository

International Nuclear Information System (INIS)

1987-02-01

This study discusses the various alternative salt management techniques for the disposal of excess mined salt at seven potentially acceptable nuclear waste repository sites: Deaf Smith and Swisher Counties, Texas; Richton and Cypress Creek Domes, Mississippi; Vacherie Dome, Louisiana; and Davis and Lavender Canyons, Utah. Because the repository development involves the underground excavation of corridors and waste emplacement rooms, in either bedded or domed salt formations, excess salt will be mined and must be disposed of offsite. The salt disposal alternatives examined for all the sites include commercial use, ocean disposal, deep well injection, landfill disposal, and underground mine disposal. These alternatives (and other site-specific disposal methods) are reviewed, using estimated amounts of excavated, backfilled, and excess salt. Methods of transporting the excess salt are discussed, along with possible impacts of each disposal method and potential regulatory requirements. A preferred method of disposal is recommended for each potentially acceptable repository site. 14 refs., 5 tabs

Modified technology in new constructions, and cost effective remedial action in existing structures, to prevent infiltration of soil gas carrying radon

International Nuclear Information System (INIS)

Ericson, S.O.; Schmid, H.; Clavensjo, B.

1984-01-01

The general principles and mechanisms of how soil gas carrying radon infiltrates from the foundation bed and subsoil into buildings are discussed. The Swedish Building Research Council has funded experiments and evaluations of cost effective remedial actions. The work has concerned existing dwellings with high concentration of radon where this is a result of infiltrating soil gas and/or exhalation from building materials. A review is given of experience and results acquired up to the summer of 1983. 100 dwellings have been erected with consideration of possible infiltration of soil gas. Modification of design, added costs (investment and operation) and resulting concentration of radon in indoor air is discussed. In general minor modifications are sufficient. (author)

An adaptable, low cost test-bed for unmanned vehicle systems research

Science.gov (United States)

Goppert, James M.

2011-12-01

An unmanned vehicle systems test-bed has been developed. The test-bed has been designed to accommodate hardware changes and various vehicle types and algorithms. The creation of this test-bed allows research teams to focus on algorithm development and employ a common well-tested experimental framework. The ArduPilotOne autopilot was developed to provide the necessary level of abstraction for multiple vehicle types. The autopilot was also designed to be highly integrated with the Mavlink protocol for Micro Air Vehicle (MAV) communication. Mavlink is the native protocol for QGroundControl, a MAV ground control program. Features were added to QGroundControl to accommodate outdoor usage. Next, the Mavsim toolbox was developed for Scicoslab to allow hardware-in-the-loop testing, control design and analysis, and estimation algorithm testing and verification. In order to obtain linear models of aircraft dynamics, the JSBSim flight dynamics engine was extended to use a probabilistic Nelder-Mead simplex method. The JSBSim aircraft dynamics were compared with wind-tunnel data collected. Finally, a structured methodology for successive loop closure control design is proposed. This methodology is demonstrated along with the rest of the test-bed tools on a quadrotor, a fixed wing RC plane, and a ground vehicle. Test results for the ground vehicle are presented.

Municipal solid-waste disposal and ground-water quality in a coastal environment, west-central Florida

Science.gov (United States)

Fernandez, Mario

1983-01-01

Solid waste is defined along with various methods of disposal and the hydrogeologic factors to be considered when locating land-fills is presented. Types of solid waste, composition, and sources are identified. Generation of municipal solid waste in Florida has been estimated at 4.5 pounds per day per person or about 7.8 million tons per year. Leachate is generated when precipitation and ground water percolate through the waste. Gases, mainly carbon dioxide and methane, are also produced. Leachate generally contains high concentrations of dissolved organic and inorganic matter. The two typical hydrogeologic conditions in west-central Florida are (1) permeable sand overlying clay and limestone and (2) permeable sand overlying limestone. These conditions are discussed in relation to leachate migration. Factors in landfill site selection are presented and discussed, followed by a discussion on monitoring landfills. Monitoring of landfills includes the drilling of test holes, measuring physical properties of the corings, installation of monitoring wells, and water-quality monitoring. (USGS)

Use of engineered soils and other site modifications for low-level radioactive waste disposal

International Nuclear Information System (INIS)

1994-08-01

The U.S. Nuclear Regulatory Commission requires that low-level radioactive waste (LLW) disposal facilities be designed to minimize contact between waste and infiltrating water through the use of site design features. The purpose of this investigation is to identify engineered barriers and evaluate their ability to enhance the long-term performance of an LLW disposal facility. Previously used barriers such as concrete overpacks, vaults, backfill, and engineered soil covers, are evaluated as well as state-of-the-art barriers, including an engineered sorptive soil layer underlying a facility and an advanced design soil cover incorporating a double-capillary layer. The purpose of this investigation is also to provide information in incorporating or excluding specific engineered barriers as part of new disposal facility designs. Evaluations are performed using performance assessment modeling techniques. A generic reference disposal facility design is used as a baseline for comparing the improvements in long-term performance offered by designs incorporating engineered barriers in generic and humid environments. These evaluations simulate water infiltration through the facility, waste leaching, radionuclide transport through the facility, and decay and ingrowth. They also calculate a maximum (peak annual) dose for each disposal system design. A relative dose reduction factor is calculated for each design evaluated. The results of this investigation are presented for concrete overpacks, concrete vaults, sorptive backfill, sorptive engineered soil underlying the facility, and sloped engineered soil covers using a single-capillary barrier and a double-capillary barrier. Designs using combinations of barriers are also evaluated. These designs include a vault plus overpacks, sorptive backfill plus overpacks, and overpack with vault plus sorptive backfill, underlying sorptive soil, and engineered soil cover

Mapping Sargassum beds off, ChonBuri Province, Thailand, using ALOS AVNI2 image

Science.gov (United States)

Noiraksar, Thidarat; Komatsu, Teruhisa; Sawayama, Shuhei; Phauk, Sophany; Hayashizaki, Ken-ichi

2012-10-01

Sargassum species grow on rocks and dead corals and form dense seaweed beds. Sargassum beds play ecological roles such as CO2 uptake and O2 production through photosynthesis, spawning and nursery grounds of fish, feeding ground for sea urchins and abalones, and substrates for attached animals and plants on leaves and holdfasts. However, increasing human impacts and climate change decrease or degrade Sargassum beds in ASEAN countries. It is necessary to grasp present spatial distributions of this habitat. Thailand, especially its coastal zone along the Gulf of Thailand, is facing degradation of Sargassum beds due to increase in industries and population. JAXA launched non-commercial satellite, ALOS, providing multiband images with ultra-high spatial resolution optical sensors (10 m), AVNIR2. Unfortunately, ALOS has terminated its mission in April 2011. However, JAXA has archived ALOS AVNIR2 images over the world. They are still useful for mapping coastal ecosystems. We examined capability of remote sensing with ALOS AVNIR2 to map Sargassum beds in waters off Sattahip protected area as a natural park in Chon Buri Province, Thailand, threatened by degradation of water quality due to above-mentioned impacts. Ground truth data were obtained in February 2012 by using continual pictures taken by manta tow. Supervised classification could detect Sargassum beds off Sattahip at about 70% user accuracy. It is estimated that error is caused by mixel effect of bottom substrates in a pixel with 10 x 10 m. Our results indicate that ALOS AVNIR2 images are useful for mapping Sargassum beds in Southeast Asia.

Subsurface disposal of liquid low-level radioactive wastes at Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Stow, S.H.; Haase, C.S.

1986-01-01

At Oak Ridge National Laboratory (ORNL) subsurface injection has been used to dispose of low-level liquid nuclear waste for the last two decades. The process consists of mixing liquid waste with cement and other additives to form a slurry that is injected under pressure through a cased well into a low-permeability shale at a depth of 300 m. The slurry spreads from the injection well along bedding plane fractures and forms solid grout sheets of up to 200 m in radius. Using this process, ORNL has disposed of over 1.5 x 10 6 Ci of activity; the principal nuclides are 90 Sr and 137 Cs. In 1982, a new injection facility was put into operation. Each injection, which lasts some two days, results in the emplacement of approximately 750,000 liters of slurry. Disposal cost per liter is about $0.30, including capital costs of the facility. This subsurface disposal process is fundamentally different from other operations. Wastes are injected into a low-permeability aquitard, and the process is designed to isolate nuclides, preventing dispersion in groundwaters. The porosity into which wastes are injected is created by hydraulically fracturing the host formation along bedding planes. Investigations are under way to determine the long-term hydrologic isolation of the injection zone and the geochemical impact of saline groundwater on nuclide mobility. Injections are monitored by gamma-ray logging of cased observation wells to determine grout sheet orientation after an injection. Recent monitoring work has involved the use of tiltmeters, surface uplift surveys, and seismic arrays. Recent regulatory constraints may cause permanent cessation of the operation. Federal and state statutes, written for other types of injection facilities, impact the ORNL facility. This disposal process, which may have great applicability for disposal of many wastes, including hazardous wastes, may not be developed for future use

Calculations of the radiological impact of disposal of unit activity of selected radionuclides for use in waste management system studies

International Nuclear Information System (INIS)

Smith, G.M.

1985-03-01

The purpose of the work described is to provide estimates of the radiological impact following disposal of unit activity via each of several options, including shallow burial, engineered trench disposal, disposal in a geologic repository and disposal on the deep ocean bed. Results are presented for a range of important representative radionuclides. No single option is clearly the best from the radiological point of view. However, in conjunction with waste inventory data the results may be used to provide a preliminary view of the relative radiological merits of the various disposal options. (author)

Taiwan industrial cooperation program technology transfer for low-level radioactive waste final disposal - phase I.

Energy Technology Data Exchange (ETDEWEB)

Knowlton, Robert G.; Cochran, John Russell; Arnold, Bill Walter; Jow, Hong-Nian; Mattie, Patrick D.; Schelling, Frank Joseph Jr. (; .)

2007-01-01

Sandia National Laboratories and the Institute of Nuclear Energy Research, Taiwan have collaborated in a technology transfer program related to low-level radioactive waste (LLW) disposal in Taiwan. Phase I of this program included regulatory analysis of LLW final disposal, development of LLW disposal performance assessment capabilities, and preliminary performance assessments of two potential disposal sites. Performance objectives were based on regulations in Taiwan and comparisons to those in the United States. Probabilistic performance assessment models were constructed based on limited site data using software including GoldSim, BLT-MS, FEHM, and HELP. These software codes provided the probabilistic framework, container degradation, waste-form leaching, groundwater flow, radionuclide transport, and cover infiltration simulation capabilities in the performance assessment. Preliminary performance assessment analyses were conducted for a near-surface disposal system and a mined cavern disposal system at two representative sites in Taiwan. Results of example calculations indicate peak simulated concentrations to a receptor within a few hundred years of LLW disposal, primarily from highly soluble, non-sorbing radionuclides.

Impact of recharge through residual oil upon sampling of underlying ground water

International Nuclear Information System (INIS)

Wise, W.R.; Chang, Chichung; Klopp, R.A.; Bedient, P.B.

1991-01-01

At an aviation gasoline spill site in Traverse City, Michigan, historical records indicate a positive correlation between significant rainfall events and increased concentrations of slightly soluble organic compounds in the monitoring wells of the site. To investigate the recharge effect on ground water quality due to infiltrating water percolating past residual oil and into the saturated zone, an in situ infiltration experiment was performed at the site. Sampling cones were set at various depths below a circular test area, 13 feet (4 meters) in diameter. Rainfall was simulated by sprinkling the test area at a rate sufficiently low to prevent runoff. The sampling cones for soil-gas and ground water quality were installed in the unsaturated and saturated zones to observed the effects of the recharge process. Infiltrated water was determined to have transported organic constituents of the residual oil, specifically benzene, toluene, ethylbenzene, and ortho-xylene (BTEX), into the ground water beneath the water table, elevating the aqueous concentrations of these constituents in the saturated zone. Soil-gas concentrations of the organic compounds in the unsaturated zone increased with depth and time after the commencement of infiltration. Reaeration of the unconfined aquifer via the infiltrated water was observed. It is concluded that water quality measurements are directly coupled to recharge events for the sandy type of aquifer with an overlying oil phase, which was studied in this work. Ground water sampling strategies and data analysis need to reflect the effect of recharge from precipitation on shallow, unconfined aquifers where an oil phase may be present

Climate considerations

International Nuclear Information System (INIS)

Hutchinson, I.P.G.; Ellison, R.D.

1992-01-01

The purpose of this paper is to investigate the conditions under which rainfall and snowmelt result in infiltration, percolation, and leachate formation, and to develop guidelines for incorporating these processes into the mine waste disposal regulations. This is important because in mine waste, and under certain circumstances, these processes can result in conditions which pose a threat to surface and ground water quality. This paper provides a general overview of infiltration, percolation, and leachate formation. It incorporates a discussion of the methods that can be used to quantify infiltration and the climatic and physical site and waste conditions under which percolation and leachate formation occur. Reference is made to case histories on infiltration, ground water recharge, and analytical procedures for calculating infiltration. An approach to infiltration prediction is outlined, and the paper concludes with a discussion on how climatic factors and prediction of infiltration could be incorporated into the regulations

Electrodialysis reversal: Process and cost approximations for treating coal-bed methane waters

Energy Technology Data Exchange (ETDEWEB)

Sajtar, E.T.; Bagley, D.M. [University of Wyoming, Laramie, WY (United States)

2009-02-15

Brackish waters with total dissolved solids (TDS) concentrations less than 10,000 mg/L are extracted from coal-beds in the Wyoming Powder River basin to facilitate the production of coal-bed methane. These waters frequently require treatment before disposal or use. Electrodialysis reversal (EDR) has not yet been used to treat these waters but this technology should be suitable. The question is whether EDR would be cost-effective. The purpose of this work, then, was to develop models for predicting the cost of EDR for brackish waters. These models, developed from data available in the literature, were found to predict actual EDR costs as a function of TDS removal, influent flow rate, chemical rejection efficiency, water recovery, electricity use, and labor cost within 10% of reported values. The total amortized cost for removing 1,000 mg/L of TDS from 10,000 m{sup 3}/day of influent assuming no concentrate disposal costs was predicted to range from $0.23/m{sup 3} to $0.85/m{sup 3} and was highly dependent on capital cost and facility life. Concentrate disposal costs significantly affected total treatment cost, providing a total treatment cost range from $0.38/m{sup 3} to $6.38/m{sup 3}, depending on concentrate disposal cost and water recovery. Pilot demonstrations of EDR in the Powder River basin should be conducted to determine the achievable water recovery when treating these waters.

Tritium waste disposal technology in the US

International Nuclear Information System (INIS)

Albenesius, E.L.; Towler, O.A.

1983-01-01

Tritium waste disposal methods in the US range from disposal of low specific activity waste along with other low-level waste in shallow land burial facilities, to disposal of kilocurie amounts in specially designed triple containers in 65' deep augered holes located in an aird region of the US. Total estimated curies disposed of are 500,000 in commercial burial sites and 10 million curies in defense related sites. At three disposal sites in humid areas, tritium has migrated into the ground water, and at one arid site tritium vapor has been detected emerging from the soil above the disposal area. Leaching tests on tritium containing waste show that tritium in the form of HTO leaches readily from most waste forms, but that leaching rates of tritiated water into polymer impregnated concrete are reduced by as much as a factor of ten. Tests on improved tritium containment are ongoing. Disposal costs for tritium waste are 7 to 10 dollars per cubic foot for shallow land burial of low specific activity tritium waste, and 10 to 20 dollars per cubic foot for disposal of high specific activity waste. The cost of packaging the high specific activity waste is 150 to 300 dollars per cubic foot. 18 references

Test bed for applications of heterogeneous unmanned vehicles

Directory of Open Access Journals (Sweden)

Filiberto Muñoz Palacios

2017-01-01

Full Text Available This article addresses the development and implementation of a test bed for applications of heterogeneous unmanned vehicle systems. The test bed consists of unmanned aerial vehicles (Parrot AR.Drones versions 1 or 2, Parrot SA, Paris, France, and Bebop Drones 1.0 and 2.0, Parrot SA, Paris, France, ground vehicles (WowWee Rovio, WowWee Group Limited, Hong Kong, China, and the motion capture systems VICON and OptiTrack. Such test bed allows the user to choose between two different options of development environments, to perform aerial and ground vehicles applications. On the one hand, it is possible to select an environment based on the VICON system and LabVIEW (National Instruments or robotics operating system platforms, which make use the Parrot AR.Drone software development kit or the Bebop_autonomy Driver to communicate with the unmanned vehicles. On the other hand, it is possible to employ a platform that uses the OptiTrack system and that allows users to develop their own applications, replacing AR.Drone’s original firmware with original code. We have developed four experimental setups to illustrate the use of the Parrot software development kit, the Bebop Driver (AutonomyLab, Simon Fraser University, British Columbia, Canada, and the original firmware replacement for performing a strategy that involves both ground and aerial vehicle tracking. Finally, in order to illustrate the effectiveness of the developed test bed for the implementation of advanced controllers, we present experimental results of the implementation of three consensus algorithms: static, adaptive, and neural network, in order to accomplish that a team of multiagents systems move together to track a target.

Burnup performance of OTTO cycle pebble bed reactors with ROX fuel

International Nuclear Information System (INIS)

Ho, Hai Quan; Obara, Toru

2015-01-01

Highlights: • A 300 MW t Small Pebble Bed Reactor with Rock-like oxide fuel is proposed. • Using ROX fuel can achieve high discharged burnup of spent fuel. • High geological stability can be expected in direct disposal of the spent ROX fuel. • The Pebble Bed Reactor with ROX fuel can be critical at steady state operation. • All the reactor designs have a negative temperature coefficient. - Abstract: A pebble bed high-temperature gas-cooled reactor (PBR) with rock-like oxide (ROX) fuel was designed to achieve high discharged burnup and improve the integrity of the spent fuel in geological disposal. The MCPBR code with a JENDL-4.0 library, which developed the analysis of the Once-Through-Then-Out (OTTO) cycle in PBR, was used to perform the criticality and burnup analysis. Burnup calculations for eight cases were carried out for both ROX fuel and a UO 2 fuel reactor with different heavy-metal loading conditions. The effective multiplication factor of all cases approximately equalled unity in the equilibrium condition. The ROX fuel reactor showed lower FIFA than the UO 2 fuel reactor at the same heavy-metal loading, about 5–15%. However, the power peaking factor and maximum power per fuel ball in the ROX fuel core were lower than that of UO 2 fuel core. This effect makes it possible to compensate for the lower-FIFA disadvantage in a ROX fuel core. All reactor designs had a negative temperature coefficient that is needed for the passive safety features of a pebble bed reactor

Radioactive waste disposal: an international law perspective

International Nuclear Information System (INIS)

Barrie, G.N.

1989-01-01

The question of radioactive waste disposal is the most intractable technical and political problem facing nuclear industry. Environmentalists world-wide demand a nuclear waste policy that must be ecologically acceptable internationally. Radioactive wastes and oil pollution were the first two types of marine pollution to receive international attention and various marine pollution controls were established. Ocean disposal was co-ordinated by the Nuclear Energy Agency and the Organization of Economic Co-operation and Development in 1967. The first treaty was the 1958 Convention on the High Seas (High Seas Convention). In response to its call for national co-operation the International Atomic Energy Agency (IAEA) established its Brynielson panel. The IAEA first issued guidelines on sea dumping in 1961. The London Dumping Convention, written in 1972, is the only global agreement concerned solely with the disposal of wastes in the marine environment by dumping. None of the global agreements make specific reference to sea-bed disposal of high-level radioactive wastes. Negotiations began at the Third UN Conference on the Law of the Sea (UNCLOS III) for the codification of a comprehensive treaty concerned with the protection, conservation, sustainable use and development of the marine environment. Burial in deep geological formations is a method of HLW disposal which decreases the chances of accidental intrusion by mankind and has little likelihood of malicious intrusion. National waste management programmes of different countries differ but there is agreement on the acceptable technical solutions to issues of waste management. The final disposition of HLW - storage or disposal - has not been decisively determined, but there is growing consensus that geological land-based disposal is the most viable alternative. Expanded international technical co-operation could well reduce the time needed to develop effective waste disposal mechanisms

Performance Assessment of a Generic Repository in Bedded Salt for DOE-Managed Nuclear Waste

Science.gov (United States)

Stein, E. R.; Sevougian, S. D.; Hammond, G. E.; Frederick, J. M.; Mariner, P. E.

2016-12-01

A mined repository in salt is one of the concepts under consideration for disposal of DOE-managed defense-related spent nuclear fuel (SNF) and high level waste (HLW). Bedded salt is a favorable medium for disposal of nuclear waste due to its low permeability, high thermal conductivity, and ability to self-heal. Sandia's Generic Disposal System Analysis framework is used to assess the ability of a generic repository in bedded salt to isolate radionuclides from the biosphere. The performance assessment considers multiple waste types of varying thermal load and radionuclide inventory, the engineered barrier system comprising the waste packages, backfill, and emplacement drifts, and the natural barrier system formed by a bedded salt deposit and the overlying sedimentary sequence (including an aquifer). The model simulates disposal of nearly the entire inventory of DOE-managed, defense-related SNF (excluding Naval SNF) and HLW in a half-symmetry domain containing approximately 6 million grid cells. Grid refinement captures the detail of 25,200 individual waste packages in 180 disposal panels, associated access halls, and 4 shafts connecting the land surface to the repository. Equations describing coupled heat and fluid flow and reactive transport are solved numerically with PFLOTRAN, a massively parallel flow and transport code. Simulated processes include heat conduction and convection, waste package failure, waste form dissolution, radioactive decay and ingrowth, sorption, solubility limits, advection, dispersion, and diffusion. Simulations are run to 1 million years, and radionuclide concentrations are observed within an aquifer at a point approximately 4 kilometers downgradient of the repository. The software package DAKOTA is used to sample likely ranges of input parameters including waste form dissolution rates and properties of engineered and natural materials in order to quantify uncertainty in predicted concentrations and sensitivity to input parameters. Sandia

Simulation of aquifer tests and ground-water flowpaths at the local scale in fractured shales and sandstones of the Brunswick Group and Lockatong Formation, Lansdale, Montgomery County, Pennsylvania

Science.gov (United States)

Goode, Daniel J.; Senior, Lisa A.

2000-01-01

The U.S. Geological Survey, as part of technical assistance to the U.S. Environmental Protection Agency, has constructed and calibrated models of local-scale ground-water flow in and near Lansdale, Pa., where numerous sources of industrial contamination have been consolidated into the North Penn Area 6 Superfund Site. The local-scale models incorporate hydrogeologic structure of northwest-dipping beds with uniform hydraulic properties identified in previous studies. Computations associated with mapping the dipping-bed structure into the three-dimensional model grid are handled by a preprocessor using a programmed geographic information system (GIS). Hydraulic properties are identified by calibration of the models using measured water levels during pumping and recovery from aquifer tests at three sites. Reduced flow across low-permeability beds is explicitly simulated. The dipping high-permeability beds are extensive in the strike direction but are of limited extent in the dip direction. This model structure yields ground-water-flow patterns characteristic of anisotropic aquifers; preferred flow is in the strike direction. The transmissivities of high-permeability beds in the local-scale models range from 142 to 1,900 ft2/d (feet squared per day) (13 to 177 m2/d). The hydraulic conductivities of low-permeability parts of the aquifer range from 9.6 x 10-4 to 0.26 ft/d (feet per day) (2.9 x 10-4 to 0.079 m/d). Storage coefficients and specific storage are very low, indicating the confined nature of the aquifer system. The calibrated models are used to simulate contributing areas of wells under alternative, hypothetical ground-water-management practices. Predictive contributing areas indicate the general characteristics of ground-water flow towards wells in the Lansdale area. Recharge to wells in Lansdale generally comes from infiltration near the well and over an area that extends upgradient from the well. The contributing areas for two wells pumping at 10 gal

Vegetation growth patterns on six rock-covered UMTRA Project disposal cells

International Nuclear Information System (INIS)

1992-02-01

This study assessed vegetation growth patterns, the potential impacts of vegetation growth on disposal cell cover integrity, and possible measures that could be taken to monitor and/or control plant growth, where necessary, on six Uranium Mill Tailings Remedial Action (UMTRA) Project rock-covered disposal cells. A large-scale invasion of volunteer plants was observed on the Shiprock and Burrell disposal cells. Plant growth at the South Clive, Green River, and Tuba City disposal cells was sparse except for the south rock apron and south slope of the Tuba City disposal cell, where windblown sand had filled up part of the rock cover and plant growth was observed. The rock-covered topslope of the Collins Ranch disposal cell was intentionally covered with topsoil and vegetated. Plant roots growing on the disposal cells are changing the characteristics of the cover by drying out the radon barrier, encouraging the establishment of soil-building processes in the bedding and radon barrier layers, creating channels in the radon barrier, and facilitating ecological succession, which could lead to the establishment of additional deep-rooted plants on the disposal cells. If left unchecked, plant roots would reach the tailings at the Burrell and Collins Ranch disposal cells within a few years, likely resulting in the transport of contaminants out of the cells

Water infiltration and heat transfer in one dimensional unsaturated packed beds; Fuhowa ryushi sonai no ichijigen suibun nagare to dennetsu tokusei

Energy Technology Data Exchange (ETDEWEB)

Aoki, K; Akahori, M; Hattori, M [Nagaoka University of Technology, Niigata (Japan); Shiraishi, N [Toshiba Corp., Tokyo (Japan)

1998-05-25

Water and heat transport in unsaturated packed beds due to supplying hot water have been investigated experimentally and theoretically. Using various sizes of glass beads, capillary pressure and permeability in packed beds were measured in unsaturated beds. The distributions in water saturation and temperature were predicted for one dimensional packed bed, based on a model assuming local thermal equilibrium among water, gas and particles at any specific space. The predicted temperature distributions were compared with the experimental results obtained using various glass sizes. In layered packed beds, water saturation becomes discontinuous at the interface of two layers because of the difference of the water characteristics between two beds. Water penetrates faster in coarse-over fine-textured profile compared with in fine-over coarse-textured profile. Similarly, the temperature rises faster in former profile under the same supplied heat quantity. 11 refs., 13 figs., 1 tab.

Discharge of treated wastewater from drilling exploratory wells by infiltration of hydrocarbons in the ground; Vertido de aguas residuales tratadas provenientes de pozos de perforacion exploratoria de hidrocarburos mediante la infiltracion en el terreno

Energy Technology Data Exchange (ETDEWEB)

Rodriguez Miranda, J. P.

2009-07-01

The discharge of treated waste water from a well drilling exploratory oil, such as the consideration ser out to determine the minimum area needed to saturate the ground is not where he planned the infiltration of the dumping in special conditions of soil type and permeability, limited space, water quality and influence of underground aquifers in the study area. (Author) 16 refs.

Characterization and Application of a Disposable Rotating Bed Bioreactor for Mesenchymal Stem Cell Expansion.

Science.gov (United States)

Neumann, Anne; Lavrentieva, Antonina; Heilkenbrinker, Alexandra; Loenne, Maren; Kasper, Cornelia

2014-11-27

Recruitment of mesenchymal stromal cells (MSC) into the field of tissue engineering is a promising development since these cells can be expanded vivo to clinically relevant numbers and, after expansion, retain their ability to differentiate into various cell lineages. Safety requirements and the necessity to obtain high cell numbers without frequent subcultivation of cells raised the question of the possibility of expanding MSC in one-way (single-use) disposable bioreactors. In this study, umbilical cord-derived MSC (UC-MSC) were expanded in a disposable Z 2000 H bioreactor under dynamic conditions. Z was characterized regarding residence time and mixing in order to evaluate the optimal bioreactor settings, enabling optimal mass transfer in the absence of shear stress, allowing an reproducible expansion of MSC, while maintaining their stemness properties. Culture of the UC-MSC in disposable Z 2000 H bioreactor resulted in a reproducible 8-fold increase of cell numbers after 5 days. Cells were shown to maintain specific MSC surface marker expression as well as trilineage differentiation potential and lack stress-induced premature senescence.

Characterization and Application of a Disposable Rotating Bed Bioreactor for Mesenchymal Stem Cell Expansion

Directory of Open Access Journals (Sweden)

Anne Neumann

2014-11-01

Full Text Available Recruitment of mesenchymal stromal cells (MSC into the field of tissue engineering is a promising development since these cells can be expanded vivo to clinically relevant numbers and, after expansion, retain their ability to differentiate into various cell lineages. Safety requirements and the necessity to obtain high cell numbers without frequent subcultivation of cells raised the question of the possibility of expanding MSC in one-way (single-use disposable bioreactors. In this study, umbilical cord-derived MSC (UC-MSC were expanded in a disposable Z 2000 H bioreactor under dynamic conditions. Z was characterized regarding residence time and mixing in order to evaluate the optimal bioreactor settings, enabling optimal mass transfer in the absence of shear stress, allowing an reproducible expansion of MSC, while maintaining their stemness properties. Culture of the UC-MSC in disposable Z 2000 H bioreactor resulted in a reproducible 8-fold increase of cell numbers after 5 days. Cells were shown to maintain specific MSC surface marker expression as well as trilineage differentiation potential and lack stress-induced premature senescence.

Incineration of Sludge in a Fluidized-Bed Combustor

OpenAIRE

Chien-Song Chyang; Yu-Chi Wang

2017-01-01

For sludge disposal, incineration is considered to be better than direct burial because of regulations and space limitations in Taiwan. Additionally, burial after incineration can effectively prolong the lifespan of a landfill. Therefore, it is the most satisfactory method for treating sludge at present. Of the various incineration technologies, the fluidized bed incinerator is a suitable choice due to its fuel flexibility. In this work, sludge generated from industrial plants was treated in ...

Groundwater flow modeling for near-field of a hypothetical near-surface disposal facility

International Nuclear Information System (INIS)

Park, H. Y.; Park, J. W.; Jang, G. M.; Kim, C. R.

2000-01-01

For a hypothetical near-surface radioactive disposal facility, the behavior of groundwater flow around the near-field of disposal vault located at the unsaturated zone were analyzed. Three alternative conceptual models proposed as the hydraulic barrier layer design were simulated to assess the hydrologic performance of engineered barriers for the facility. In order to evaluate the seepage possibility of the infiltrated water passed through the final disposal cover after the facility closure, the flow path around and water flux through each disposal vault were compared. The hydrologic parameters variation that accounts for the long-term aging and degradation of the cover and engineered materials was considered in the simulations. The results showed that it is necessary to construct the hydraulic barrier at the upper and sides of the vault, and that, for this case, achieving design hydraulic properties of bentonite/sand mixture barrier in the as-built condition is crucial to limit the seepage into the waste

Relative Impacts of Low Permeability Subsurface Deposits on Recharge Basin Infiltration Rates

Science.gov (United States)

Oconnell, P.; Becker, M.; Pham, C.; Rodriguez, G.; Hutchinson, A.; Plumlee, M.

2017-12-01

Artificial recharge of aquifers through spreading basins has become an important component of water management in semi-arid climates. The rate at which water can be recharged in these basins is limited by the natural vertical permeability of the underlying deposits which may be highly variable both laterally and vertically. To help understand hydrostratigraphic controls on recharge, a newly constructed basin was surveyed and instrumented. Prior to flooding the basin, lithology was characterized by shallow hand coring, direct push coring, ground penetrating radar, and electrical resistivity. After flooding, recharge was monitored through piezometers, electrical resistivity, and a network of fiber optic distributed temperature sensing (DTS). The DTS network used temperature as a tracer to measure infiltration rate on 25 cm intervals both laterally and vertically. Several hundred paired DTS time series datasets (from fiber optic cables located at 0 and 0.5 meters below ground surface) were processed with the cross-wavelet transform (XWT) to calculate spatially and temporally continuous infiltration rates, which can be interpolated and animated to visualize heterogeneity. Time series data from 8-meter deep, vertically oriented DTS cables reveal depth intervals where infiltration rates vary. Inverted resistivity sections from repeated dipole-dipole surveys along the sidewall of a spreading basin exhibit a positive correlation with the distribution of relatively high and low infiltration rates, indicating zones of preferential downward (efficient) and lateral (inefficient) flow, respectively. In contrast to other monitored basins, no perching was observed in the vertically oriented DTS cables. The variation in recharge across the basin and the appearance of subsurface lateral flow can be explained in context of the alluvial depositional environment.

Practical Guidelines for Water Percolation Capacity Determination of the Ground

Directory of Open Access Journals (Sweden)

Mihael Brenčič

2011-06-01

Full Text Available Determination of water infiltration capacity of ground soils and rocks represents important part of design and construction procedures of the facilities for the infiltration of clean precipitation water. With their help percolation capacity of ground as well as response of the infiltration facilities to the inflowing precipitation water is estimated.Comparing to other in situ hydrogeological tests they can be understood as simple. However, in every day’s practiceseveral problems during their on site application and desk interpretation can arise. Paper represents review of existingpractical engineering procedures during the performance of percolation tests. Procedures are described for the borehole and shaft percolation tests execution and calculation theory for stationary and non‑stationary percolation tests are given. Theory is illustrated with practical exercises. Interpretations of typical departures from theoretical presumptions according to Hvorslev test of non-stationary test are illustrated.

Circulating fluidized bed boilers design and operations

CERN Document Server

Basu, Prabir

1991-01-01

This book provides practicing engineers and students with insight into the design and operation of circulating fluidized bed (CFB) boilers. Through a combination of theoretical concepts and practical experience, this book gives the reader a basic understanding of the many aspects of this subject.Important environmental considerations, including solid waste disposal and predicted emissions, are addressed individually in separate chapters. This book places an emphasis on combustion, hydrodynamics, heat transfer, and material issues, and illustrates these concepts with numerous examples of pres

Foreign experience in alpha-contaminated waste disposal

International Nuclear Information System (INIS)

Lakey, P.

1982-01-01

The European presentations provided some useful comparisons with the situation int he United States regarding the transuranic (TRU) waste limit. First, in Europe, there appears to be a more moderate view on intrusion compared to the preoccupation in United States with this issue. Second, and superficially, in the United Kingdom and France, the working limit for near-surface disposal is greater than 10 nCi/g and more like 100 nCi/g. Looking beneath the superficial, however, the important difference is that their limits are working limits; they are not cast in bronze like the 10 nCi/g US value is not perceived to be. Europeans seem to have a more flexible and practical view of the issue and have reserved for its solution a rather large middle ground that appears to be lacking in the US position. For example, the United Kingdom is moving actively toward a version of greater confinement disposal or engineered disposal at a greater depth (with plutonium numbers like 10 4 nCi/g projected) and then moving on to the modified mine with limits like 10 5 nCi/g. From the French presentations, limits like 10 3 nCi/g were discussed. As we debate the TRU limit issue, what we seem to hear is an argument between the advocates of a generic limit of perhaps 100 nCi/g and the arguments for site-specific limits. This debate clouds perhaps the more basic issue of the need for a middle ground disposal approach between the extremes of a room trash limit and geologic disposal

Design of the disposal facility 2012

International Nuclear Information System (INIS)

Saanio, T.; Ikonen, A.; Keto, P.; Kirkkomaeki, T.; Kukkola, T.; Nieminen, J.; Raiko, H.

2013-11-01

The spent nuclear fuel accumulated from the nuclear power plants in Olkiluoto in Eurajoki and in Haestholmen in Loviisa will be disposed of in Olkiluoto. A facility complex will be constructed at Olkiluoto, and it will include two nuclear waste facilities according to Government Degree 736/2008. The nuclear waste facilities are an encapsulation plant, constructed to encapsulate spent nuclear fuel and a disposal facility consisting of an underground repository and other underground rooms and above ground service spaces. The repository is planned to be excavated to a depth of 400 - 450 meters. Access routes to the disposal facility are an inclined access tunnel and vertical shafts. The encapsulated fuel is transferred to the disposal facility in the canister lift. The canisters are transferred from the technical rooms to the disposal area via central tunnel and deposited in the deposition holes which are bored in the floors of the deposition tunnels and are lined beforehand with compacted bentonite blocks. Two parallel central tunnels connect all the deposition tunnels and these central tunnels are inter-connected at regular intervals. The solution improves the fire safety of the underground rooms and allows flexible backfilling and closing of the deposition tunnels in stages during the operational phase of the repository. An underground rock characterization facility, ONKALO, is excavated at the disposal level. ONKALO is designed and constructed so that it can later serve as part of the repository. The goal is that the first part of the disposal facility will be constructed under the building permit phase in the 2010's and operations will start in the 2020's. The fuel from 4 operating reactors as well the fuel from the fifth nuclear power plant under construction, has been taken into account in designing the disposal facility. According to the information from TVO and Fortum, the amount of the spent nuclear fuel is 5,440 tU. The disposal facility is being excavated

Effect of the settlement of sediments on water infiltration in two urban infiltration basins

OpenAIRE

LASSABATERE, Laurent; ANGULO JARAMILLO, R; GOUTALAND, David; LETELLIER, Laetitia; GAUDET, JP; WINIARSKI, Thierry; DELOLME, C

2010-01-01

The sealing of surfaces in urban areas makes storm water management compulsory. The suspended solids from surface runoff water accumulate in infiltration basins and may impact on water infiltration. This paper describes a study of the effect of the settlement of sedimentary layers on the water infiltration capacity of two urban infiltrations basins. In situ water infiltration experiments were performed (1) to quantify the effect of sediment on water infiltration at local scale and (2) to deri...

Structural evaluation of WIPP disposal room raised to Clay Seam G

International Nuclear Information System (INIS)

Park, Byoung Yoon; Holland, John F.

2004-01-01

This report summarizes a series of structural calculations that examine effects of raising the Waste Isolation Pilot Plant repository horizon from the original design level upward 2.43 meters. These calculations allow evaluation of various features incorporated in conceptual models used for performance assessment. Material presented in this report supports the regulatory compliance re-certification, and therefore begins by replicating the calculations used in the initial compliance certification application. Calculations are then repeated for grid changes appropriate for the new horizon raised to Clay Seam G. Results are presented in three main areas: 1. Disposal room porosity, 2. Disturbed rock zone characteristics, and 3. Anhydrite marker bed failure. No change to the porosity surface for the compliance re-certification application is necessary to account for raising the repository horizon, because the new porosity surface is essentially identical. The disturbed rock zone evolution and devolution are charted in terms of a stress invariant criterion over the regulatory period. This model shows that the damage zone does not extend upward to MB 138, but does reach MB 139 below the repository. Damaged salt would be expected to heal in nominally 100 years. The anhydrite marker beds sustain states of stress that promote failure and substantial marker bed deformation into the room assures fractured anhydrite will sustain in the proximity of the disposal rooms

Control and prevention of seepage from uranium mill waste disposal facilities

International Nuclear Information System (INIS)

Williams, R.E.

1978-01-01

This paper constitutes an analysis of the technologies which are available for the prevention of movement of waste waters out of uranium mill waste disposal facilities via sub-surface routes. Hydrogeologic criteria for potential uranium mill waste disposal sites and mathematical modeling of contaminant migration in ground water are presented. Methods for prevention of seepage from uranium mill waste disposal facilities are investigated: liners, clay seals, synthetic polymeric membranes (PVC, polyethylene, chlorinated polyethylene, hypalon, butyl rubber, neoprene, elasticized polyolefin)

Stability of disposal rooms during waste retrieval

International Nuclear Information System (INIS)

Brandshaug, T.

1989-03-01

This report presents the results of a numerical analysis to determine the stability of waste disposal rooms for vertical and horizontal emplacement during the period of waste retrieval. It is assumed that waste retrieval starts 50 years after the initial emplacement of the waste, and that access to and retrieval of the waste containers take place through the disposal rooms. It is further assumed that the disposal rooms are not back-filled. Convective cooling of the disposal rooms in preparation for waste retrieval is included in the analysis. Conditions and parameters used were taken from the Nevada Nuclear Waste Storage Investigation (NNWSI) Project Site Characterization Plan Conceptual Design Report (MacDougall et al., 1987). Thermal results are presented which illustrate the heat transfer response of the rock adjacent to the disposal rooms. Mechanical results are presented which illustrate the predicted distribution of stress, joint slip, and room deformations for the period of time investigated. Under the assumption that the host rock can be classified as ''fair to good'' using the Geomechanics Classification System (Bieniawski, 1974), only light ground support would appear to be necessary for the disposal rooms to remain stable. 23 refs., 28 figs., 2 tabs

The opalinus clay project - disposal of medium and highly-active nuclear wastes

International Nuclear Information System (INIS)

Mueller, U.

2003-01-01

This article describes the project to demonstrate the feasibility of disposing of long-living medium-active and highly-radioactive nuclear wastes in sedimentary rock in Switzerland. The disposal tasks to be carried out are reviewed and the solutions proposed are described, including short-term handling, intermediate storage and final disposal of low, medium and highly-active wastes. The present state of affairs is described and, in particular, the feasibility of implementing a final storage facility in the opalinus clay beds to be found in northern Switzerland. The project for such a facility in the wine-growing area of the canton of Zurich is described in detail, including the storage concept, the technology to be used and operational aspects as well as questions of safety

Modeling of waste/near field interactions for a waste repository in bedded salt: the Dynamic Network (DNET) model

International Nuclear Information System (INIS)

Cranwell, R.M.

1983-01-01

The Fuel Cycle Risk Analysis Division of Sandia National Laboratories has been funded by the US Nuclear Regulatory Commission to develop a methodology for use in assessing the long-term risk from the disposal of radioactive wastes in deep geologic formations. As part of this program, the Dynamic Network (DNET) model was developed to investigate waste/near field interactions associated with the disposal of radioactive wastes in bedded salt formations. The model is a quasi-multi-dimensional network model with capabilities for simulating processes such as fluid flow, heat transport, salt dissolution, salt creep, and the effects of thermal expansion and subsedence on the rock units surrounding the repository. The use of DNET has been demonstrated in the analysis of a hypothetical disposal site containing a bedded salt formation as the host medium for the repository. An example of this demonstration analysis is discussed. Furthermore, the outcome of sensitivity analyses performed on the DNET model are presented

PENGARUH MASSA JENIS PARTIKEL DAN KETINGGIAN PARTIKEL TERHADAP FENOMENA FLUIDISASI DALAM FLUIDIZED BED DENGAN MENGGUNAKAN CFD

Directory of Open Access Journals (Sweden)

Rosyida Permatasari

2016-12-01

Full Text Available Fenomena fluidisasi pada fluidized bed yaitu kecepatan minimum dan tekanan statis partikel merupakan hal fenomena yang penting dalam desain fluidized bed. Fenomena-fenomena tersebut dipengaruhi oleh banyak faktor dalam fluidized bed diantaranya massa jenis dan tinggi partikel di dalam fluidized bed. Penelitian ini menggunakan jenis partikel yang berbeda-beda dan rasio ketinggian partikel terhadap diameter fluidized bed (H/D dengan menggunakan Computational Fluid Dynamics. Partikel yang digunakan adalah partikel dengan jenis Geldart B yaitu glass beads (ρ=2600 kg/m3, ground walnut shell (ρ=1200 kg/m3 dan ground corncob (ρ=800 kg/m3, sedangkan rasio ketinggian partikel yang digunakan yaitu 0.5, 1, 1.5, 2, dan 2.5. Hasil penelitian menunjukkan bahwa massa jenis partikel berbanding lurus dengan kecepatan minimum fluidisasi dan ketinggian partikel tidak mempengaruhi kecepatan minimum fluidisasi.

Control of water infiltration into near surface LLW disposal units - progress report on field experiments at a Humid Region Site, Beltsville, Maryland

International Nuclear Information System (INIS)

O'Donnell, E.; Ridky, R.W.; Schulz, R.K.

1990-01-01

Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated. They are: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g. clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained the conductive layer will wick water around the capillary break. Below grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry to waste and without institutional care. These various concepts are being assessed in six large (70 x 45 x 10 each) lysimeters at Beltsville, Maryland. 6 refs., 21 figs

International Space Station Sustaining Engineering: A Ground-Based Test Bed for Evaluating Integrated Environmental Control and Life Support System and Internal Thermal Control System Flight Performance

Science.gov (United States)

Ray, Charles D.; Perry, Jay L.; Callahan, David M.

2000-01-01

As the International Space Station's (ISS) various habitable modules are placed in service on orbit, the need to provide for sustaining engineering becomes increasingly important to ensure the proper function of critical onboard systems. Chief among these are the Environmental Control and Life Support System (ECLSS) and the Internal Thermal Control System (ITCS). Without either, life onboard the ISS would prove difficult or nearly impossible. For this reason, a ground-based ECLSS/ITCS hardware performance simulation capability has been developed at NASA's Marshall Space Flight Center. The ECLSS/ITCS Sustaining Engineering Test Bed will be used to assist the ISS Program in resolving hardware anomalies and performing periodic performance assessments. The ISS flight configuration being simulated by the test bed is described as well as ongoing activities related to its preparation for supporting ISS Mission 5A. Growth options for the test facility are presented whereby the current facility may be upgraded to enhance its capability for supporting future station operation well beyond Mission 5A. Test bed capabilities for demonstrating technology improvements of ECLSS hardware are also described.

The effectiveness of bed bathing practices on skin integrity and hospital-acquired infections among adult patients

DEFF Research Database (Denmark)

Veje, Pia; Larsen, Palle

2014-01-01

is: What is the effectiveness of traditional towel bed bath practice compared to other innovate bed bath practices on maintaining skin integrity, skin barrier function and reduction of pathogen microbial counts on skin among adult patients in all settings? Inclusion criteria: Types of participants...... practices, including all bag bath interventions, not limited to any specific type or brand. For the purpose of this systematic review, bag bath interventions include bathing patients with pre-packaged disposal washcloths by use of a different cloth to wash each part of the patient's body. The washcloths...... typically comprise rayon/polyester cloth pre-moistened with an evaporating no-rinse cleanser and emollients. Comparator: The comparator is the traditional bed bath (towel bed bath) intervention, regardless of type and frequency. For the purposes of this systematic review, traditional bed bath refers...

Disposal facility for radioactive wastes

International Nuclear Information System (INIS)

Utsunomiya, Toru.

1985-01-01

Purpose: To remove heat generated from radioactive wastes thereby prevent the working circumstances from being worsened in a disposal-facility for radioactive wastes. Constitution: The disposal-facility comprises a plurality of holes dug out into the ground inside a tunnel excavated for the storage of radioactive wastes. After placing radioactive wastes into the shafts, re-filling materials are directly filled with a purpose of reducing the dosage. Further, a plurality of heat pipes are inserted into the holes and embedded within the re-filling materials so as to gather heat from the radioactive wastes. The heat pipes are connected to a heat exchanger disposed within the tunnel. As a result, heating of the solidified radioactive wastes itself or the containing vessel to high temperature can be avoided, as well as thermal degradation of the re-filling materials and the worsening in the working circumstance within the tunnel can be overcome. (Moriyama, K.)

The cost of engineered disposal facilities

International Nuclear Information System (INIS)

Mallory, C.W.; Razor, J.E.; Mills, D.

1987-01-01

An improved disposal trench was designed, constructed and placed into operation at the Maxey Flats Disposal Site during the period April 1985 through July 1986. With the improved trench design, the waste packages are placed in clusters and the surrounding space is filled with gravel and grouted with a sand/cement mixture to form walls and cells that surround the waste package. The walls provide structural support for a poly-ethylene reinforced soil beam which in turn supports a multi-layer protective cap. About 2,700 drums of waste (20,250 CF) were placed into the trench. The total cost of the improved trench was $193,500 and the unit cost was $9.56 per cubic foot not including the placement of the waste. The engineered features of the trench (i.e., sidewall infiltration barrier, grout backfill and the soil beam) cost $82,600 for a unit cost of $4.08 per cubic foot of waste. This is compared to the cost of concrete cannisters used for radioactive waste disposal. On a production basis the cannisters are estimated to cost about $1,260. Depending upon the type waste, the cost of the cannisters will range from $2 to $12 per cubic foot of waste. The slightly higher cost of the concrete cannisters is offset by certain performance advantages

A Prospective, Multicenter Study to Compare a Disposable, High-fluid Capacity Underpad to Nonpermeable, Disposable, Reusable Containment Products on Incontinence-associated Dermatitis Rates Among Skilled Nursing Facility Residents.

Science.gov (United States)

Motta, Glenda; Milne, Catherine T

2017-12-01

Due to the high prevalence of incontinence among skilled nursing facility (SNF) residents, incontinence-associated derma- titis (IAD) is a common occurrence. In addition, facility staff may mistakenly identify IAD as a pressure injury. A prospective, descriptive, multicenter study was conducted in 3 Connecticut facilities to evaluate the effect of substituting a disposable, high- uid capacity underpad for nonpermeable disposable and reusable containment products on the rate of IADs. Residents with and without IAD but with high IAD risk scores who were bed- or chairbound or ambulatory and used disposable nonpermeable briefs and underpads or reusable, laundered containment products when in bed longer than 2 hours were randomly enrolled and observed for a 4-week period. Facility staff were trained on the importance of differentiating between IAD and pressure injury; they substituted the study product (a disposable, high- uid capacity underpad) for all previously used containment products. Patient risk for IAD and skin condition were assessed using the Perineal Assessment Tool (PAT) and the Skin Condition Assessment Tool (SAT), respectively, at 5 time points: baseline, week 1, week 2, week 3, and week 4. The PAT is a 4-item instrument based conceptually on the 4 determinants in perineal skin breakdown; subscales are rated from 1 (least risk) to 3 (most risk), with a total score range of 4 to 12. The SAT is used to evaluate IAD speci cally, generating a cumulative severity score ranging from 0 to 3 on area of skin affected, degree of redness, and depth of ero- sion. Final data analysis was conducted on 40 residents: 25 had IAD present at enrollment and 15 were deemed high risk for developing IAD. Mean SAT scores in the 25 participants with IAD decreased with signi cance at week 1 (P = .0016), week 2 (P = .0023), week 3 (P = .0005), and week 4 (P disposable, high- uid capacity underpad improved SAT scores over time. IAD rates increased in each facility, but pressure

Long-term surveillance plan for the Burro Canyon disposal cell, Slick Rock, Colorado

International Nuclear Information System (INIS)

1998-05-01

This long-term surveillance plan (LTSP) describes the US Department of Energy (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Burro Canyon disposal cell in San Miguel County, Colorado. The US Nuclear Regulatory Commission (NRC) developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Burro Canyon disposal cell. The general license becomes effective when the NRC concurs with the DOE's determination that remedial action is complete at the Burro Canyon disposal cell and the NRC formally accepts this LTSP. Attachment 1 contains the concurrence letters from NRC. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Burro Canyon disposal cell performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. Ground water monitoring will not be required at the Burro Canyon disposal cell because the ground water protection strategy is supplemental standards based on low yield from the uppermost aquifer

Ground-water hydrology and subsurface migration of radioisotopes at a low-level solid radioactive-waste disposal site, West Valley, New York

International Nuclear Information System (INIS)

Prudic, D.E.; Randall, A.D.

1979-01-01

Burial trenches for disposal of solid radioactive waste at West Valley, NY, are excavated in till that has very low hydraulic conductivity (about 5 x 10 -8 centimeters per second). Fractures and root tubes with chemically oxidized and/or reduced soil in their walls extend 3 to 4.5 meters below natural land surface. Preliminary simulations of pressure heads with a digital model suggest that hydraulic conductivity is an order of magnitude greater in the fractured till near land surface than at greater depth. Hydraulic gradients are predominantly downward, even beneath small valleys. The upper part of a body of underlying lacustrine silt is unsaturated; in the lower, saturated part, slow lateral flow may occur. In the older trenches, water began to build up in 1971, overflowed briefly in 1975, and was pumped out in 1975--76. Water levels rose abruptly during major rainstorms in mid-1975, indicating rapid infiltration through cracks in the cover material. The new trenches have maintained low, stable water levels, perhaps because of thicker, more compact cover and less waste settlement; pressure heads near these trenches are low, locally approaching zero, perhaps because of slight infiltration and limited near-surface storage. Peak tritium concentrations in test-hole cores (generally 10 -5 to 10 -3 microcuries per milliliter) were found within 3 meters of land surface and are attributed to surface contamination. Concentrations declined rapidly with depth within the fractured till; secondary peaks found at about 9 meters in three holes are attributed to lateral migration from trenches. Other radioisotopes were detected only near land surface. Samples from the walls of shallow fractures revealed no accumulation of radioisotopes

Ground-water hydrology and subsurface migration of radioisotopes at a low-level solid radioactive-waste disposal site, West Valley, New York

International Nuclear Information System (INIS)

Prudic, D.E.; Randall, A.D.

1977-07-01

Burial trenches for disposal of solid radioactive waste at West Valley, N.Y. are excavated in till that has very low hydraulic conductivity (about 5 x 10 -8 centimeters per second). Fractures and root tubes with chemically oxidized and(or) reduced soil in their walls extend 3 to 4.5 meters below natural land surface. Preliminary simulations of pressure heads with a digital model suggest that hydraulic conductivity is an order of magnitude greater in the fractured till near land surface than at greater depth. Hydraulic gradients are predominantly downward, even beneath small valleys. The upper part of a body of underlying lacustrine silt is unsaturated; in the lower, saturated part, slow lateral flow may occur. In the older trenches, water began to build up in 1971, overflowed briefly in 1975, and was pumped out in 1975--76. Water levels rose abruptly during major rainstorms in mid-1975, indicating rapid infiltration through cracks in the cover material. The new trenches have maintained low, stable water levels, perhaps because of thicker, more compact cover and less waste settlement; pressure heads near these trenches are low, locally approaching zero, perhaps because of slight infiltration and limited near-surface storage. Peak tritium concentrations in test-hole cores (generally 10 -5 to 10 -3 microcuries per milliliter) were found within 3 meters of land surface and are attributed to surface contamination. Concentrations declined rapidly with depth within the fractured till; secondary peaks found at about 9 meters in three holes are attributed to lateral migration from trenches. Other radioisotopes were detected only near land surface. Samples from the walls of shallow fractures revealed no accumulation of radioisotopes

Pulverized coal vs. circulating fluidized bed: An economic comparison

International Nuclear Information System (INIS)

Johns, R.F.

1991-01-01

As the power industry looks to the 1990s for expanded steam generation capacity, boiler owners will continue on their long-standing assignment to evaluate and select the best, lowest cost alternative to meet their energy needs. For coal-fired plants, this evaluation process includes pulverized coal-fired boilers (PC) and circulating fluidized bed boilers (CFB). The cost difference between these products is site specific and depends on several variables, including: Boiler size, pressure, and temperature; Operating variables, such as the cost for fuel, auxiliary power, SO 2 reagent, and ash disposal; Capital cost; and Financial variables, such as evaluation period and interest rate. This paper provides a technical and economic comparison between a pulverized coal-fired boiler and circulating fluidized bed boiler

Low level tank waste disposal study

Energy Technology Data Exchange (ETDEWEB)

Mullally, J.A.

1994-09-29

Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

Low level tank waste disposal study

International Nuclear Information System (INIS)

Mullally, J.A.

1994-01-01

Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site

Hydrologic information needs for evaluating waste disposal options

Energy Technology Data Exchange (ETDEWEB)

Huff, D.D.

1983-01-01

Before waste disposal options can be assessed, an objective or set of criteria for evaluation must be established. For hydrologists, the objective is to ensure that ground water and surface water do not become contaminated beyond acceptable limits as a result of waste disposal operations. The focus here is on the information required to quantify hydrologic transport of potential contaminants from the disposal site. It is important to recognize that the composition of the waste, its physical and chemical form, and the intended disposal methods (e.g., surface spreading, incineration, shallow land burial, or interment in a deep geologic repository) must either be specified a priori or set forth as specific options for evaluation, because these factors influence the nature of the hydrologic data needs. The hydrologic information needs of major importance are given together with specific measurable variables to be determined.

Development of the Korean Reference Vertical Disposal System Concept for Spent Fuels

International Nuclear Information System (INIS)

Lee, J.Y.; Cho, D.K.; Kim, S.G.; Choi, H.J.; Choi, J.W.; Hahn, P.S.

2006-01-01

The development of a deep geologic disposal system for the spent fuel from nuclear power plants has been carried out since this program was launched at 1997 in Korea. In ' this paper, a pre-conceptual design of the Korean Reference HLW Vertical disposal System (KRS-V1) is presented. Though no site for the underground repository has yet been specified in Korea, a generic site with granitic rock is considered for reference HLW repository design. Depth of the repository is assumed to be 500 meters. The repository consists of the disposal area, technical rooms with four shafts to connect them to the ground level in the controlled area and technical rooms with an access tunnel and three shafts to connect them to the ground level in the uncontrolled area. Disposal area consists of disposal tunnels, panel tunnels and a central tunnel. The repository will be excavated, operated and backfilled in several phases including an Underground Research Laboratory (URL) phase. The result of this preliminary conceptual design will be used for an evaluation of the feasibility, analyses of the long term safety, information for public communication and a cost estimation etc. (authors)

Infiltrated carbon foam composites

Science.gov (United States)

Lucas, Rick D. (Inventor); Danford, Harry E. (Inventor); Plucinski, Janusz W. (Inventor); Merriman, Douglas J. (Inventor); Blacker, Jesse M. (Inventor)

2012-01-01

An infiltrated carbon foam composite and method for making the composite is described. The infiltrated carbon foam composite may include a carbonized carbon aerogel in cells of a carbon foam body and a resin is infiltrated into the carbon foam body filling the cells of the carbon foam body and spaces around the carbonized carbon aerogel. The infiltrated carbon foam composites may be useful for mid-density ablative thermal protection systems.

Establishment of new disposal capacity for the Savannah River Plant

International Nuclear Information System (INIS)

Albenesius, E.L.; Wilhite, E.L.

1987-01-01

Two new low-level waste (LLW) disposal sites for decontaminated salt solidified with cement and fly ash (saltstone) and for conventional solid LLW are planned for SRP in the next several years. An above-ground vault disposal system for saltstone was designed to minimize impact on the environment by controlling permeability and diffusivity of the waste form and concrete liner. The experimental program leading to the engineered disposal system included formulation studies, multiple approaches to measurement of permeability and diffusivity, extensive mathematical modeling, and large-scale lysimeter tests to validate model projections. The overall study is an example of the systems approach to disposal site design to achieve a predetermined performance objective. The same systems approach is being used to develop alternative designs for disposal of conventional LLW at the Savannah River Plant. 14 figures

KS 20322007 Near-Surface Disposal Radioactive Waste - Code Of Practice

International Nuclear Information System (INIS)

Omondi, C.

2017-01-01

To provide a basis for the near-surface disposal of solid radioactive waste to ensures that there is no unacceptable risk to humans, other biota or the environment. Near-Surface Disposal is the disposal of radioactive waste in below or above the natural ground surface, within app. 30 m. The code deals with management aspects associated with radioactive waste disposal only, and is not intended to cover issues related to the production and use of radionuclides. The objective of waste disposal is to isolate radioactive waste in order to ensure that there is no unacceptable health risk to humans and no long-term unacceptable effect to the environment. Radiation protection annual effective dose for exposure of members of the public should not exceed 1 mSv/year and occupational exposure of 20 mSv/year

Movement of water infiltrated from a recharge basin to wells.

Science.gov (United States)

O'Leary, David R; Izbicki, John A; Moran, Jean E; Meeth, Tanya; Nakagawa, Brandon; Metzger, Loren; Bonds, Chris; Singleton, Michael J

2012-01-01

Local surface water and stormflow were infiltrated intermittently from a 40-ha basin between September 2003 and September 2007 to determine the feasibility of recharging alluvial aquifers pumped for public supply, near Stockton, California. Infiltration of water produced a pressure response that propagated through unconsolidated alluvial-fan deposits to 125 m below land surface (bls) in 5 d and through deeper, more consolidated alluvial deposits to 194 m bls in 25 d, resulting in increased water levels in nearby monitoring wells. The top of the saturated zone near the basin fluctuates seasonally from depths of about 15 to 20 m. Since the start of recharge, water infiltrated from the basin has reached depths as great as 165 m bls. On the basis of sulfur hexafluoride tracer test data, basin water moved downward through the saturated alluvial deposits until reaching more permeable zones about 110 m bls. Once reaching these permeable zones, water moved rapidly to nearby pumping wells at rates as high as 13 m/d. Flow to wells through highly permeable material was confirmed on the basis of flowmeter logging, and simulated numerically using a two-dimensional radial groundwater flow model. Arsenic concentrations increased slightly as a result of recharge from 2 to 6 µg/L immediately below the basin. Although few water-quality issues were identified during sample collection, high groundwater velocities and short travel times to nearby wells may have implications for groundwater management at this and at other sites in heterogeneous alluvial aquifers. Ground Water © 2011, National Ground Water Association. Published 2011. This article is a U.S. Government work and is in the public domain in the USA.

Work plan for monitor well/groundwater elevation data recorder installation at the Cheney Disposal site, Grand Junction, Colorado

International Nuclear Information System (INIS)

1994-09-01

In May 1990, during the excavation for the Grand Junction, Colorado, Cheney Reservoir disposal cell (Cheney), a water bearing paleochannel was encountered along the northern boundary of the excavation (designated the Northwest Paleochannel). To ensure the long-term integrity of the disposal embankment, remedial actions were taken including the excavation of the paleochannel and underlying material to bedrock, backfilling of the trapezoidal trench with granular material, and placement of a geotextile liner above the granular material. Compacted clay backfill was placed above the reconstructed paleochannel trench, and the northwest corner was restored to the designated grade. Investigation of other paleochannels determined that ground water flow terminated before it migrated as far west as the disposal cell. Therefore, flow in these paleochannels would have no impact on the disposal cell. Although characterization efforts did not indicate the presence of a ground water-bearing paleochannel south of the disposal cell, the potential could not be ruled out. As a best management practice for long-term monitoring at Cheney, two monitor wells will be installed within the paleochannels. One well will be installed within 50 feet (ft) west of the reconstructed Northwest Paleochannel. The second well will be installed near the southwestern (downgradient) corner of the disposal cell. The purposes of these wells are to characterize ground water flow (if any) within the paleochannels and to monitor the potential for water movement (seepage) into or out of the disposal cell. Initial monitoring of the paleochannels will consist of water level elevation measurement collection and trend analysis to evaluate fluctuations in storage. The purpose of this document is to describe the work that will be performed and the procedures that will be followed during installation of two ground water monitor wells and two ground water elevation data recorders (data loggers) at Cheney

Analysis of Arterial Mechanics During Head-Down-Tilt Bed Rest

Science.gov (United States)

Elliott, Morgan B.; Martin, David S.; Westby, Christian M.; Stenger, Michael B.; Platts, Steven H.

2014-01-01

Carotid, brachial, and tibial arteries reacted differently to HDTBR. Previous studies have not analyzed the mechanical properties of the human brachial or anterior tibial arteries. After slight variations during bed-rest, arterial mechanical properties and IMT returned to pre-bed rest values, with the exception of tibial stiffness and PSE, which continued to be reduced post-bed rest while the DC remained elevated. The tibial artery remodeling was probably due to decreased pressure and volume. Resulting implications for longer duration spaceflight are unclear. Arterial health may be affected by microgravity, as shown by increased thoracic aorta stiffness in other ground based simulations (Aubert).

The disposal of high level nuclear waste in the oceans

International Nuclear Information System (INIS)

Vilks, Gustavs

1976-01-01

A report is given on a meeting held at Woods Hole, Massachusetts to consider the feasibility of using the sea bed as a disposal site for highly radioactive nuclear waste. Some disadvantages are explained, the chief being that ocean water alone, regardless of depth, is a poor barrier. Some delegates discussed emplacement of vitrified waste on the ocean floor, and others its burial in rock or sediment below the floor. The most suitable sites are the mid-plate/mid-gyse localities of abyssal hills. Some engineering work on submarine burial has been done by Sandia Labs., in the U.S.A. Ocean disposal is particularly interesting to Britain and Japan. Data on biological transport rates are needed. (author)

Long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas. Revision 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-11-01

The need for ground water monitoring at the Falls City disposal site was evaluated in accordance with NRC regulations and guidelines established by the DOE in Guidance for Implementing the Long-term Surveillance Program for UMTRA Project Title 1 Disposal Sites (DOE, 1996). Based on evaluation of site characterization data, it has been determined that a program to monitor ground water for demonstration of disposal cell performance based on a set of concentration limits is not appropriate because ground water in the uppermost aquifer is of limited use, and a narrative supplemental standard has been applied to the site that does not include numerical concentration limits or a point of compliance. The limited use designation is based on the fact that ground water in the uppermost aquifer is not currently or potentially a source of drinking water in the area because it contains widespread ambient contamination that cannot be cleaned up using methods reasonably employed by public water supply systems. Background ground water quality varies by orders of magnitude since the aquifer is in an area of redistribution of uranium mineralization derived from ore bodies. The DOE plans to perform post-closure ground water monitoring in the uppermost aquifer as a best management practice (BMP) as requested by the state of Texas.

Long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas. Revision 2

International Nuclear Information System (INIS)

1996-11-01

The need for ground water monitoring at the Falls City disposal site was evaluated in accordance with NRC regulations and guidelines established by the DOE in Guidance for Implementing the Long-term Surveillance Program for UMTRA Project Title 1 Disposal Sites (DOE, 1996). Based on evaluation of site characterization data, it has been determined that a program to monitor ground water for demonstration of disposal cell performance based on a set of concentration limits is not appropriate because ground water in the uppermost aquifer is of limited use, and a narrative supplemental standard has been applied to the site that does not include numerical concentration limits or a point of compliance. The limited use designation is based on the fact that ground water in the uppermost aquifer is not currently or potentially a source of drinking water in the area because it contains widespread ambient contamination that cannot be cleaned up using methods reasonably employed by public water supply systems. Background ground water quality varies by orders of magnitude since the aquifer is in an area of redistribution of uranium mineralization derived from ore bodies. The DOE plans to perform post-closure ground water monitoring in the uppermost aquifer as a best management practice (BMP) as requested by the state of Texas

Effects of land disposal of municipal sewage sludge on fate of nitrates in soil, streambed sediment, and water quality

Science.gov (United States)

Tindall, James A.; Lull, Kenneth J.; Gaggiani, Neville G.

1994-01-01

This study was undertaken to determine the effects of sewage-sludge disposal at the Lowry sewage-sludge-disposal area, near Denver, Colorado, on ground- and surface-water quality, to determine the fate of nitrates from sludge leachate, and to determine the source areas of leachate and the potential for additional leaching from the disposal area.Sewage-sludge disposal began in 1969. Two methods were used to apply the sludge: burial and plowing. Also, the sludge was applied both in liquid and cake forms. Data in this report represent the chemical composition of soil and streambed sediment from seven soil- and four streambed-sampling sites in 1986, chemical and bacterial composition of ground water from 28 wells from 1981 to 1987, and surface-water runoff from seven water-sampling sites from 1984 to 1987. Ground water samples were obtained from alluvial and bedrock aquifers. Samples of soil, streambed sediment, ground water and surface water were obtained for onsite measurement and chemical analysis. Measurements included determination of nitrogen compounds and major cations and anions, fecal-coliform and -streptococcus bacteria, specific conductance, and pH.Thirteen wells in the alluvial aquifer in Region 3 of the study area contain water that was probably affected by sewage-sludge leachate. The plots of concentration of nitrate with time show seasonal trends and trends caused by precipitation. In addition to yearly fluctuation, there were noticeable increases in ground-water concentrations of nitrate that coincided with increased precipitation. After 3 years of annual ground-water-quality monitoring and 4 years of a quarterly sampling program, it has been determined that leachate from the sewage-sludge-disposal area caused increased nitrite plus nitrate (as nitrogen) concentration in the alluvial ground water at the site. Soil analyses from the disposal area indicate that organic nitrogen was the dominant form of nitrogen in the soil.As a result of investigations at

The role of post-ore processes in the alteration of infiltrational uranium deposits

International Nuclear Information System (INIS)

Kondrat'eva, I.A.; Bobrova, L.L.; Nesterova, M.V.

1992-01-01

Ore-bearing rocks and ores of uranium deposits that are associated with gray alluvial deposits and formed through oxidation of sedimentary beds at the end of the Jurassic, have undergone intensive alterations. The impact of hot carbonic acid solutions on infiltrational uranium deposits, along with calcite and hematite, resulted in partial dissolution of and redeposition of uranium. Uranium concentrates with newly formed Fe-bisulfides and hydroxides in the reducing stage of epigenetic alterations within a hydrochemical sulfide-gley medium, leading to changes in ore morphology. 20 refs., 7 figs., 3 tabs

Incineration: why this may be the most environmentally sound method of renal healthcare waste disposal.

Science.gov (United States)

James, Ray

2010-09-01

The environment and 'green' issues are currently being promoted in the healthcare sector through recently launched initiatives. This paper considers aspects of healthcare waste management, with particular reference to waste generated in dialysis units. With dialysis being dependent upon large amounts of disposables, it generates considerable volumes of waste. This paper focuses upon a typical haemodialysis unit, evaluating and quantifying the volumes and categories of waste generated. Each haemodialysis patient on thrice weekly dialysis generates some 323 kg per year of waste, of which 271 kg is classified as clinical. This equates to 1626 kg of (solid) clinical waste per dialysis bed, which is around three times the volume of clinical waste generated per general hospital bed. Waste disposal routes are considered and this suggests that present healthcare waste paradigms are outmoded. They do not allow for flexible approaches to solving what is a dynamic problem, and there is a need for new thinking models in terms of managing the unsustainable situation of disposal in constantly growing landfills. Healthcare waste management must be considered not only in terms of the environmental impact and potential long-term health effects, but also in terms of society's future energy requirements.

System cuts radwaste-disposal cost

International Nuclear Information System (INIS)

May, J.R.

1978-01-01

Pilot-plant and full-scale prototype-system test data on a new volume-reduction system for low-level radioactive wastes, of the type generated by nuclear plants, indicate that total present costs for radwaste disposal can be reduced by more than 50%. In 1975, Newport News Industrial Corp. and Energy Inc. decided to develop cooperatively a fluidized-bed process that would combine the features of a calciner and an incinerator. The new radwaste-volume-reduction system, designated RWR-1, can reduce the volume of concentrated liquids, ion-exchange resin beads, filter sludges, and various combustible solids, such as protective clothing, rags, paper, wood, and plastics

Integrated drying and incineration of wet sewage sludge in combined bubbling and circulating fluidized bed units.

Science.gov (United States)

Li, Shiyuan; Li, Yunyu; Lu, Qinggang; Zhu, Jianguo; Yao, Yao; Bao, Shaolin

2014-12-01

An original integrated drying and incineration technique is proposed to dispose of sewage sludge with moisture content of about 80% in a circulating fluidized bed. This system combines a bubbling fluidized bed dryer with a circulating fluidized bed incinerator. After drying, sewage sludge with moisture less than 20% is transported directly and continuously from the fluidized bed dryer into a circulating fluidized bed incinerator. Pilot plant results showed that integrated drying and incineration is feasible in a unique single system. A 100 t/d Sewage Sludge Incineration Demonstration Project was constructed at the Qige sewage treatment plant in Hangzhou City in China. The operational performance showed that the main operation results conformed to the design values, from which it can be concluded that the scale-up of this technique is deemed both feasible and successful. Copyright © 2014 Elsevier Ltd. All rights reserved.

Performance Evaluation of the ISS Water Processor Multifiltration Beds

Science.gov (United States)

Bowman, Elizabeth M.; Carter, Layne; Wilson, Mark; Cole, Harold; Orozco, Nicole; Snowdon, Doug

2012-01-01

The ISS Water Processor Assembly (WPA) produces potable water from a waste stream containing humidity condensate and urine distillate. The primary treatment process is achieved in the Multifiltration Bed, which includes adsorbent media and ion exchange resin for the removal of dissolved organic and inorganic contaminants. The first Multifiltration Bed was replaced on ISS in July 2010 after initial indication of inorganic breakthrough. This bed was returned to ground in July 2011 for an engineering investigation. The water resident in the bed was analyzed for various parameters to evaluate adsorbent loading, performance of the ion exchange resin, microbial activity, and generation of leachates from the ion exchange resin. Portions of the adsorbent media and ion exchange resin were sampled and subsequently desorbed to identify the primary contaminants removed at various points in the bed. In addition, an unused Multifiltration Bed was evaluated after two years in storage to assess the generation of leachates during storage. This assessment was performed to evaluate the possibility that these leachates are impacting performance of the Catalytic Reactor located downstream of the Multifiltration Bed. The results of these investigations and implications to the operation of the WPA on ISS are documented in this paper.

Preliminary environmental assessments of disposal of rock mined during excavation of a federal repository for radioactive waste

International Nuclear Information System (INIS)

1977-09-01

Since the environmental impact of mined rock handling will be dependent not only upon the nature of the material and the way in which it might be disposed but also upon the features of the disposal site area and surroundings, it was necessary to select ''reference environmental locii'' within the regions of geological interest to typify the environmental setting into which the rock would be placed. Reference locii (locations) were developed for consideration of the environmental implications of mined rock from: bedded rock salt from the Salina region, bedded rock salt from the Permian region, dome rock salt from the Gulf Interior region, Pierre shale from the Argillaceous region, granite from the crystalline rock region, volcanic basalt rock from the crystalline ash region, and carbonate rock from the limestone region. Each of these reference locii was examined with respect to those demographic, geographic, physical and ecological attributes which might be impacted by various mined rock disposal alternatives. Alternatives considered included: onsite surface storage, industrial or commercial use, offsite disposal, and environmental blending. Potential impact assessment consists of a qualitative look at the environmental implications of various alternatives for handling the mined rock, given baseline characteristics of an area typified by those represented by the ''reference locus''

The soil apparent infiltrability observed with ponded infiltration experiment in a permanent grid of infiltration rings

Czech Academy of Sciences Publication Activity Database

Votrubová, J.; Jelínková, V.; Němcová, R.; Tesař, Miroslav; Vogel, T.; Císlerová, M.

2010-01-01

Roč. 12, - (2010), s. 11898 ISSN 1607-7962. [European Geosciences Union General Assembly 2010. 02.05.2010-07.05.2010, Wienna] R&D Projects: GA ČR GA205/08/1174 Institutional research plan: CEZ:AV0Z20600510 Keywords : soil hydraulic conductivity * infiltration * infiltration ring Subject RIV: DA - Hydrology ; Limnology

Saturated and unsaturated stability analysis of slope subjected to rainfall infiltration

Directory of Open Access Journals (Sweden)

Gofar Nurly

2017-01-01

Full Text Available This paper presents results of saturated and unsaturated stability analysis of typical residual slopes subjected to rainfall infiltration corresponds to 50 years rainfall return period. The slope angles considered were 45° and 70°. The saturated stability analyses were carried out for original and critical ground water level commonly considered by practicing engineer. The analyses were conducted using limit equilibrium method. Unsaturated stability analyses used combination of coupled stress–pore-water pressure analysis to evaluate the effect of rainfall infiltration on the deformation and transient pore-water pressure on slope stability. Slope stability analyses were performed at some times during and after rainfall infiltration. Results show that the critical condition for slope made by sandy material was at the end of rainfall while for clayey material was at some specified times after the rainfall ceased. Unsaturated stability analysis on sandy soil gives higher factor of safety because the soil never reached saturation. Transient analysis using unsaturated soil concept could predict more critical condition of delayed failure of slopes made up of clayey soil.

Periarticular infiltration for pain relief after total hip arthroplasty: a comparison with epidural and PCA analgesia.

Science.gov (United States)

Pandazi, Ageliki; Kanellopoulos, Ilias; Kalimeris, Konstantinos; Batistaki, Chrysanthi; Nikolakopoulos, Nikolaos; Matsota, Paraskevi; Babis, George C; Kostopanagiotou, Georgia

2013-11-01

Epidural and intravenous patient-controlled analgesia (PCA) are established methods for pain relief after total hip arthroplasty (THA). Periarticular infiltration is an alternative method that is gaining ground due to its simplicity and safety. Our study aims to assess the efficacy of periarticular infiltration in pain relief after THA. Sixty-three patients undergoing THA under spinal anaesthesia were randomly assigned to receive postoperative analgesia with continuous epidural infusion with ropivacaine (epidural group), intraoperative periarticular infiltration with ropivacaine, clonidine, morphine, epinephrine and corticosteroids (infiltration group) or PCA with morphine (PCA group). PCA morphine provided rescue analgesia in all groups. We recorded morphine consumption, visual analog scale (VAS) scores at rest and movement, blood loss from wound drainage, mean arterial pressure (MAP) and adverse effects at 1, 6, 12, 24 h postoperatively. Morphine consumption at all time points, VAS scores at rest, 6, 12 and 24 h and at movement, 6 and 12 h postoperatively were lower in infiltration group compared to PCA group (p PCA group (p PCA with morphine after THA, providing better pain relief and lower opioid consumption postoperatively. Infiltration seems to be equally effective to epidural analgesia without having the potential side effects of the latter.

Geologic disposal of nuclear wastes: salt's lead is challenged

International Nuclear Information System (INIS)

Kerr, R.A.

1979-01-01

The types of radioactive waste disposal sites available are outlined. The use of salt deposits and their advantages are discussed. The reasons for the selection of the present site for the Waste Isolation Pilot Plant are presented. The possibilities of using salt domes along the Gulf Coast and not-salt rocks as nuclear waste repositories are also discussed. The sea bed characteristics are described and advantages of this type of site selection are presented

Pathways for Disposal of Commercially-Generated Tritiated Waste

Energy Technology Data Exchange (ETDEWEB)

Halverson, Nancy V. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Environmental Sciences and Biotechnology

2016-09-26

From a waste disposal standpoint, tritium is a major challenge. Because it behaves like hydrogen, tritium exchanges readily with hydrogen in the ground water and moves easily through the ground. Land disposal sites must control the tritium activity and mobility of incoming wastes to protect human health and the environment. Consequently, disposal of tritiated low-level wastes is highly regulated and disposal options are limited. The United States has had eight operating commercial facilities licensed for low-level radioactive waste disposal, only four of which are currently receiving waste. Each of these is licensed and regulated by its state. Only two of these sites accept waste from states outside of their specified regional compact. For waste streams that cannot be disposed directly at one of the four active commercial low-level waste disposal facilities, processing facilities offer various forms of tritiated low-level waste processing and treatment, and then transport and dispose of the residuals at a disposal facility. These processing facilities may remove and recycle tritium, reduce waste volume, solidify liquid waste, remove hazardous constituents, or perform a number of additional treatments. Waste brokers also offer many low-level and mixed waste management and transportation services. These services can be especially helpful for small-quantity tritiated-waste generators, such as universities, research institutions, medical facilities, and some industries. The information contained in this report covers general capabilities and requirements for the various disposal/processing facilities and brokerage companies, but is not considered exhaustive. Typically, each facility has extensive waste acceptance criteria and will require a generator to thoroughly characterize their wastes. Then a contractual agreement between the waste generator and the disposal/processing/broker entity must be in place before waste is accepted. Costs for tritiated waste

Pathways for Disposal of Commercially-Generated Tritiated Waste

International Nuclear Information System (INIS)

Halverson, Nancy V.

2016-01-01

From a waste disposal standpoint, tritium is a major challenge. Because it behaves like hydrogen, tritium exchanges readily with hydrogen in the ground water and moves easily through the ground. Land disposal sites must control the tritium activity and mobility of incoming wastes to protect human health and the environment. Consequently, disposal of tritiated low-level wastes is highly regulated and disposal options are limited. The United States has had eight operating commercial facilities licensed for low-level radioactive waste disposal, only four of which are currently receiving waste. Each of these is licensed and regulated by its state. Only two of these sites accept waste from states outside of their specified regional compact. For waste streams that cannot be disposed directly at one of the four active commercial low-level waste disposal facilities, processing facilities offer various forms of tritiated low-level waste processing and treatment, and then transport and dispose of the residuals at a disposal facility. These processing facilities may remove and recycle tritium, reduce waste volume, solidify liquid waste, remove hazardous constituents, or perform a number of additional treatments. Waste brokers also offer many low-level and mixed waste management and transportation services. These services can be especially helpful for small-quantity tritiated-waste generators, such as universities, research institutions, medical facilities, and some industries. The information contained in this report covers general capabilities and requirements for the various disposal/processing facilities and brokerage companies, but is not considered exhaustive. Typically, each facility has extensive waste acceptance criteria and will require a generator to thoroughly characterize their wastes. Then a contractual agreement between the waste generator and the disposal/processing/broker entity must be in place before waste is accepted. Costs for tritiated waste

Comparison of risks due to HLW and SURF repositories in bedded salt

International Nuclear Information System (INIS)

Chu, M.S.Y.; Ortiz, N.R.; Wahi, K.K.

1983-01-01

A methodology was developed for use in the analysis of risks from geologic disposal of nuclear wastes. This methodology is applied to two conceptual nuclear waste repositories in bedded salt containing High-Level Waste (HLW) and Spent Un-Reprocessed Fuel (SURF), respectively. A comparison of the risk estimated from the HLW and SURF repositories is presented

Wastewater planning in Djenné, Mali. A pilot project for the local infiltration of domestic wastewater.

Science.gov (United States)

Alderlieste, M C; Langeveld, J G

2005-01-01

The city of Djenné (Mali) is famous for its mosque which is the world's largest adobe building. Djenné is considered to be one of the most interesting cities in Western Africa from an architectural point of view. Since 1988, Djenné is listed as a UNESCO World Heritage Site. In the 1990s, a drinking water supply network was provided by foreign development organisations. However, no facilities were provided for the disposal of wastewater, resulting in an increase of waterborne diseases. This paper describes the urban drainage problem in Djenné and discusses the systematic evaluation of possible solutions and the subsequent pilot project for the local infiltration of sullage. The infiltration of sullage proved to be an appropriate technology for solving the urban drainage problem in Djenné.

Repository site data and information in bedded salt: Palo Duro Basin, Texas

International Nuclear Information System (INIS)

Tien, P.; Nimick, F.B.; Muller, A.B.; Davis, P.A.; Guzowski, R.V.; Duda, L.E.; Hunter, R.L.

1983-11-01

This report is a compilation of data from the literature on the Palo Duro Basin. The Palo Duro Basin is a structural basin, about 150 miles long and 80 miles wide, that is a part of the much larger Permian Basin. The US Department of Energy is investigating the Palo Duro Basin as a potentially suitable area for the site of a repository for the disposal of high-level radioactive waste. Sediments overlying the Precambrian basement range from about 5000 to about 11,000 ft in thickness and from Cambrian to Holocene in age. The strata in the Palo Duro Basin that are of primary interest to the Department of Energy are the bedded salts of the Permian San Andres Formation. The total thickness of the bedded salts is about 2000 ft. The geology of the Palo Duro Basin is well understood. A great deal of information exists on the properties of salt, although much of the available information was not collected in the Palo Duro Basin. Mineral resources are not currently being exploited from the center of the Palo Duro Basin at depth, although the possibility of exploration for and development of such resources can not be ruled out. The continued existence of salts of Permian age indicates a lack of any large amount of circulating ground water. The hydrology of the pre-Tertiary rocks, however, is currently too poorly understood to carry out detailed, site-specific hydrologic modeling with a high degree of confidence. In general, ground water flows from west to east in the Basin. There is little or no hydraulic connection between aquifers above and below the salt sequences. Potable water is pumped from the Ogallala aquifer. Most of the other aquifers yield only nonpotable water. More extensive hydrological data are needed for detailed future modeling in support of risk assessment for a possible repository for high-level waste in the Palo Duro Basin. 464 references

Treatment and disposal of petroleum contaminated soil (June 1996) : revised May 1998

International Nuclear Information System (INIS)

1998-05-01

Leaking petroleum storage tanks and petroleum contaminated sites can pose significant environmental and public safety hazards. Proper mitigation is required to remove this threat. These guidelines are intended to assist environmental consultants, petroleum service contractors, waste disposal ground operators and petroleum storage tank owners in the management of petroleum contaminated soil (PCS). The procedures that should be used for disposal and treatment of PCS at licensed soil treatment facilities, municipal waste disposal grounds, and at single-use soil treatment sites approved by Manitoba Environment are described. The treatment should control excessive emission of volatile organic compounds to the atmosphere. Losses of petroleum compounds by leaching should also be controlled. The main treatment method at government-approved sites is land farming. Other remedial options include enhanced bioremediation, asphalt incorporation, soil washing, and thermal treatment. Permitting and licensing procedures, guidelines for the design and operations at PCS treatment and disposal sites, procedures for the removal and re-use of treated soil and procedures for the decommissioning of PCS treatment sites are also outlined. A list of other associated regulations and guidelines is included. 2 tabs

1974 conceptual design description of a bedded salt pilot plant in southeast New Mexico

International Nuclear Information System (INIS)

1977-06-01

The policy of the United States Atomic Energy Commission is to take custody of all commercial high-level radioactive wastes and maintain control of them in perpetuity. This policy (Title 10, Code of Federal Regulations, Part 50, Appendix F) requires that the high-level wastes from nuclear fuels reprocessing plants be solidified within five years after reprocessing and then shipped to a federal repository within ten years after reprocessing. Ultimate disposal sites and/or methods have not yet been selected and are not expected to be ready when waste deliveries begin about 1983. Therefore, the AEC plans to build an interim storage facility, called Retrievable Surface Storage Facility (RSSF), to store and isolate the waste from man and his environment until the suitability of the permanent repository is demonstrated and public acceptance has been established. Meantime, the AEC is proceeding with the study and development of an ultimate disposal method. Bedded salt is being considered for ultimate waste disposal, and work is in progress to develop a Bedded Salt Pilot Plant to demonstrate its acceptability. The pilot plant will permit in situ verification of laboratory work on the interaction of heat and radioactivity of the waste with the salt and surroundings. One concept of such a pilot facility is described

Long-term reactive transport modelling of stabilized/solidified waste: from dynamic leaching tests to disposal scenarios

Energy Technology Data Exchange (ETDEWEB)

Windt, Laurent de [Ecole des Mines de Paris, CG-Hydrodynamics and Reaction Group, 35 R. St-Honore, 77300 Fontainebleau (France)]. E-mail: laurent.dewindt@ensmp.fr; Badreddine, Rabia [INERIS, Direction des Risques Chroniques, Unite Dechets et Sites Pollues, Parc Technologique Alata BP 2, 60550 Verneuil-en-Halatte (France); Lagneau, Vincent [Ecole des Mines de Paris, CG-Hydrodynamics and Reaction Group, 35 R. St-Honore, 77300 Fontainebleau (France)

2007-01-31

Environmental impact assessment of hazardous waste disposal relies, among others, on standardized leaching tests characterized by a strong coupling between diffusion and chemical processes. In that respect, this study shows that reactive transport modelling is a useful tool to extrapolate laboratory results to site conditions characterized by lower solution/solid (L/S) ratios, site specific geometry, infiltration, etc. A cement solidified/stabilized (S/S) waste containing lead is investigated as a typical example. The reactive transport model developed in a previous study to simulate the initial state of the waste as well as laboratory batch and dynamic tests is first summarized. Using the same numerical code (HYTEC), this model is then integrated to a simplified waste disposal scenario assuming a defective cover and rain water infiltration. The coupled evolution of the S/S waste chemistry and the pollutant plume migration are modelled assessing the importance of the cracking state of the monolithic waste. The studied configurations correspond to an undamaged and fully sealed system, a few main fractures between undamaged monoliths and, finally, a dense crack-network in the monoliths. The model considers the potential effects of cracking, first the increase of rain water and carbon dioxide infiltration and, secondly, the increase of L/S ratio and reactive surfaces, using either explicit fracture representation or dual porosity approaches.

Effect strooiselmateriaal, strooiselhoeveelheid, opvangschoteltjes en waterdruk op resultaten vleeskuikens = Influence of bedding material, bedding amount, drip cup and reduced water pressure on broiler performance

NARCIS (Netherlands)

Harn, van J.; Jong, de I.C.; Veldkamp, T.

2009-01-01

Four different bedding materials for broiler houses were compared: white wood shavings, chopped wheat straw, ground rapeseed straw and silage maize. Performance results, carcass yields, litter quality, broiler quality and gait score were measured.

Nuclear waste disposal site

International Nuclear Information System (INIS)

Mallory, C.W.; Watts, R.E.; Sanner, W.S. Jr.; Paladino, J.B.; Lilley, A.W.; Winston, S.J.; Stricklin, B.C.; Razor, J.E.

1988-01-01

This patent describes a disposal site for the disposal of toxic or radioactive waste, comprising: (a) a trench in the earth having a substantially flat bottom lined with a layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for obstructing any capillary-type flow of ground water to the interior of the trench; (b) a non-rigid, radiation-blocking cap formed from a first layer of alluvium, a second layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for blocking any capillary-type flow of water between the layer of alluvium and the rest of the cap, a layer of water-shedding silt for directing surface water away from the trench, and a layer of rip-rap over the silt layer for protecting the silt layer from erosion and for providing a radiation barrier; (c) a solidly-packed array of abutting modules of uniform size and shape disposed in the trench and under the cap for both encapsulating the wastes from water and for structurally supporting the cap, wherein each module in the array is slidable movable in the vertical direction in order to allow the array of modules to flexibly conform to variations in the shape of the flat trench bottom caused by seismic disturbances and to facilitate the recoverability of the modules; (d) a layer of solid, fluent, coarse, granular materials having a high hydraulic conductivity in the space between the side of the modules and the walls of the trench for obstructing any capillary-type flow of ground water to the interior of the trench; and (e) a drain and wherein the layer of silt is sloped to direct surface water flowing over the cap into the drain

Unconfined aquifer response to infiltration basins and shallow pump tests

Science.gov (United States)

Ostendorf, David W.; DeGroot, Don J.; Hinlein, Erich S.

2007-05-01

SummaryWe measure and model the unsteady, axisymmetric response of an unconfined aquifer to delayed, arbitrary recharge. Water table drainage follows the initial elastic aquifer response, as modeled for uniform, instantaneous recharge by Zlotnik and Ledder [Zlotnik, V., Ledder, G., 1992. Groundwater flow in a compressible unconfined aquifer with uniform circular recharge. Water Resources Research 28(6), 1619-1630] and delayed drainage by Moench [Moench, A.F., 1995. Combining the Neuman and Boulton models for flow to a well in an unconfined aquifer. Ground Water 33(3), 378-384]. We extend their analyses with a convolution integral that models the delayed response of an aquifer to infiltration from a circular infiltration basin. The basin routes the hydrograph to the water table with a decay constant dependent on a Brooks and Corey [Brooks, R.H., Corey, A.T., 1966. Properties of porous media affecting fluid flow. Journal of the Irrigation and Drainage Division ASCE 92(2), 61-88] unsaturated permeability exponent. The resulting closed form model approaches Neuman's [Neuman, S.P., 1972. Theory of flow in unconfined aquifers considering delayed response of the water table. Water Resources Research 8(4), 1031-1045] partially penetrating pump test equation for a small source radius, instantaneous, uniform drainage and a shallow screen section. Irrigation pump data at a well characterized part of the Plymouth-Carver Aquifer in southeastern Massachusetts calibrate the small source model, while infiltration data from the closed drainage system of State Route 25 calibrate the infiltration basin model. The calibrated permeability, elasticity, specific yield, and permeability exponent are plausible and consistent for the pump and infiltration data sets.

1994 Characterization report for the state approved land disposal site

International Nuclear Information System (INIS)

Swanson, L.C.

1994-01-01

This report summarizes the results of characterization activities at the proposed state-approved land disposal site (SALDS); it updates the original characterization report with studies completed since the first characterization report. The initial characterization report discusses studies from two characterization boreholes, 699-48-77A and 699-48-77B. This revision includes data from implementation of the Groundwater Monitoring Plan and the Aquifer Test Plan. The primary sources of data are two down-gradient groundwater monitoring wells, 699-48-77C and 699-48-77D, and aquifer testing of three zones in well 699-48-77C. The SALDS is located on the Hanford Site, approximately 183 m north of the 200 West Area on the north side of the 200 Areas Plateau. The SALDS is an infiltration basin proposed for disposal of treated effluents from the 200 Areas of Hanford

Alternate Methods of Effluent Disposal for On-Lot Home Sewage Systems. Special Circular 214.

Science.gov (United States)

Wooding, N. Henry

This circular provides current information for homeowners who must repair or replace existing on-lot sewage disposal systems. Several alternatives such as elevated sand mounds, sand-lined beds and trenches and oversized absorption areas are discussed. Site characteristics and preparation are outlined. Each alternative is accompanied by a diagram…

Percolation testing at the F- and H-Area Seepage Basins

International Nuclear Information System (INIS)

McHood, M.D.

1993-01-01

The design of the F- and H-Area Seepage Basin contaminated groundwater remediation system requires information from multiple well pump tests (Reference 1). Soil percolation rates are needed in order to support the multiple well pump test planning. The objective of this task was to determine characteristic percolation rates for soils in four select areas where infiltration galleries are proposed. These infiltration galleries will be temporary installations built on the ground surface and used to disposes of water from the multiple well pump tests. A procedure defining the specific work process for collecting percolation rate data is contained in Appendix 3. Results from these percolation tests will be used in the design of infiltration galleries for the disposal of well water extracted during the multiple well pump tests

Shallow ground burial of low-level waste

International Nuclear Information System (INIS)

Camilleri, A.; Cooper, M.B.; Hargrave, N.J.; Munslow-Davies, L.

1989-01-01

Acceptance criteria for the disposal of low-level radioactive wastes are presented for adoption throughout Australia, a continent in which there are readily available areas in arid, sparsely inhabited places, likely to be suitable as sites for shallow ground burial. Drawing upon overseas practices and experiences, criteria have been developed for low-level waste disposal and are intended to be applicable and relevant to the Australian situation. Concentration levels have been derived for a shallow ground burial facility assuming a realistic institutional control period of 200 years. A comparison is made between this period and institutional control for 100 years and 300 years. Longer institutional control periods enable the acceptance of higher concentrations of radionuclides of intermediate half-lives. Scenarios, which have been considered, include current Australian pastoral practices and traditional Aboriginal occupancy. The derived radionuclide concentration levels for the disposal of low level wastes are not dissimilar to those developed in other countries. 17 refs., 6 tabs., 1 fig

Sensitivity of MRI in detecting alveolar infiltrates. Experimental studies; Sensitivitaet der MRT fuer alveolaere Infiltrate. Experimentelle Untersuchungen

Energy Technology Data Exchange (ETDEWEB)

Biederer, J.; Busse, I.; Grimm, J.; Reuter, M.; Heller, M. [Kiel Univ. (Germany). Klinikum fuer Diagnostische Radiologie; Muhle, C. [Kiel Univ. (Germany). Klinik fuer Nuklearmedizin; Freitag, S. [Kiel Univ. (Germany). Inst. fuer Medizinische Informatik und Statistik

2002-08-01

Purpose: An experimental study using porcine lung explants and a dedicated chest phantom to evaluate the signal intensity of artificial alveolar infiltrates with T{sub 1}- and T{sub 2}-weighted MRI sequences. Material and Methods: 10 porcine lung explants were intubated, transferred into the cavity of a MRI-compatible chest phantom and inflated by continuous evacuation of the artificial pleural space. All lungs were examined with MRI at 1.5 T before and after intra-tracheal instillation of either 100 or 200 ml gelatine-stabilised liquid to simulate alveolar infiltrates. MR-examination comprised gradient echo (2D- and 3D-GRE) and fast spin echo sequences (T{sub 2}-TSE and T{sub 2}-HASTE). The signal intensity of lung parenchyma was evaluated at representative cross sections using a standardised scheme. Control studies were acquired with helical CT. Results: The instilled liquid caused patchy confluent alveolar infiltrates resembling the findings in patients with pneumonia or ARDS. CT revealed typical ground-glass opacities. Before the application of the liquid, only T{sub 2}-HASTE and T{sub 2}-TSE displayed lung parenchyma signals with a signal/noise ratio of 3.62 and 1.39, respectively. After application of the liquid, both T{sub 2}-weighted sequences showed clearly visible infiltrates with an increase in signal intensity of approx. 30% at 100 ml (p<0.01) and 60% at 200 ml (p<0.01). With 2D- and 3D-GRE the infiltrates were not visible, although the lung parenchyma signal increase was statistically significant. On 2D-GRE the increase in signal intensity reached 0.74% (p=0.32) after 100 ml and 5.6% (p<0.01) after 200 ml for 3D-GRE: 2.2% [p=0.02] at 100 ml and 4.4% at 200 ml [p<0.001]. The CT controls revealed a significant increase of lung density of 17. H.E. at 100 ml (p=0.02) and 75 H.E. at 200 ml (p<0.01). Conclusions: MRI with T{sub 2}-weighted sequences detects artificial alveolar infiltrates with high signal intensity and may be a highly sensitive tool to

Concept of ground facilities and the analyses of the factors for cost estimation

Energy Technology Data Exchange (ETDEWEB)

Lee, J. Y.; Choi, H. J.; Choi, J. W.; Kim, S. K.; Cho, D. K

2007-09-15

The geologic disposal of spent fuels generated from the nuclear power plants is the only way to protect the human beings and the surrounding environments present and future. The direct disposal of the spent fuels from the nuclear power plants is considered, and a Korean Reference HLW disposal System(KRS) suitable for our representative geological conditions have been developed. In this study, the concept of the spent fuel encapsulation process as a key of the above ground facilities for deep geological disposal was established. To do this, the design requirements, such as the functions and the spent fuel accumulations, were reviewed. Also, the design principles and the bases were established. Based on the requirements and the bases, the encapsulation process of the spent fuel from receiving spent fuel of nuclear power plants to transferring canister into the underground repository was established. Simulation for the above-ground facility in graphic circumstances through KRS design concept and disposal scenarios for spent nuclear fuel showed that an appropriate process was performed based on facility design concept and required for more improvement on construction facility by actual demonstration test. And, based on the concept of the above ground facilities for the Korean Reference HLW disposal System, the analyses of the factors for the cost estimation was carried out.

Fate of individual sewage disposal system wastewater within regolith in mountainous terrain

Science.gov (United States)

Dano, Kathleen; Poeter, Eileen; Thyne, Geoff

2008-06-01

In order to improve understanding of the fate of septic tank or individual sewage disposal system (ISDS) effluent in regolith overlying fractured-rock aquifers, effluent from an ISDS in such a setting was tracked via geophysical, hydrological, and geochemical methods. Under typical precipitation conditions, the effluent entered the fractured bedrock within 5 m of the boundary of the constructed infiltration area. During a period of unusually high spring recharge, the plume migrated between 50 and 100 m within the regolith before infiltrating the fractured bedrock. The chemical signature of the effluent is similar to that required to account for the decline in water quality, suggesting a causative relationship (as estimated from mass-balance models of the surface-water chemistry near the mouth of the basin). The elevated salt content of the effluent during periods of high natural recharge to the infiltration area correlates with elevated salt concentrations in surface and groundwater at the basin scale, suggesting that some of the effluent salt load may be stored in the unsaturated zone during dry periods and flushed during periods of elevated natural recharge.

Facial infiltrative lipomatosis

International Nuclear Information System (INIS)

Haloi, A.K.; Ditchfield, M.; Pennington, A.; Philips, R.

2006-01-01

Although there are multiple case reports and small series concerning facial infiltrative lipomatosis, there is no composite radiological description of the condition. Radiological evaluation of facial infiltrative lipomatosis using plain film, sonography, CT and MRI. We radiologically evaluated four patients with facial infiltrative lipomatosis. Initial plain radiographs of the face were acquired in all patients. Three children had an initial sonographic examination to evaluate the condition, followed by MRI. One child had a CT and then MRI. One child had abnormalities on plain radiographs. Sonographically, the lesions were seen as ill-defined heterogeneously hypoechoic areas with indistinct margins. On CT images, the lesions did not have a homogeneous fat density but showed some relatively more dense areas in deeper parts of the lesions. MRI provided better delineation of the exact extent of the process and characterization of facial infiltrative lipomatosis. Facial infiltrative lipomatosis should be considered as a differential diagnosis of vascular or lymphatic malformation when a child presents with unilateral facial swelling. MRI is the most useful single imaging modality to evaluate the condition, as it provides the best delineation of the exact extent of the process. (orig.)

Protective barrier systems for final disposal of Hanford Waste Sites

International Nuclear Information System (INIS)

Phillips, S.J.; Hartley, J.N.

1986-01-01

A protecting barrier system is being developed for potential application in the final disposal of defense wastes at the Hanford Site. The functional requirements for the protective barrier are control of water infiltration, wind erosion, and plant and animal intrusion into the waste zone. The barrier must also be able to function without maintenance for the required time period (up to 10,000 yr). This paper summarizes the progress made and future plans in this effort to design and test protective barriers at the Hanford Site

Thermal Analysis of Disposal of High-Level Nuclear Waste in a Generic Bedded Salt repository using the Semi-Analytical Method.

Energy Technology Data Exchange (ETDEWEB)

Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Matteo, Edward N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-05-01

An example case is presented for testing analytical thermal models. The example case represents thermal analysis of a generic repository in bedded salt at 500 m depth. The analysis is part of the study reported in Matteo et al. (2016). Ambient average ground surface temperature of 15°C, and a natural geothermal gradient of 25°C/km, were assumed to calculate temperature at the near field. For generic salt repository concept crushed salt backfill is assumed. For the semi-analytical analysis crushed salt thermal conductivity of 0.57 W/m-K was used. With time the crushed salt is expected to consolidate into intact salt. In this study a backfill thermal conductivity of 3.2 W/m-K (same as intact) is used for sensitivity analysis. Decay heat data for SRS glass is given in Table 1. The rest of the parameter values are shown below. Results of peak temperatures at the waste package surface are given in Table 2.

Regulatory mechanisms for underground waste disposal in Nigeria ...

African Journals Online (AJOL)

Michael Horsfall

Environmental Pollution Control in Nigeria, National Guidelines on Waste Disposal through Underground ... dead, domestic waste and, excrement in this manner. The soil and geological formations that are the waste ... waste water daily is presently seeking partnerships with the ... role in ground water quality protection from.

Saturated and unsaturated stability analysis of slope subjected to rainfall infiltration

OpenAIRE

Gofar Nurly; Rahardjo Harianto

2017-01-01

This paper presents results of saturated and unsaturated stability analysis of typical residual slopes subjected to rainfall infiltration corresponds to 50 years rainfall return period. The slope angles considered were 45° and 70°. The saturated stability analyses were carried out for original and critical ground water level commonly considered by practicing engineer. The analyses were conducted using limit equilibrium method. Unsaturated stability analyses used combination of coupled stress–...

Bed mixing dryer for high moisture content fuels

Energy Technology Data Exchange (ETDEWEB)

Hulkkonen, S; Heinonen, O. [Imatran Voima Oy, Vantaa (Finland)

1998-12-31

Bed mixing dryer is a new type of fuel drying technology for fluidized bed combustion. The idea is to extract hot bed material from the fluidized bed and use it as a heat source for drying the fuel. Drying occurs at steam atmosphere which makes it possible to recover the latent heat of evaporation to process. This improves the thermal efficiency of the power plant process considerably, especially in combined heat and power applications. Imatran Voima Oy (IVO) has developed the Bed Mixing Dryer technology since early 1990s. The first pilot plant was built in 1994 to IVO`s Kuusamo peat and wood fired power plant. The capacity of the plant is 6 MW{sub e} and 20 MW of district heat. In Kuusamo the dryer is connected to a bubbling fluidized bed. Since it`s commissioning the dryer has been used successfully for about 3000 hours during the heating season in wintertime. The second application of the technology will be a demonstration project in Oerebro (S). IVO Power Engineering Ltd will supply in 1997 a dryer to Oerebro Energi`s peat, wood and coal fired CHP plant equipped with circulating fluidized bed boiler. The fuel to be dried is sawdust with fuel input of about 60 MW. In Kuusamo the dryer produces 3 MW of additional district heat and in Oerebro 6 MW. The fuels in Kuusamo are peat, saw dust and bark. In addition to the municipal heat production this type of drying technology has its benefits in pulp and paper industry processes. Disposal of paper mill sludges is becoming more difficult and costly which has resulted in need of alternative treatment. Drying of the sludge before combustion in a boiler for power production is an attractive option. At the moment IVO is carrying out several studies to apply the Bed Mixing Dryer in pulp and paper industry processes. Economy of drying the sludge looks promising

Bed mixing dryer for high moisture content fuels

Energy Technology Data Exchange (ETDEWEB)

Hulkkonen, S.; Heinonen, O. [Imatran Voima Oy, Vantaa (Finland)

1997-12-31

Bed mixing dryer is a new type of fuel drying technology for fluidized bed combustion. The idea is to extract hot bed material from the fluidized bed and use it as a heat source for drying the fuel. Drying occurs at steam atmosphere which makes it possible to recover the latent heat of evaporation to process. This improves the thermal efficiency of the power plant process considerably, especially in combined heat and power applications. Imatran Voima Oy (IVO) has developed the Bed Mixing Dryer technology since early 1990s. The first pilot plant was built in 1994 to IVO`s Kuusamo peat and wood fired power plant. The capacity of the plant is 6 MW{sub e} and 20 MW of district heat. In Kuusamo the dryer is connected to a bubbling fluidized bed. Since it`s commissioning the dryer has been used successfully for about 3000 hours during the heating season in wintertime. The second application of the technology will be a demonstration project in Oerebro (S). IVO Power Engineering Ltd will supply in 1997 a dryer to Oerebro Energi`s peat, wood and coal fired CHP plant equipped with circulating fluidized bed boiler. The fuel to be dried is sawdust with fuel input of about 60 MW. In Kuusamo the dryer produces 3 MW of additional district heat and in Oerebro 6 MW. The fuels in Kuusamo are peat, saw dust and bark. In addition to the municipal heat production this type of drying technology has its benefits in pulp and paper industry processes. Disposal of paper mill sludges is becoming more difficult and costly which has resulted in need of alternative treatment. Drying of the sludge before combustion in a boiler for power production is an attractive option. At the moment IVO is carrying out several studies to apply the Bed Mixing Dryer in pulp and paper industry processes. Economy of drying the sludge looks promising

Temperature profile in a fix-bed reactor and with cylindrical geometry by the method of orthogonal collocation

International Nuclear Information System (INIS)

Basta, C.

1982-01-01

Using the method of orthogonal colocation the boundary problem for a fix bed with cylindrical geometry was solved. The axial disposal term was despicable and the results were compared with those the explicit finite difference method. (E.G.) [pt

Cleanup Verification Package for the 618-2 Burial Ground

Energy Technology Data Exchange (ETDEWEB)

W. S. Thompson

2006-12-28

This cleanup verification package documents completion of remedial action for the 618-2 Burial Ground, also referred to as Solid Waste Burial Ground No. 2; Burial Ground No. 2; 318-2; and Dry Waste Burial Site No. 2. This waste site was used primarily for the disposal of contaminated equipment, materials and laboratory waste from the 300 Area Facilities.

Cleanup Verification Package for the 618-2 Burial Ground

International Nuclear Information System (INIS)

Thompson, W.S.

2006-01-01

This cleanup verification package documents completion of remedial action for the 618-2 Burial Ground, also referred to as Solid Waste Burial Ground No. 2; Burial Ground No. 2; 318-2; and Dry Waste Burial Site No. 2. This waste site was used primarily for the disposal of contaminated equipment, materials and laboratory waste from the 300 Area Facilities

Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments

International Nuclear Information System (INIS)

Cummins, G.D.

1994-06-01

This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste is subject to the TSCA regulations of 40 CFR 761. Interim approval is requested for a period not to exceed 5 years from the date of approval. This request covers only the disposal of small 10 quantities of solid PCB waste contained in decommissioned, defueled submarine reactor compartments (SRC). In addition, the request applies only to disposal 12 of this waste in Trench 94 of the 218-E-12B Burial Ground (Trench 94) in the 13 200 East Area of the US Department of Energy's (DOE) Hanford Facility. Disposal of this waste will be conducted in accordance with the Compliance 15 Agreement (Appendix H) between the DOE Richland Operations Office (DOE-RL) and 16 the US Environmental Protection Agency (EPA), Region 10. During the 5-year interim approval period, the DOE-RL will submit an application seeking final 18 approval for operation of Trench 94 as a chemical waste landfill, including 19 any necessary waivers, and also will seek a final dangerous waste permit from 20 the Washington State Department of Ecology (Ecology) for disposal of lead 21 shielding contained in the SRCS

Investigation of radionuclide release from Solid Waste Disposal Area 3, Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Stueber, A.M.; Webster, D.A.; Munro, I.L.; Farrow, N.D.; Scott, T.G.

1981-08-01

Radionuclide release from Solid Waste Disposal Area (SWDA) 3 has been studied through the analysis of surface and ground waters from the local drainage areas. SWDA 3 is located in the Northwest Tributary drainage basin, a part of the White Oak Creek drainage; 90 Sr is the only radionuclide being discharged in solution in the main stream. Water-level measurements in wells around SWDA 3 suggest the presence of a ground-water divide beneath the southwestern end of the disposal area. Ground water below this area may be moving southwestward toward the Raccoon Creek drainage system. Strontium-90 activity has been detected in this watershed, discharging from a seep adjacent to a Raccoon Creek tributary stream about 640 m southwest of SWDA 3. It appears that 90 Sr is moving through ground-water flow to the northeast and to the southwest of SWDA 3 and that this direction of movement is related to bedrock structure. The trend of a line connecting the two seeps passes through the disposal area and is parallel to bedrock strike. Information from core-hole logs and televiewer logs suggests that 90 Sr in ground water may be moving through solution channels near the contact between units F and G of the Chickamauga Limestone. The apparent extent of migration of 90 Sr in bedrock has implications regarding potential underground radionuclide movement in Melton Valley

Development of closure criteria for inactive radioactive waste disposal sites at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Kocher, D.C.

1989-01-01

The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, specifies that cleanup of inactive waste disposal sites at Department of Energy (DOE) facilities shall at least attain legally applicable or relevant and appropriate requirements (ARARs) for cleanup or control of environmental contamination. This paper discusses potential ARARs for cleanup of inactive radioactive waste disposal sites and proposes a set of closure criteria for such sites at Oak Ridge National Laboratory (ORNL). The most important potential ARARs include Federal standards for radiation protection of the public, radioactivity in drinking water, and near-surface land disposal of radioactive wastes. On the basis of these standards, we propose that cleanup and closure of inactive radioactive waste disposal sites at ORNL shall achieve (1) limits on annual effective dose equivalent for off-site individuals and inadvertent intruders that conform to the DOE's performance objectives for new low-level waste disposal facilities and (2) to the extent reasonably achievable, limits on radionuclide concentrations in ground water and surface waters in accordance with Federal drinking water standards and ground-water protection requirements

Perfluorinated compounds in infiltrated river rhine water and infiltrated rainwater in coastal dunes.

Science.gov (United States)

Eschauzier, Christian; Haftka, Joris; Stuyfzand, Pieter J; de Voogt, Pim

2010-10-01

Different studies have shown that surface waters contain perfluorinated compounds (PFCs) in the low ng/L range. Surface waters are used to produce drinking water and PFCs have been shown to travel through the purification system and form a potential threat to human health. The specific physicochemical properties of PFCs cause them to be persistent and some of them to be bioaccumulative and toxic in the environment. This study investigates the evolvement of PFC concentrations in Rhine water and rainwater during dune water infiltration processes over a transect in the dune area of the western part of The Netherlands. The difference between infiltrated river water and rainwater in terms of PFC composition was investigated. Furthermore, isomer profiles were investigated. The compound perfluorobutanesulfonate (PFBS) was found at the highest concentrations of all PFCs investigated, up to 37 ng/L in infiltrated river water (71 ± 13% of ΣPFCs). This is in contrast with the predominant occurrence of perfluorooctanoic acid (PFOA) and perfluorooctanesulfonate (PFOS) reported in literature. The concentrations of PFBS found in infiltrated river Rhine water were significantly higher than those in infiltrated rainwater. For perfluorohexanesulfonate (PFHxS) the opposite was found: infiltrated rainwater contained more than infiltrated river water. The concentrations of PFOA, perfluorohexanoic acid (PFHxA), perfluoroheptanoic acid (PFHpA), PFBS, PFOS, and PFHxS in infiltrated river water showed an increasing trend with decreasing age of the water. The relative contribution of the branched PFOA and PFOS isomers to total concentrations of PFOA and PFOS showed a decreasing trend with decreasing age of the water.

Onsite disposal of radioactive waste: Estimating potential groundwater contamination

International Nuclear Information System (INIS)

Goode, D.J.; Neuder, S.M.; Pennifill, R.A.; Ginn, T.

1986-11-01

Volumes 1 and 2 of this report describe the NRC's methodology for assessing the potential public health and environmental impacts associated with onsite disposal of very low activity radioactive materials. This volume (Vol. 3) describes a general methodology for predicting potential groundwater contamination from onsite disposal. The methodology includes formulating a conceptual model, representing the conceptual model mathematically, estimating conservative parameters, and predicting receptor concentrations. Processes which must generally be considered in the methodology include infiltration, leaching of radionuclides from the waste, transport to the saturated zone, transport within the saturated zone, and withdrawal at a receptor location. A case study of shallow burial of iodine-125 illustrates application of the MOCMOD84 version of the US Geological Survey's 2-D solute transport model and a corresponding analytical solution. The appendices include a description and listing of MOCMOD84, descriptions of several analytical solution techniques, and a procedure for estimating conservative groundwater velocity values

Radioactive waste disposal: Recommendations for a repository site selection

International Nuclear Information System (INIS)

Cadelli, N.; Orlowski, S.

1992-01-01

This report is a guidebook on recommendations for site selection of radioactive waste repository, based on a consensus in european community. This report describes particularly selection criteria and recommendations for radioactive waste disposal in underground or ground repositories. 14 refs

Radioactive waste disposal in geological formations

International Nuclear Information System (INIS)

Gera, F.

1977-01-01

The nuclear energy controversy, now raging in several countries, is based on two main issues: the safety of nuclear plants and the possibility to dispose safely of the long-lived radioactive wastes. Consideration of the evolution of the hazard potential of waste in function of decay time leads to a somewhat conservative reference containment time in the order of one hundred thousand years. Several concepts have been proposed for the disposal of long-lived wastes. At the present time, emplacement into suitable geological formations under land areas can be considered the most promising disposal option. It is practically impossible to define detailed criteria to be followed in selecting suitable sites for disposal of long-lived wastes. Basically there is a single criterion, namely; that the geological environment must be able to contain the wastes for at least a hundred thousand years. However, due to the extreme variability of geological settings, it is conceivable that this basic capability could be provided by a great variety of different conditions. The predominant natural mechanism by which waste radionuclides could be moved from a sealed repository in a deep geological formation into the biosphere is leaching and transfer by ground water. Hence the greatest challenge is to give a satisfactory demonstration that isolation from ground water will persist over the required containment time. Since geological predictions are necessarily affected by fairly high levels of uncertainty, the only practical approach is not a straight-forward forecast of future geological events, but a careful assessment of the upper limits of geologic changes that could take place in the repository area over the next hundred thousand years. If waste containment were to survive these extreme geological changes the disposal site could be considered acceptable. If some release of activity were to take place in consequence of the hypothetical events the disposal solution might still be

Numerical simulations of fire spread in a Pinus pinaster needles fuel bed

International Nuclear Information System (INIS)

Menage, D; Chetehouna, K; Mell, W

2012-01-01

The main aim of this paper is to extend the cases of WFDS model validation by comparing its predictions to literature data on a ground fire spreading in a Pinus pinaster needles fuel bed. This comparison is based on the experimental results of Mendes-Lopes and co-workers. This study is performed using the same domain as in the experiments (3.0m×1.2m×0.9m) with a mesh of 49,280 cells. We investigate the influence of wind (varied between 0 and 2 m/s) and moisture content (10 and 18%) on the rate of spread. The WFDS rate of spread is determined using a cross-correlation function of ground temperature profiles. The simulated rate of spread, as well as temperature, compared favourably to experimental values and show the WFDS model capacity to predict ground fires in Pinus Pinaster fuel beds.

Numerical simulations of fire spread in a Pinus pinaster needles fuel bed

Science.gov (United States)

Menage, D.; Chetehouna, K.; Mell, W.

2012-11-01

The main aim of this paper is to extend the cases of WFDS model validation by comparing its predictions to literature data on a ground fire spreading in a Pinus pinaster needles fuel bed. This comparison is based on the experimental results of Mendes-Lopes and co-workers. This study is performed using the same domain as in the experiments (3.0m×1.2m×0.9m) with a mesh of 49,280 cells. We investigate the influence of wind (varied between 0 and 2 m/s) and moisture content (10 and 18%) on the rate of spread. The WFDS rate of spread is determined using a cross-correlation function of ground temperature profiles. The simulated rate of spread, as well as temperature, compared favourably to experimental values and show the WFDS model capacity to predict ground fires in Pinus Pinaster fuel beds.

Technical approach for the management of UMTRA ground water investigation-derived wastes

International Nuclear Information System (INIS)

1994-02-01

During characterization, remediation, or monitoring activities of the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project, ground water samples are collected to assess the extent and amount of waterborne contamination that might have come from the mill tailings. This sampling sometimes occurs in contaminated areas where ground water quality has been degraded. Ground water sampling activities may result in field-generated wastes that must be disposed of in a manner protective of human health and the environment. During ground water sampling, appropriate measures must be taken to dispose of presampling purge water and well development water that is pumped to flush out any newly constructed wells. Additionally, pumping tests may produce thousands of gallons of potentially contaminated ground water that must be properly managed. In addition to the liquid wastes, there is the potential for bringing contaminated soils to the ground surface during the drilling and installation of water wells in areas where the subsurface soils may be contaminated. These soils must be properly managed as well. This paper addresses the general technical approach that the UMTRA Project will follow in managing field-generated wastes from well drilling, development, sampling, and testing. It will provide guidance for the preparation of Technical Assistance Contractor (TAC) Standard Operating Procedures (SOP) for the management and disposal of field-generated wastes from ground water monitoring and remediation activities

COOLOCE debris bed experiments and simulations investigating the coolability of cylindrical beds with different materials and flow modes

Energy Technology Data Exchange (ETDEWEB)

Takasuo, E.; Kinnunen, T.; Holmstroem, S.; Lehtikuusi, T. [VTT Technical Research Centre of Finland (Finland)

2013-07-15

The COOLOCE experiments aim at investigating the coolability of debris beds of different geometries, flow modes and materials. A debris bed may be formed of solidified corium as a result of a severe accident in a nuclear power reactor. The COOLOCE-8 test series consisted of experiments with a top-flooded test bed with irregular gravel as the simulant material. The objective was to produce comparison data useful in estimating the effects of different particle materials and the possible effect of the test arrangement on the results. It was found that the dryout heat flux (DHF) measured for the gravel was lower compared to previous experiments with spherical beads, and somewhat lower compared to the early STYX experiments. The difference between the beads and gravel is at least partially explained by the smaller average size of the gravel particles. The COOLOCE-9 test series included scoping experiments examining the effect of subcooling of the water pool in which the debris bed is immersed. The experiments with initially subcooled pool suggest that the subcooling may increase DHF and increase coolability. The aim of the COOLOCE-10 experiments was to investigate the effect of lateral flooding on the DHF a cylindrical test bed. The top of the test cylinder and its sidewall were open to water infiltration. It was found that the DHF is increased compared to a top-flooded cylinder by more than 50%. This suggests that coolability is notably improved. 2D simulations of the top-flooded test beds have been run with the MEWA code. Prior to the simulations, the effective particle diameter for the spherical beads and the irregular gravel was estimated by single-phase pressure loss measurements performed at KTH in Sweden. Parameter variations were done for particle size and porosity used as input in the models. It was found that with the measured effective particle diameter and porosity, the simulation models predict DHF with a relatively good accuracy in the case of spherical

Storing in clay beds? What about research advancement?

International Nuclear Information System (INIS)

Lebon, P.

2006-01-01

The concept of underground disposal of toxic or radioactive materials is based on the idea that some geologic formations are capable to ensure the confinement of waste packages over very long periods of time by limiting the water influx towards the toxic elements and by fixing up those in solution. This paper presents the state-of-the-art about the researches on manufactured clays (nature, properties and conditioning) and about the researches on clay beds with the example of the Meuse/Haute-Marne (France) underground laboratory (geologic history, lithology, permeability, rock mechanics). (J.S.)

USE THE METHOD OF DIMENSIONING OF INFILTRATION-RETENTION BASINS FOR MANAGEMENT OF RAINWATER

Directory of Open Access Journals (Sweden)

Ewa Suchanek

2015-01-01

Full Text Available The easiest way to “use” rainwater is its detention in places where it falls, and referral to the ground. Systems of rainwater utilization system can be implemented in different variants. In the simplest configuration it is a tank, with a runoff from the roof. The principle of operation of the tank (basin is a method for rain water management. The article presents a practical application of methods of dimensioning infiltration basins by performing calculations showing how to alter the dimensions of the basin when changing the ground conditions while maintaining the same filling.

Ultrasound-Guided Intermediate Site Greater Occipital Nerve Infiltration: A Technical Feasibility Study.

Science.gov (United States)

Zipfel, Jonathan; Kastler, Adrian; Tatu, Laurent; Behr, Julien; Kechidi, Rachid; Kastler, Bruno

2016-01-01

Two studies recently reported that computed tomography (CT) guided infiltration of the greater occipital nerve at its intermediate site allows a high efficacy rate with long-lasting pain relief following procedure in occipital neuralgia and in various craniofacial pain syndromes. The purpose of our study was to evaluate the technical feasibility and safety of ultrasound-guided intermediate site greater occipital nerve infiltration. Retrospective study. This study was conducted at the imaging department of a 1,409 bed university hospital. Local institutional review board approval was obtained and written consent was waived. In this retrospective study, 12 patients suffering from refractory occipital neuralgia or craniofacial pain syndromes were included between April and October 2014. They underwent a total of 21 ultrasound-guided infiltrations. Infiltration of the greater occipital nerve was performed at the intermediate site of the greater occipital nerve, at its first bend between obliqus capitis inferior and semispinalis capitis muscles with local anestetics and cortivazol. Technical success was defined as satisfactory diffusion of added iodinated contrast media in the fatty space between these muscles depicted on control CT scan. We also reported first data of immediate block test efficacy and initial clinical efficacy at 7 days, one month, and 3 months, defined by a decrease of at least 50% of visual analog scale (VAS) scores. Technical success rate was 95.24%. Patients suffered from right unilateral occipital neuralgia in 3 cases, left unilateral occipital neuralgia in 2 cases, bilateral occipital neuralgia in 2 cases, migraine in one case, cervicogenic headache in one case, tension-type headache in 2 cases, and cluster headache in one case. Block test efficacy was found in 93.3% (14/15) cases. Clinical efficacy was found in 80% of cases at 7 days, in 66.7% of cases at one month and in 60% of cases at 3 months. No major complications were noted. Some of the

Ground Water Monitoring Requirements for Hazardous Waste Treatment, Storage and Disposal Facilities

Science.gov (United States)

The groundwater monitoring requirements for hazardous waste treatment, storage and disposal facilities (TSDFs) are just one aspect of the Resource Conservation and Recovery Act (RCRA) hazardous waste management strategy for protecting human health and the

Experimental characterization of cement-bentonite interaction using core infiltration techniques coupled with 4D X-ray tomography

International Nuclear Information System (INIS)

Dolder, F.; Maeder, U.; Jenni, A.

2012-01-01

Document available in extended abstract form only. Deep geological disposal of radioactive waste foresee cementitious materials as reinforcement of tunnels, backfill, or as waste matrix. Bentonite, or sand-bentonite mixtures, are proposed as backfill material enclosing spent fuel drums, or as drift seals. The emplacement of cementitious material next to clay material generates an enormous chemical gradient in pore water, which drives diffusive transport. Laboratory studies and reactive transport modeling predict significant mineral alteration on both sides of interfaces, mainly resulting in a decrease of porosity in bentonite. The goal of the project is to characterize and quantify the cement/bentonite skin effects spatially and temporally. The expected analytical data set will be amenable to interpretation by reactive transport modeling. The project focuses on the advective-diffusive transport domain, resolved at intermediate spatial scales. The experiments are carried out in a newly developed X-ray transparent core infiltration apparatus, constructed from carbon fiber compounds and suitable for confining and infiltration pressures up to 80 bars. This setup allows to performing X-ray computed tomography scans (CT) periodically without interrupting the running core infiltration experiment. The experiment is performed on cylindrical bentonite samples (50 by 50 mm) compacted and saturated in-house with a dedicated device (Fig. 1, top). A sample is mounted in the core infiltration apparatus (Fig. 1, bottom) and subjected to a confining pressure in order to simulate underground repository conditions proposed by NAGRA (Swiss National Cooperative for the Disposal of Radioactive Waste). The infiltration of high-pH cement pore-fluids into the bentonite plug is expected to alter the mineral assemblage over time as an advancing reaction front. The related change in phase densities, porosity and bulk density is tracked over time recording periodically non-destructive CT scans

Long-term surveillance plan for the Gunnison, Colorado disposal site. Revision 2

International Nuclear Information System (INIS)

1997-02-01

This long-term surveillance plan (LTSP) describes the US Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The US Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance

DSEM, Radioactive Waste Disposal Site Economic Model

International Nuclear Information System (INIS)

Smith, P.R.

2005-01-01

1 - Description of program or function: The Disposal Site Economic Model calculates the average generator price, or average price per cubic foot charged by a disposal facility to a waste generator, one measure of comparing the economic attractiveness of different waste disposal site and disposal technology combinations. The generator price is calculated to recover all costs necessary to develop, construct, operate, close, and care for a site through the end of the institutional care period and to provide the necessary financial returns to the site developer and lender (when used). Six alternative disposal technologies, based on either private or public financing, can be considered - shallow land disposal, intermediate depth disposal, above or below ground vaults, modular concrete canister disposal, and earth mounded concrete bunkers - based on either private or public development. 2 - Method of solution: The economic models incorporate default cost data from the Conceptual Design Report (DOE/LLW-60T, June 1987), a study by Rodgers Associates Engineering Corporation. Because all costs are in constant 1986 dollars, the figures must be modified to account for inflation. Interest during construction is either capitalized for the private developer or rolled into the loan for the public developer. All capital costs during construction are depreciated over the operation life of the site using straight-line depreciation for the private sector. 3 - Restrictions on the complexity of the problem: Maxima of - 100 years post-operating period, 30 years operating period, 15 years pre-operating period. The model should be used with caution outside the range of 1.8 to 10.5 million cubic feet of total volume. Depreciation is not recognized with public development

Mechanics of Ship Grounding

DEFF Research Database (Denmark)

Pedersen, Preben Terndrup

1996-01-01

In these notes first a simplified mathematical model is presented for analysis of ship hull loading due to grounding on relatively hard and plane sand, clay or rock sea bottoms. In a second section a more rational calculation model is described for the sea bed soil reaction forces on the sea bott...

Behavior of cement paste as backfill in waste disposal boreholes

International Nuclear Information System (INIS)

Ferreira, Eduardo G.A.; Isiki, Vera L.K.; Miyamoto, Hissae; Marumo, Julio T.; Vicente, Roberto

2011-01-01

The Radioactive Waste Management Laboratory (GRR) at the Nuclear and Energy Research Institute (IPEN) in Sao Paulo, Brazil, is developing the concept a repository for disposition of disused sealed radioactive sources in a deep borehole, aiming at providing a feasible and inexpensive alternative for final disposal. A relevant fraction of the Brazilian inventory of sources has long half-life which prevents them to be disposed of in shallow ground disposal facilities. In the concept of repository under study, Portland cement paste is intended to be used as a backfill between the steel casing and the geological formation around the borehole. Cement paste will function as structural, an additional barrier against the migration of radionuclides outside the repository, and as a blockage against the transport of water between the different strata of the geological setting. The durability of cementitious materials under the conditions prevailing at the depth of disposal is as yet unknown. The objective of this research is to investigate the behavior of the cement paste and to estimate its service life. In this paper we present the results of mechanical strength measurements and chemical and mineralogical analysis of samples to detect the changes caused by radiation, temperature and aggressive chemicals present in ground water. Techniques of analysis included Inductively Coupled Plasma Atomic Emission Spectroscopy, Ion Chromatography, X-Ray Diffraction, and Thermo-Gravimetric Analysis. (author)

High integrity container evaluation for solid waste disposal burial containers

International Nuclear Information System (INIS)

Josephson, W.S.

1996-01-01

In order to provide radioactive waste disposal practices with the greatest measure of public protection, Solid Waste Disposal (SWD) adopted the Nuclear Regulatory Commission (NRC) requirement to stabilize high specific activity radioactive waste prior to disposal. Under NRC guidelines, stability may be provided by several mechanisms, one of which is by placing the waste in a high integrity container (HIC). During the implementation process, SWD found that commercially-available HICs could not accommodate the varied nature of weapons complex waste, and in response developed a number of disposal containers to function as HICs. This document summarizes the evaluation of various containers that can be used for the disposal of Category 3 waste in the Low Level Burial Grounds. These containers include the VECTRA reinforced concrete HIC, reinforced concrete culvert, and the reinforced concrete vault. This evaluation provides justification for the use of these containers and identifies the conditions for use of each

Subsurface disposal of liquid low-level radioactive wastes at Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Stow, S.H.; Haase, C.S.

1986-01-01

At Oak Ridge National Laboratory (ORNL) subsurface injection has been used to dispose of low-level liquid nuclear waste for the last two decades. The process consists of mixing liquid waste with cement and other additives to form a slurry that is injected under pressure through a cased well into a low-permeability shale at a depth of 300 m (1000 ft). The slurry spreads from the injection well along bedding plane fractures and forms solid grout sheets of up to 200 m (660 ft) in radius. Using this process, ORNL has disposed of over 1.5 x 10 6 Ci of activity; the principal nuclides are 90 Sr and 137 Cs. In 1982, a new injection facility was put into operation. Each injection, which lasts some two days, results in the emplacement of approximately 750,000 l (180,000 gal) of slurry. Disposal cost per liter is approximately $0.30, including capital costs of the facility. This subsurface disposal process is fundamentally different from other operations. Wastes are injected into a low-permeability aquitard, and the process is designed to isolate nuclides, preventing dispersion in groundwaters. The porosity into which wastes are injected is created by hydraulically fracturing the host formation along bedding planes. The site is in the structurally complex Valley and Ridge Province. The stratigraphy consists of lower Paleozoic rocks. Investigations are under way to determine the long-term hydrologic isolation of the injection zone and the geochemical impact of saline groundwater on nuclide mobility. Injections are monitored by gamma-ray logging of cased observation wells to determine grout sheet orientation after an injection. Recent monitoring work has involved the use of tiltmeters, surface uplift surveys, and seismic arrays. 26 refs., 7 figs

BedMachine v3: Complete Bed Topography and Ocean Bathymetry Mapping of Greenland From Multibeam Echo Sounding Combined With Mass Conservation

DEFF Research Database (Denmark)

Morlighem, M.; Williams, C. N.; Rignot, E.

2017-01-01

Greenland's bed topography is a primary control on ice flow, grounding line migration, calving dynamics, and subglacial drainage. Moreover, fjord bathymetry regulates the penetration of warm Atlantic water (AW) that rapidly melts and undercuts Greenland's marine‐terminating glaciers. Here we...... present a new compilation of Greenland bed topography that assimilates seafloor bathymetry and ice thickness data through a mass conservation approach. A new 150 m horizontal resolution bed topography/bathymetric map of Greenland is constructed with seamless transitions at the ice/ocean interface......, yielding major improvements over previous data sets, particularly in the marine‐terminating sectors of northwest and southeast Greenland. Our map reveals that the total sea level potential of the Greenland ice sheet is 7.42 ± 0.05 m, which is 7 cm greater than previous estimates. Furthermore, it explains...

The WIPP research and development program: providing the technical basis for defense waste disposal

International Nuclear Information System (INIS)

Hunter, Th.O.

1983-01-01

The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, is being developed by the US Department of Energy as a research and development facility to demonstrate the safe disposal of radioactive wastes from the defense programs of the United States. Underground workings are at a depth of 660 in a bedded-salt formation. Site investigations began in the early 1970s and are culminating with the completion of the Site and Preliminary Design Validation (SPDV) program in 1983 in which two shafts and several thousand feet of underground drifts are being constructed. The underground facility will be used for in situ tests and demonstrations that address technical issues associated with the disposal of transuranic and defense high-level wastes (DHLW) in bedded salt. These tests are based on several years of laboratory tests, field tests in mines, and analytical modeling studies. They primarily address repository development in bedded salt, including thermal-structural interactions plugging and sealing, and facility operations; and waste package interactions, including the effects of the waste on local rock salt and the evaluation of waste package materials. In situ testing began in the WIPP with the initiation of the SPDV program in 1981. In 1983, a major series of tests will begin to investigate the response of the rock salt without the use of any radioactivity

Net-infiltration map of the Navajo Sandstone outcrop area in western Washington County, Utah

Science.gov (United States)

Heilweil, Victor M.; McKinney, Tim S.

2007-01-01

As populations grow in the arid southwestern United States and desert bedrock aquifers are increasingly targeted for future development, understanding and quantifying the spatial variability of net infiltration and recharge becomes critically important for inventorying groundwater resources and mapping contamination vulnerability. A Geographic Information System (GIS)-based model utilizing readily available soils, topographic, precipitation, and outcrop data has been developed for predicting net infiltration to exposed and soil-covered areas of the Navajo Sandstone outcrop of southwestern Utah. The Navajo Sandstone is an important regional bedrock aquifer. The GIS model determines the net-infiltration percentage of precipitation by using an empirical equation. This relation is derived from least squares linear regression between three surficial parameters (soil coarseness, topographic slope, and downgradient distance from outcrop) and the percentage of estimated net infiltration based on environmental tracer data from excavations and boreholes at Sand Hollow Reservoir in the southeastern part of the study area.Processed GIS raster layers are applied as parameters in the empirical equation for determining net infiltration for soil-covered areas as a percentage of precipitation. This net-infiltration percentage is multiplied by average annual Parameter-elevation Regressions on Independent Slopes Model (PRISM) precipitation data to obtain an infiltration rate for each model cell. Additionally, net infiltration on exposed outcrop areas is set to 10 percent of precipitation on the basis of borehole net-infiltration estimates. Soils and outcrop net-infiltration rates are merged to form a final map.Areas of low, medium, and high potential for ground-water recharge have been identified, and estimates of net infiltration range from 0.1 to 66 millimeters per year (mm/yr). Estimated net-infiltration rates of less than 10 mm/yr are considered low, rates of 10 to 50 mm/yr are

Sensitivity of long-term bare soil infiltration simulations to hydraulic properties in an arid environment

International Nuclear Information System (INIS)

Stothoff, S.A.

1997-01-01

The suitability of Yucca Mountain, Nevada, for emplacement of a high-level nuclear waste geologic repository is currently being evaluated. Assessments of the repository performance suggest that the uncertainty in infiltration rates strongly affects predicted repository performance. Most of the ground surface over the potential repository footprint is characterized by shallow to deep colluvium/alluvium overlying densely fractured, welded tuffs. In order to identify characteristic behavior of infiltration that might be expected at the site, two idealizations of this situation are examined: an effectively semi-infinite column of alluvium and a two-layer column of alluvium over a fractured impermeable matrix. For each idealization the impact of hydraulic properties is assessed. Examining the sensitivity of bare soil simulator predictions for an effectively semi-infinite column, it is found that decreasing the air entry pressure while holding all other parameters at a fixed level tends to increase both the long-term average moisture content and the long-term average net infiltration flux for homogeneous media. In contrast, increasing the van Genuchten scale parameter (m = 1 - 1/n) or decreasing the porosity tends to decrease the average soil moisture but increase the infiltration. Most interestingly, three regimes are found for permeability. For relatively high permeabilities, there is a trend toward increasing average infiltration and increasing average moisture content with decreasing permeability. For relatively low permeabilities, vapor transport dominates over liquid transport, runoff and evaporation overwhelm infiltration, and the soil becomes very dry with essentially no infiltration flux Between the extreme cases of high and low permeability, there is a zone where decreasing permeability results in decreased infiltration but increased moisture content

Disposal of radioactive wastes. A review of IAEA efforts to assure safety

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-07-15

A variety of methods for the discharge of radioactive wastes into the ground, into water and into the air were described at an international conference in Monaco in November 1959, organized by IAEA jointly with UNESCO and with the co-operation of FAO. Many of the experts at the conference were of the view that most of the proposed, or actually applied, methods of waste disposal were compatible with safety requirements. Some differences of opinion existed about disposal into the sea. It was generally agreed that much additional research was necessary for devising the most effective and economical methods of disposal and gaining a better knowledge of the effects of the various types of disposal operations.

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.

Bed blocking by elderly patients in general-hospital wards.

Science.gov (United States)

Rubin, S G; Davies, G H

1975-08-01

A point prevalence survey, using a questionnaire, was performed in three general hospitals to investigate the problem of elderly patients blocking acute-hospital beds. A total of 1010 occupied general beds were surveyed and all patients, over the age of 60 years, who had been in hospital more than four weeks, and who, in the opinion of medical and nursing staff, were no longer in need of the facilities of a general hospital, were investigated. Forty-eight patients (4.8 per cent of the total) were found to be genuinely in bed inappropriate to their needs. Rehabilitation, together with assessment of these patients, appeared disorganized and lacked consistency, and decisions regarding suitable 'disposal' appeared to be made without sufficient consultation and conformed to no detectable pattern. The main reason for the continuing bed occupancy of the patients was the length of the waiting lists for alternative residential accommodation and the main single medical factor preventing discharge home or to a hostel was the problem of mobility. By interviewing staff and patients and scrutinizing the questionnaires, it was found that 23 patients (48 per cent) were only suitable for transfer to a long-stay hospital. Of these, however, 15 (31 per cent) could be placed in specialized accommodation if some degree of nursing care, at present not available, was provided.

Radioactive waste disposal - ethical and environmental considerations - A Canadian perspective

International Nuclear Information System (INIS)

Roots, F.

1994-01-01

This work deals with ethical and environmental considerations of radioactive waste disposal in Canada. It begins with the canadian attitudes toward nature and environment. Then are given the canadian institutions which reflect an environmental ethic, the development of a canadian radioactive waste management policy, the establishment of formal assessment and review process for a nuclear fuel waste disposal facility, some studies of the ethical and risk dimensions of nuclear waste decisions, the canadian societal response to issues of radioactive wastes, the analysis of risks associated with fuel waste disposal, the influence of other energy related environmental assessments and some common ground and possible accommodation between the different views. (O.L.). 50 refs

Research of Rainwater Infiltration in Eastern Slovakia

Directory of Open Access Journals (Sweden)

Hudáková Gabriela

2015-11-01

Full Text Available Today precipitation water in the majority of built up and other sealed surface areas no longer reach the water circulation system via natural routes. This can lead to long-term changes to the soil and water resources, reduce the natural local regeneration of the groundwater and have effects on the chemical and biological conditions above and below the ground surface. Reasonable rainwater management leads to maintain or recover a sound and sustainable water cycle. The purpose of this paper is to present objectives and monitoring of a drainage project in Eastern Slovakia, in Kosice city. The paper focuses on percolation facilities in the research area of campus of Technical University and measurements connected with rainwater infiltration.

Method of disposing of shut-down nuclear power plants

International Nuclear Information System (INIS)

Gaiser, H.

1984-01-01

A shut-down atomic power plant or a section thereof, particularly the nuclear reactor, is disposed of by sinking it to below ground level by constructing a caisson with cutting edges from the foundations of said plant or section or by excavating a pit therebelow

Long-term natural attenuation of carbon and nitrogen within a groundwater plume after removal of the treated wastewater source.

Science.gov (United States)

Repert, Deborah A; Barber, Larry B; Hess, Kathryn M; Keefe, Steffanie H; Kent, Douglas B; LeBlanc, Denis R; Smith, Richard L

2006-02-15

Disposal of treated wastewater for more than 60 years onto infiltration beds on Cape Cod, Massachusetts produced a groundwater contaminant plume greater than 6 km long in a surficial sand and gravel aquifer. In December 1995 the wastewater disposal ceased. A long-term, continuous study was conducted to characterize the post-cessation attenuation of the plume from the source to 0.6 km downgradient. Concentrations and total pools of mobile constituents, such as boron and nitrate, steadily decreased within 1-4 years along the transect. Dissolved organic carbon loads also decreased, but to a lesser extent, particularly downgradient of the infiltration beds. After 4 years, concentrations and pools of carbon and nitrogen in groundwater were relatively constant with time and distance, but substantially elevated above background. The contaminant plume core remained anoxic for the entire 10-year study period; temporal patterns of integrated oxygen deficit decreased slowly at all sites. In 2004, substantial amounts of total dissolved carbon (7 mol C m(-2)) and fixed (dissolved plus sorbed) inorganic nitrogen (0.5 mol N m(-2)) were still present in a 28-m vertical interval at the disposal site. Sorbed constituents have contributed substantially to the dissolved carbon and nitrogen pools and are responsible for the long-term persistence of the contaminant plume. Natural aquifer restoration at the discharge location will take at least several decades, even though groundwater flow rates and the potential for contaminant flushing are relatively high.

Ground-water exploration in Al Marj area, Cyrenaica, United Kingdom of Libya

Science.gov (United States)

Newport, T.G.; Haddor, Yousef

1963-01-01

The present report, based largely on fieldwork during 1959-61, describes the results of reconnaissance hydrogeologic studies and exploratory drilling to evaluate the general water-bearing properties of the rocks and the availability of groundwater supplies for irrigation, stock, and village uses in Al Marj area. These studies and the drilling were conducted under the auspices of the U.S. Operations Mission of the International Cooperation Administration. Al Marj area, located in the Province of Cyrenaica on the southern coast of the Mediterranean Sea, contains a land area of about 6,770 square kilometers. Along the Mediterranean shore is a narrow coastal plain that rises evenly to the base of an escarpment that forms the seaward front of an undulating plateau known as. Al Jabal al Akhgiar. The climate is semiarid; seasonal rainfall occurs during the winter months. Owing to orographic effects, the rainfall is somewhat higher in the Jabal than in the coastal plain. The average annual rainfall ranges from about 250 millimeters in the coastal plain to 450 millimeters on the Jabal. All the streams (wadis) of the area are ephemeral and flow only in response to heavy rains of the winter season. From a drainage divide on the Jabal some streams flow north and northwest toward the sea and the others, south and southeast to the interior desert. Solution features, such as limestone sink holes, are common in the coastal plain and a large solution depression occurs near Al Marj. The rocks of A1 Marj area consist predominantly of limestone and some sandstone and shale; they range from Cretaceous to Miocene age. On the coastal plain Miocene limestone is locally mantled by Quaternary alluvial, beach and lagoonal deposits. The Miocene and older beds have a regional southerly dip. These rocks are broken by northeast-trending normal faults in the coastal and inland escarpments. The ground-water reservoir is contained chiefly in fractures, bedding planes, and solution openings in the

Seismic safety in nuclear-waste disposal

International Nuclear Information System (INIS)

Carpenter, D.W.; Towse, D.

1979-01-01

Seismic safety is one of the factors that must be considered in the disposal of nuclear waste in deep geologic media. This report reviews the data on damage to underground equipment and structures from earthquakes, the record of associated motions, and the conventional methods of seismic safety-analysis and engineering. Safety considerations may be divided into two classes: those during the operational life of a disposal facility, and those pertinent to the post-decommissioning life of the facility. Operational hazards may be mitigated by conventional construction practices and site selection criteria. Events that would materially affect the long-term integrity of a decommissioned facility appear to be highly unlikely and can be substantially avoided by conservative site selection and facility design. These events include substantial fault movement within the disposal facility and severe ground shaking in an earthquake epicentral region. Techniques need to be developed to address the question of long-term earthquake probability in relatively aseismic regions, and for discriminating between active and extinct faults in regions where earthquake activity does not result in surface ruptures

Seismic safety in nuclear-waste disposal

Energy Technology Data Exchange (ETDEWEB)

Carpenter, D.W.; Towse, D.

1979-04-26

Seismic safety is one of the factors that must be considered in the disposal of nuclear waste in deep geologic media. This report reviews the data on damage to underground equipment and structures from earthquakes, the record of associated motions, and the conventional methods of seismic safety-analysis and engineering. Safety considerations may be divided into two classes: those during the operational life of a disposal facility, and those pertinent to the post-decommissioning life of the facility. Operational hazards may be mitigated by conventional construction practices and site selection criteria. Events that would materially affect the long-term integrity of a decommissioned facility appear to be highly unlikely and can be substantially avoided by conservative site selection and facility design. These events include substantial fault movement within the disposal facility and severe ground shaking in an earthquake epicentral region. Techniques need to be developed to address the question of long-term earthquake probability in relatively aseismic regions, and for discriminating between active and extinct faults in regions where earthquake activity does not result in surface ruptures.

Study on the possibility of sea-disposal of krypton-85

International Nuclear Information System (INIS)

Dalen, A. van; Vons, L.H.; Verkerk, B.

1980-01-01

Results of a feasibility study, performed under a contract with the Commission of the European Communities, regarding technical and radiological aspects of sea-disposal of all krypton-85 retained in a large fuel reprocessing facility, are presented. The design of a double-walled, essentially spherical container is described that provides both double containment of the compressed gas and permanent 'disposable' radiation shielding. Three sizes have been studied, i.e. with internal volumes of 0.01, 0.05 and 0.1 m 3 , each designed to hold 0.1 m 3 (STP) of krypton, and each containing approximately 400 TBq of 85 Kr per 0.001 m 3 sphere volume. This results in an internal heat production of 17.5 kW/m 3 . Calculations of temperatures and stresses that would result from the conditions of the required fire test for B(U) transport packages showed that the design would allow the containers to pass this test. Radiological consequences have been considered for disposal of petabecquerel amounts of 85 Kr as a function of undamaged container lifetime on the sea bed. Finally, an indication is given of the necessary amendments to the London Convention in order to allow sea-disposal of these large amounts of radioactive krypton. (author)

Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

International Nuclear Information System (INIS)

2003-12-01

Radioactive waste must be managed safely, consistent with internationally agreed safety standards. The disposal method chosen for the waste should be commensurate with the hazard and longevity of the waste. Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. The term 'near surface disposal' encompasses a wide range of design options, including disposal in engineered structures at or just below ground level, disposal in simple earthen trenches a few metres deep, disposal in engineered concrete vaults, and disposal in rock caverns several tens of metres below the surface. The use of a near surface disposal option requires design and operational measures to provide for the protection of human health and the environment, both during operation of the disposal facility and following its closure. To ensure the safety of both workers and the public (both in the short term and the long term), the operator is required to design a comprehensive waste management system for the safe operation and closure of a near surface disposal facility. Part of such a system is to establish criteria for accepting waste for disposal at the facility. The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures and in addition, to prevent or limit hazards, which could arise from non-radiological causes. Waste acceptance criteria include limits on radionuclide content concentration in waste materials, and radionuclide amounts in packages and in the repository as a whole. They also include limits on quantity of free liquids, requirements for exclusion of chelating agents and pyrophoric materials, and specifications of the characteristics of the waste containers. Largely as a result of problems encountered at some disposal facilities operated in the past, in 1985 the IAEA published guidance on generic acceptance

Geotechnical aspects of deep ocean radioactive waste disposal

International Nuclear Information System (INIS)

Freeman, T.J.

1990-01-01

The methods that might be used to bury radioactive waste in the deep ocean, and their likely effect on the sediment barrier, have been the subject of an international research program performed during the last ten years. This paper reviews the geotechnical aspects of deep ocean disposal and discusses how far the research performed has gone towards providing the information needed to assess this form of disposal. Considerable progress has been made during the course of the international program towards understanding the processes involved in the emplacement of heat generating waste (HGW) into the deep ocean bed and the subsequent interactions between the waste and the sediments. These processes do not appear to have a deleterious effect on the barrier properties of the sediments, and it is concluded that it is likely that HGW could be emplaced in the deep ocean in such a way that the seabed would provide an effective containment for the radionuclides

Combined geophysical methods for mapping infiltration pathways at the Aurora Water Aquifer recharge and recovery site

Science.gov (United States)

Jasper, Cameron A.

Although aquifer recharge and recovery systems are a sustainable, decentralized, low cost, and low energy approach for the reclamation, treatment, and storage of post- treatment wastewater, they can suffer from poor infiltration rates and the development of a near-surface clogging layer within infiltration ponds. One such aquifer recharge and recovery system, the Aurora Water site in Colorado, U.S.A, functions at about 25% of its predicted capacity to recharge floodplain deposits by flooding infiltration ponds with post-treatment wastewater extracted from river bank aquifers along the South Platte River. The underwater self-potential method was developed to survey self-potential signals at the ground surface in a flooded infiltration pond for mapping infiltration pathways. A method for using heat as a groundwater tracer within the infiltration pond used an array of in situ high-resolution temperature sensing probes. Both relatively positive and negative underwater self-potential anomalies are consistent with observed recovery well pumping rates and specific discharge estimates from temperature data. Results from electrical resistivity tomography and electromagnetics surveys provide consistent electrical conductivity distributions associated with sediment textures. A lab method was developed for resistivity tests of near-surface sediment samples. Forward numerical modeling synthesizes the geophysical information to best match observed self- potential anomalies and provide permeability distributions, which is important for effective aquifer recharge and recovery system design, and optimization strategy development.

Performance Assessment Monitoring Plan for the Hanford Site Low-Level Burial Grounds

International Nuclear Information System (INIS)

2006-01-01

The U.S. Department of Energy Order 435.1, Radioactive Waste Management, requires a disposal authorization statement authorizing operation (or continued operation) for low-level waste disposal facilities. In fulfillment of these requirements, a disposal authorization statement was issued on October 25, 1999, authorizing the Hanford Site to transfer, receive, possess, and dispose of low-level radioactive waste at the 200 East Area burial grounds and the 200 West Area burial grounds. One of the conditions is that monitoring plans for the 200 East Area and 200 West Area low-level burial grounds be written and approved by the Richland Operations Office. As a result of a record of decision for the Hanford Site Solid Waste Program and acceptance of the Hanford Site Solid Waste Environmental Impact Statement, the use of the low-level burial ground (LLBG) as a disposal facility for low-level and mixed low-level wastes has been restricted to lined trenches and the Navy reactor-compartment trench only. Hence, as of July 2004, only the two lined trenches in burial ground 218-W-5 (trenches 31 and 34, see Appendix A) and the Navy reactor-compartment trench in burial ground 218 E 12B (trench 94) are allowed to receive waste. When the two lined trenches are filled, the LLBG will cease to operate except for reactor compartment disposal at trench 94. Remaining operational lifetime of the LLBG is dependent on waste volume disposal rates. Existing programs for air sampling and analyses and subsidence monitoring are currently adequate for performance assessment at the LLBG. The waste disposal authorization for the Hanford Site is based (in part) on the post-closure performance assessments for the LLBG. In order to maintain a useful link between operational monitoring (e.g., Resource Conservation and Recovery Act [RCRA], Comprehensive Environmental Response, Compensation, and Liability Act, and State Waste Discharge Permits), constituents, monitoring frequencies, and boundaries require

User's manual and guide to SALT3 and SALT4: two-dimensional computer codes for analysis of test-scale underground excavations for the disposal of radioactive waste in bedded salt deposits

International Nuclear Information System (INIS)

Lindner, E.N.; St John, C.M.; Hart, R.D.

1984-02-01

SALT3 and SALT4 are two-dimensional analytical/displacement-discontinuity codes designed to evaluate temperatures, deformation, and stresses associated with underground disposal of radioactive waste in bedded salt. These codes were developed by the University of Minnesota for the Office of Nuclear Waste Isolation in 1979. The present documentation describes the mathematical equations of the physical system being modeled, the numerical techniques utilized, and the organization of these computer codes. The SALT3 and SALT4 codes can simulate: (a) viscoelastic behavior in pillars adjacent to excavations; (b) transversely isotropic elastic moduli such as those exhibited by bedded or stratified rock; and (c) excavation sequence. Major advantages of these codes are: (a) computational efficiency; (b) the small amount of input data required; and (c) a creep law based on laboratory experimental data for salt. The main disadvantage is that some of the assumptions in the formulation of the codes, i.e., the homogeneous elastic half-space and temperature-independent material properties, render it unsuitable for canister-scale analysis or analysis of lateral deformation of the pillars. The SALT3 and SALT4 codes can be used for parameter sensitivity analyses of two-dimensional, repository-scale, thermomechanical response in bedded salt during the excavation, operational, and post-closure phases. It is especially useful in evaluating alternative patterns and sequences of excavation or waste canister placement. SALT3 is a refinement of an earlier code, SALT, and includes a fully anelastic creep model and thermal stress routine. SALT4 is a later version, and incorporates a revised creep model which is strain-hardening

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

Transport of low-level radioactive soil at deep-ocean disposal site

International Nuclear Information System (INIS)

Abdelrhman, M.A.

1993-01-01

This discussion highlights the impact of treating disposed material as barge loads, instead of as single particles. The specific objectives of this discussion are: to present the effect of initial plume dynamics on water column exposure time; and to qualitatively show the effect of horizontal diffusion of particulates in a water column and bed exposure to particulates. A model for instantaneous release of dredged material from a hopper dredge is adapted to illustrate these effects

Tritium migration from a low-level radioactive-waste disposal site near Chicago, Illinois

Science.gov (United States)

Nicholas, J.R.; Healy, R.W.

1988-01-01

This paper describes the results of a study to determine the geologic and hydrologic factors that control migration of tritium from a closed, low-level radioactive-waste disposal site. The disposal site, which operated from 1943 to mid1949, contains waste generated by research activities at the world's first nuclear reactors. Tritium has migrated horizontally at least 1,300 feet northward in glacial drift and more than 650 feet in the underlying dolomite. Thin, gently sloping sand layers in an otherwise clayey glacial drift are major conduits for ground-water flow and tritium migration in a perched zone beneath the disposal site. Tritium concentrations in the drift beneath the disposal site exceed 100,000 nanocuries per liter. Regional horizontal joints in the dolomite are enlarged by solution and are the major conduits for ground-water flow and tritium migration in the dolomite. A weathered zone at the top of the dolomite also is a pathway for tritium migration. The maximum measured tritium concentration in the dolomite is 29.4 nanocuries per liter. Fluctuations of tritium concentration in the dolomite are the result of dilution by seasonal recharge from the drift.

Impact of Rain Water Infiltration on the Stability of Earth Slopes

Directory of Open Access Journals (Sweden)

Muhammad Farooq Ahmed

2016-12-01

Full Text Available Slope failure occurs very often in natural and man-made slopes which are subjected to frequent changes in ground water level, rapid drawdown, rainfall and earthquakes. The current study discusses the significance of water infiltration, pore water pressure and degree of saturation that affect the stability of earth slopes. Rainwater infiltration not only mechanically reduces the shear strength of a slope material, but also chemically alters the mineral composition of the soil matrix. It results in the alteration of macro structures which in turn decreases the factor of safety. A few case studies are discussed in this paper to quantitatively observe the variation in factor of safety (FOS of various earth slopes by changing the degree of saturation. The results showed that most of the earth slopes get failed or become critical when the degree of saturation approaches to 50 % or more.

Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments. Revision 2

Energy Technology Data Exchange (ETDEWEB)

Cummins, G.D.

1994-06-01

This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste is subject to the TSCA regulations of 40 CFR 761. Interim approval is requested for a period not to exceed 5 years from the date of approval. This request covers only the disposal of small 10 quantities of solid PCB waste contained in decommissioned, defueled submarine reactor compartments (SRC). In addition, the request applies only to disposal 12 of this waste in Trench 94 of the 218-E-12B Burial Ground (Trench 94) in the 13 200 East Area of the US Department of Energy`s (DOE) Hanford Facility. Disposal of this waste will be conducted in accordance with the Compliance 15 Agreement (Appendix H) between the DOE Richland Operations Office (DOE-RL) and 16 the US Environmental Protection Agency (EPA), Region 10. During the 5-year interim approval period, the DOE-RL will submit an application seeking final 18 approval for operation of Trench 94 as a chemical waste landfill, including 19 any necessary waivers, and also will seek a final dangerous waste permit from 20 the Washington State Department of Ecology (Ecology) for disposal of lead 21 shielding contained in the SRCS.

Cost estimate of Olkiluoto disposal facility for spent nuclear fuel

International Nuclear Information System (INIS)

Kukkola, T.; Saanio, T.

2005-03-01

The cost estimate covers the underground rock characterisation facility ONKALO, the investment and the operating costs of the above and underground facilities, the decommissioning of the encapsulation plant and the closure costs of the repository. The above ground facility is a once-investment; a re-investment takes place after 37 years operation. The repository is extended stepwise thus also the investment take place in stages. Annual operating costs are calculated with different operating efficiencies. The total investment costs of the disposal facility are estimated to be 503 M euro (Million Euros), the total operating costs are 1,923 M euro and the decommissioning and the closure costs are 116 M euro totaling 2,542 M euro. The investment costs of the above ground facility are 142 M euro, the operating costs are 1,678 M euro. The repository investment costs are 360 M euro and the operating costs are 245 M euro. The decommissioning costs are 7 M euro and the closure costs are 109 M euro. The costs are calculated by using the price level of December 2003. The cost estimate is based on a plan, where the spent fuel is encapsulated and the disposal canisters are disposed into the bedrock at a depth of about 420 meters in one storey. In the encapsulation process, the fuel assemblies are closed into composite canisters, in which the inner part of the canister is made of nodular cast iron and the outer wall of copper having a thickness of 50 mm. The inner canister is closed gas-tight by a bolted steel lid, and the electron beam welding method is used to close the outer copper lid. The encapsulation plant is independent and located above the deep repository spaces. The disposal canisters are transported to the repository by the lift. The disposal tunnels are constructed and closed in stages according the disposal canisters disposal. The operating time of the Loviisa nuclear power plant units is assumed to be 50 years and the operating time of the Olkiluoto nuclear power

Assessing potential impacts of a wastewater rapid infiltration basin system on groundwater quality: a delaware case study.

Science.gov (United States)

Andres, A S; Sims, J Thomas

2013-01-01

Rapid infiltration basin systems (RIBS) are receiving increased interest for domestic wastewater disposal in rural areas. They rely on natural treatment processes to filter pollutants and use extremely high effluent loading rates, much greater than natural precipitation, applied to a small geographic area instead of disposal to surface water. Concerns exist today that adopting RIBS in areas with shallow groundwater and sandy soils may increase ground and surface water pollution. We conducted a field study of RIBS effects on N and P concentrations in soils and groundwater at Cape Henlopen State Park, Delaware, where a RIBS designed and operated following USEPA guidance has been used for >25 yr. Site and wastewater characteristics (water table of 8 m, Fe- and Al-oxide coatings on soils, organic-rich effluent) were favorable for denitrification and P sorption; however, we found high P saturation, reduced soil P sorption capacity, and significant total P accumulation at depths >1.5 m, factors that could lead to dissolved P leaching. Very low soil inorganic N levels suggest that wastewater N was converted rapidly to NO-N and leached from the RIBS. Extensive groundwater monitoring supported these concerns and showed rapid offsite transport of N and P at concentrations similar to the effluent. Results suggest that high hydraulic loads and preferential flow led to flow velocities that were too large, and contact times between effluent and soils that were too short, for effective N and P attenuation processes. These findings indicate the need for better site characterization and facility designs to reduce and monitor contaminant loss from RIBS in similar settings. Copyright © by the American Society of Agronomy, Crop Science Society of America, and Soil Science Society of America, Inc.

Disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Glasby, G.P.

1977-01-01

Although controversy surrounding the possible introduction of nuclear power into New Zealand has raised many points including radiation hazards, reactor safety, capital costs, sources of uranium and earthquake risks on the one hand versus energy conservation and alternative sources of energy on the other, one problem remains paramount and is of global significance - the storage and dumping of the high-level radioactive wastes of the reactor core. The generation of abundant supplies of energy now in return for the storage of these long-lived highly radioactive wastes has been dubbed the so-called Faustian bargain. This article discusses the growth of the nuclear industry and its implications to high-level waste disposal particularly in the deep-sea bed. (auth.)

Monitoring of surface deformation and microseismicity applied to radioactive waste disposal through hydraulic fracturing at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Stow, S.H.; Haase, C.S.; Switek, J.; Holzhausen, G.R.; Majer, E.; Applied Geomechanics, Inc., Santa Cruz, CA; Lawrence Berkeley Lab., CA)

1985-01-01

Low-level liquid nuclear wastes are disposed of at Oak Ridge National Laboratory by the hydrofracture process. Wastes are mixed with cement and other additives to form a slurry that is injected into shale of low permeability at 300 m depth. The slurry spreads radially along bedding plane fractures before setting as a grout. Different methods for monitoring the location and behavior of the fractures have been investigated. Radioactive grout sheets can be located by gamma-ray logging of cased observation wells. Two other methods are based on the fact that the ground surface is deformed by the injection. The first entails surface leveling of a series of benchmarks; uplift up to 2.5 cm occurs. The second method involves use of tiltmeters that are sensitive and measure ground deformation in real time during an injection. Both methods show subsidence during the weeks following an injection. Interpretive models for the tiltmeter data are based on the elastic response of isotropic and anisotropic media to the inflation of a fluid-filled fracture. A fourth monitoring method is based on microseismicity. Geophone arrays were used to characterize the fracture process and to provide initial assessment of the feasibility of using seismic measurements to map the fractures as they form. An evaluation of each method is presented

Cleanup Verification Package for the 618-3 Burial Ground

International Nuclear Information System (INIS)

Appel, M.J.

2006-01-01

This cleanup verification package documents completion of remedial action for the 618-3 Solid Waste Burial Ground, also referred to as Burial Ground Number 3 and the Dry Waste Burial Ground Number 3. During its period of operation, the 618-3 site was used to dispose of uranium-contaminated construction debris from the 311 Building and construction/demolition debris from remodeling of the 313, 303-J and 303-K Buildings

Disposal method of radioactive wastes

International Nuclear Information System (INIS)

Uetake, Naoto; Fukazawa, Tetsuo.

1986-01-01

Purpose: To improve the safety of underground disposal of radioactive wastes for a long period of time by surrounding the periphery of the radioactive wastes with materials that can inhibit the migration of radioactive nuclides and are physically and chemically stable. Method: Hardening products prepared from a water-hardenable calcium silicate compound and an aqueous solution of alkali silicate have compression strength as comparable with that of concretes, high water tightness and adsorbing property to radioactive isotopes such as cobalt similar to that of concretes and they also show adsorption to cesium which is not adsorbed to concretes. Further, the kneaded slurry thereof is excellent in the workability and can be poured even into narrow gaps. Accordingly, by alternately charging granular radioactive wastes and this slurry before hardening into the ground, the radioactive wastes can be put to underground disposal stably with simple procedures. (Kamimura, M.)

Shallow disposal of radioactive waste

International Nuclear Information System (INIS)

1985-02-01

A review and evaluation of computer codes capable of simulating the various processes that are instrumental in determining the dose rate to individuals resulting from the shallow disposal of radioactive waste was conducted. Possible pathways of contamination, as well as the mechanisms controlling radionuclide movement along these pathways have been identified. Potential transport pathways include the unsaturated and saturated ground water systems, surface water bodies, atmospheric transport and movement (and accumulation) in the food chain. Contributions to dose may occur as a result of ingestion of contaminated water and food, inhalation of contaminated air and immersion in contaminated air/water. Specific recommendations were developed regarding the selection and modification of a model to meet the needs associated with the prediction of dose rates to individuals as a consequence of shallow radioactive waste disposal. Specific technical requirements with regards to risk, sensitivity and uncertainty analyses have been addressed

Understanding and modeling retention of mammalian cells in fluidized bed centrifuges.

Science.gov (United States)

Kelly, William; Rubin, Jonathan; Scully, Jennifer; Kamaraju, Hari; Wnukowski, Piotr; Bhatia, Ravinder

2016-11-01

Within the last decade, fully disposable centrifuge technologies, fluidized-bed centrifuges (FBC), have been introduced to the biologics industry. The FBC has found a niche in cell therapy where it is used to collect, concentrate, and then wash mammalian cell product while continuously discarding centrate. The goal of this research was to determine optimum FBC conditions for recovery of live cells, and to develop a mathematical model that can assist with process scaleup. Cell losses can occur during bed formation via flow channels within the bed. Experimental results with the kSep400 centrifuge indicate that, for a given volume processed: the bed height (a bed compactness indicator) is affected by RPM and flowrate, and dead cells are selectively removed during operation. To explain these results, two modeling approaches were used: (i) equating the centrifugal and inertial forces on the cells (i.e., a force balance model or FBM) and (ii) a two-phase computational fluid dynamics (CFD) model to predict liquid flow patterns and cell retention in the bowl. Both models predicted bed height vs. time reasonably well, though the CFD model proved more accurate. The flow patterns predicted by CFD indicate a Coriolis-driven flow that enhances uniformity of cells in the bed and may lead to cell losses in the outflow over time. The CFD-predicted loss of viable cells and selective removal of the dead cells generally agreed with experimental trends, but did over-predict dead cell loss by up to 3-fold for some of the conditions. © 2016 American Institute of Chemical Engineers Biotechnol. Prog., 32:1520-1530, 2016. © 2016 American Institute of Chemical Engineers.

The NASA Bed Rest Project

Science.gov (United States)

Rhodes, Bradley; Meck, Janice

2005-01-01

NASA s National Vision for Space Exploration includes human travel beyond low earth orbit and the ultimate safe return of the crews. Crucial to fulfilling the vision is the successful and timely development of countermeasures for the adverse physiological effects on human systems caused by long term exposure to the microgravity environment. Limited access to in-flight resources for the foreseeable future increases NASA s reliance on ground-based analogs to simulate these effects of microgravity. The primary analog for human based research will be head-down bed rest. By this approach NASA will be able to evaluate countermeasures in large sample sizes, perform preliminary evaluations of proposed in-flight protocols and assess the utility of individual or combined strategies before flight resources are requested. In response to this critical need, NASA has created the Bed Rest Project at the Johnson Space Center. The Project establishes the infrastructure and processes to provide a long term capability for standardized domestic bed rest studies and countermeasure development. The Bed Rest Project design takes a comprehensive, interdisciplinary, integrated approach that reduces the resource overhead of one investigator for one campaign. In addition to integrating studies operationally relevant for exploration, the Project addresses other new Vision objectives, namely: 1) interagency cooperation with the NIH allows for Clinical Research Center (CRC) facility sharing to the benefit of both agencies, 2) collaboration with our International Partners expands countermeasure development opportunities for foreign and domestic investigators as well as promotes consistency in approach and results, 3) to the greatest degree possible, the Project also advances research by clinicians and academia alike to encourage return to earth benefits. This paper will describe the Project s top level goals, organization and relationship to other Exploration Vision Projects, implementation

Ground-water hydrology and glacial geology of the Kalamazoo area, Michigan

Science.gov (United States)

Deutsch, Morris; Vanlier, K.E.; Giroux, P.R.

1960-01-01

The Kalamazoo report area includes about 150 square miles of Kalamazoo County, Mich. The area is principally one of industry and commerce, although agriculture also is of considerable importance. It has a moderate and humid climate and lies within the Lake Michigan “snow belt”. Precipitation averages about 35 inches per year. Snowfall averages about 55 inches. The surface features of the area were formed during and since the glacial epoch and are classified as outwash plain, morainal highlands, and glaciated channels or drainageways. The area is formed largely on the remnants of an extensive outwash plain, which is breached by the Kalamazoo River in the northeastern part and is dissected elsewhere by several small tributaries to the river. Most of the land drained by these tributaries lies within the report area. A small portion of the southern part drains to the St. Joseph River. The Coldwater shale, which underlies the glacial deposits throughout the area, and the deeper bedrock formations are not tapped for water by wells and they have little or no potential for future development. Deposits of glacial drift, which are the source of water to all the wells in the area, have considerable potential for future development. These deposits range in thickness from about 40 feet along the Kalamazoo River to 350 feet where valleys were eroded in the bedrock surface. Permeable outwash and channel deposits are the sources of water for wells of large capacity. The moraines are formed dominantly by till of lower permeability which generally yields small supplies of water, but included sand and gravel beds of higher permeability yield larger supplies locally. The aquifers of the Kalamazoo area are recharged by infiltration of rainfall and snowmelt and by infiltration of surface waters induced by pumping of wells near the surface sources. Water pumped from most of the municipal well fields is replenished in part by such induced infiltration. Many of the industrial wells

Robowell: An automated process for monitoring ground water quality using established sampling protocols

Science.gov (United States)

Granato, G.E.; Smith, K.P.

1999-01-01

Robowell is an automated process for monitoring selected ground water quality properties and constituents by pumping a well or multilevel sampler. Robowell was developed and tested to provide a cost-effective monitoring system that meets protocols expected for manual sampling. The process uses commercially available electronics, instrumentation, and hardware, so it can be configured to monitor ground water quality using the equipment, purge protocol, and monitoring well design most appropriate for the monitoring site and the contaminants of interest. A Robowell prototype was installed on a sewage treatment plant infiltration bed that overlies a well-studied unconfined sand and gravel aquifer at the Massachusetts Military Reservation, Cape Cod, Massachusetts, during a time when two distinct plumes of constituents were released. The prototype was operated from May 10 to November 13, 1996, and quality-assurance/quality-control measurements demonstrated that the data obtained by the automated method was equivalent to data obtained by manual sampling methods using the same sampling protocols. Water level, specific conductance, pH, water temperature, dissolved oxygen, and dissolved ammonium were monitored by the prototype as the wells were purged according to U.S Geological Survey (USGS) ground water sampling protocols. Remote access to the data record, via phone modem communications, indicated the arrival of each plume over a few days and the subsequent geochemical reactions over the following weeks. Real-time availability of the monitoring record provided the information needed to initiate manual sampling efforts in response to changes in measured ground water quality, which proved the method and characterized the screened portion of the plume in detail through time. The methods and the case study described are presented to document the process for future use.

Hydro-geochemical and isotopic composition of ground water in Helwan area

Directory of Open Access Journals (Sweden)

W.M. Salem

2015-12-01

The environmental stable isotopes oxygen and hydrogen (18O, and deuterium were studied and used to identify the sources of recharge. The studied ground waters are enriched in D and 18O and the isotopic features suggest that most of the ground water recharged indirectly after evaporation prior to infiltration from irrigation return water as well as the contribution from Nile water.

Modified design in new construction prevents infiltration of soil gas that carries radon

International Nuclear Information System (INIS)

Ericson, S.O.; Schmied, H.

1987-01-01

Dwellings located on permeable soil with strong exhalation of radon often get a contribution to indoor radon from infiltrating soil gas carrying radon from the ground into the building. 100 dwellings have been built on radon dangerous land with different modifications in design and construction in order to prevent infiltration of radon. Tight construction, ventilated crawl space, ventilation/depressurization of the capillary breaking layer (crushed stone), and mechanical ventilation with heat recovery by air to air heat exchangers or heat pumps have been tested. Added building costs and measured concentration of radon after construction and 3-5 years later are reported. It is concluded that it is possible to build radon protective and radon safe dwellings on any land. The added costs have ranged from zero to 4% of total building costs

The offshore disposal of radioactive waste by drilled emplacement: A feasibility study

International Nuclear Information System (INIS)

Bury, M.R.C.

1985-01-01

This book is a report, based on a study by Taylor Woodrow Construction Limited, on the overall feasibility of the disposal of high-level radioactive waste in boreholes drilled deep into the ocean bed. The work comprises an engineering appraisal of the disposal process with a view to establishing technical and operational feasibility and providing overall cost information to enable an economic assessment to be made. Contents: Summary report; Reference criteria; Drilling operation; Transfer of radioactive waste, personnel and other supplies; Handling of radioactive waste on board; Lowering strings of canisters; Emplacement and backfilling of canisters; Preliminary design of marine platform; Retrieval of flasks or canisters lost or misplaced; Variations to the features of the lowering system; Logistics of the operation; Construction cost estimate; Operational costs; Appendix

Prediction and assessment of environmental impacts of Guangdong low-and-intermediate level radioactive waste disposal site

International Nuclear Information System (INIS)

Huang Yawen

1996-01-01

Guangdong Low-and Intermediate Level Radioactive Waste Disposal Site is located 5-7 km northeast to the Daya Bay Nuclear Power Plant. It is in a hilly area with strongly weathered light metamorphic quartz siltstone. The groundwater is 2 m below the repository bottom. The disposal unit is a U-shape concrete structure with drainage and water collecting system at the bottom. The designed cover is a multi-layer structure with functions of preventing from water infiltration, animal and plant intrusion. It is assumed that the engineered barriers would be effective to avoid waste immersion by surface water and groundwater within the first 100 years after closure. After 100 years, the engineered barriers would fail gradually. Radionuclides may release from the disposal unite. Some will enter the nearby stream, some will flow into the Daya Bay, and some will transport to groundwater through geologic media

Feasibility study - Lowered bed temperature in Fluidised Bed boilers for waste; Foerstudie - Saenkt baeddtemperatur i FB-pannor foer avfallsfoerbraenning

Energy Technology Data Exchange (ETDEWEB)

Niklasson, Fredrik

2009-01-15

Waste incineration generally serves two purposes; 1) dispose of waste and 2) generation of heat and power. In the process of power production from waste fuels, the steam temperatures in super heaters are generally limited by the severe fouling and corrosion that occurs at elevated material temperatures, caused by high concentrations of alkali metals and chloride in the flue gas and fly ash. The overall aim of a continuation of present project is to determine if a reduced temperature of the bed zone in a fluidized bed waste incinerator reduces the amount of alkali chlorides in the flue gas. If so, a reduced bed temperature might enable increased steam temperature in super heaters, or, at unchanged steam temperature, improve the lifespan of the super heaters. The results from the project are of interest for plant owners wishing to improve performance of existing plants. The results may also be used to modify the design of future plants by boiler manufacturers. The aim of present pre-study was to determine how far the bed temperature can be reduced in a waste fired fluidized bed boiler in Boraas while maintaining a stable operation with sufficient combustion temperature in the freeboard to fulfil the directives of waste incineration. A continuation of the project will be based on the results from present study. The work is based on experiments at the test boiler. During the present study, no other measurements were performed apart from some sampling of bed material and ashes at different modes of operation. The experiments show that it is possible to alter the air and recycled flue gas in such a manner that the bed temperature is reduced from about 870 deg C to 700 deg C at 100% load and normal fuel mixture, while fulfilling the directive of 850 deg C at 2 seconds. Within normal variations of the fuel properties, however, the bed temperature increases to somewhat above 700 deg C if the fuel turns dry, while it falls below 650 deg C when the fuel turns wet. With

Waste Water Treatment-Bed of Coal Fly Ash for Dyes and Pigments Industry

Directory of Open Access Journals (Sweden)

Syed Farman Ali Shah

2015-12-01

Full Text Available The highly porous power plant waste ashes have been utilized to treat toxic effluent of a dyes manufacturing plant. An attempt has been made for the first time in Pakistan, to generate an effective and economically sound treatment facility for the toxic effluent of a dyes manufacturing plant. This is an indigenous bed which could replace expensive treatment facilities, such as reverse osmosis (RO, granulated activated carbon (GAC bed, etc. The treatment efficiency was improved by coupling coagulants with fly ash adsorbent bed. The ash was collected from coal fired boilers of power plant at Lakhra Power Generation Company, Jamshoro, Pakistan. The use of this ash resolved the disposal and environmental issues by treating wastewater of chemical, dyes and pigment industry. The treatment bed comprised of briquettes of coal fly ash coupled with commercial coagulant ferrous sulfate-lime reduced COD, color, turbidity and TSS of effluent remarkably. An adsorption capacity and chemical behavior of fly ash bed was also studied. In coagulation treatment, coagulant FeSO4-lime influenced reduction of COD, color, turbidity and TSS by 32%, 48%, 50% and 51%, respectively. The CFAB coupled with coagulant, resulted an excessive removal of color, TSS, COD, and turbidity by 88%, 92%, 67% and89%, respectively.

Waste Water Treatment-Bed of Coal Fly Ash for Dyes and Pigments Industry

International Nuclear Information System (INIS)

Shah, S.F.A.; Aftab, A.; Soomro, N.; Nawaz, M.S.; Vafai, K.

2015-01-01

The highly porous power plant waste ashes have been utilized to treat toxic effluent of a dyes manufacturing plant. An attempt has been made for the first time in Pakistan, to generate an effective and economically sound treatment facility for the toxic effluent of a dyes manufacturing plant. This is an indigenous bed which could replace expensive treatment facilities, such as reverse osmosis (RO), granulated activated carbon (GAC) bed, etc. The treatment efficiency was improved by coupling coagulants with fly ash adsorbent bed. The ash was collected from coal fired boilers of power plant at Lakhra Power Generation Company, Jamshoro, Pakistan. The use of this ash resolved the disposal and environmental issues by treating wastewater of chemical, dyes and pigment industry. The treatment bed comprised of briquettes of coal fly ash coupled with commercial coagulant ferrous sulfate-lime reduced COD, color, turbidity and TSS of effluent remarkably. An adsorption capacity and chemical behavior of fly ash bed was also studied. In coagulation treatment, coagulant FeSO/sun 4/-lime influenced reduction of COD, color, turbidity and TSS by 32 percentage, 48 percentage, 50 percentage and 51 percentage, respectively. The CFAB coupled with coagulant, resulted an excessive removal of color, TSS, COD, and turbidity by 88 percentage, 92 percentage, 67 percentage and 89 percentage, respectively. (author)

Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

Energy Technology Data Exchange (ETDEWEB)

Collard, L.B.

2000-09-26

This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds.

Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

International Nuclear Information System (INIS)

Collard, L.B.

2000-01-01

This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds

UMTRA project disposal cell cover biointrusion sensitivity assessment, Revision 1

International Nuclear Information System (INIS)

1995-10-01

This study provides an analysis of potential changes that may take place in a Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell cover system as a result of plant biointrusion. Potential changes are evaluated by performing a sensitivity analysis of the relative impact of root penetrations on radon flux out of the cell cover and/or water infiltration into the cell cover. Data used in this analysis consist of existing information on vegetation growth on selected cell cover systems and information available from published studies and/or other available project research. Consistent with the scope of this paper, no new site-specific data were collected from UMTRA Project sites. Further, this paper does not focus on the issue of plant transport of radon gas or other contaminants out of the disposal cell cover though it is acknowledged that such transport has the potential to be a significant pathway for contaminants to reach the environment during portions of the design life of a disposal cell where plant growth occurs. Rather, this study was performed to evaluate the effects of physical penetration and soil drying caused by plant roots that have and are expected to continue to grow in UMTRA Project disposal cell covers. An understanding of the biological and related physical processes that take place within the cover systems of the UMTRA Project disposal cells helps the U.S. Department of Energy (DOE) determine if the presence of a plant community on these cells is detrimental, beneficial, or of mixed value in terms of the cover system's designed function. Results of this investigation provide information relevant to the formulation of a vegetation control policy

Ground-water monitoring under RCRA

International Nuclear Information System (INIS)

Coalgate, J.

1993-11-01

In developing a regulatory strategy for the disposal of hazardous waste under the Resource Conservation and Recovery Act (RCRA), protection of ground-water resources was the primary goal of the Environmental Protection Agency (EPA). EPA's ground-water protection strategy seeks to minimize the potential for hazardous wastes and hazardous constituents in waste placed in land disposel units to migrate into the environment. This is achieved through liquids management (limiting the placement of liquid wastes in or on the land, requiring the use of liners beneath waste, installing leachate collection systems and run-on and run-off controls, and covering wastes at closure). Ground-water monitoring serves to detect any failure in EPA's liquids management strategy so that ground-water contamination can be detected and addressed as soon as possible

Special Analysis: Revision of Saltstone Vault 4 Disposal Limits (U)

Energy Technology Data Exchange (ETDEWEB)

Cook, J

2005-05-26

New disposal limits have been computed for Vault 4 of the Saltstone Disposal Facility based on several revisions to the models in the existing Performance Assessment and the Special Analysis issued in 2002. The most important changes are the use of a more rigorous groundwater flow and transport model, and consideration of radon emanation. Other revisions include refinement of the aquifer mesh to more accurately model the footprint of the vault, a new plutonium chemistry model accounting for the different transport properties of oxidation states III/IV and V/VI, use of variable infiltration rates to simulate degradation of the closure system, explicit calculation of gaseous releases and consideration of the effects of settlement and seismic activity on the vault structure. The disposal limits have been compared with the projected total inventory expected to be disposed in Vault 4. The resulting sum-of-fractions of the 1000-year disposal limits is 0.2, which indicates that the performance objectives and requirements of DOE 435.1 will not be exceeded. This SA has not altered the conceptual model (i.e., migration of radionuclides from the Saltstone waste form and Vault 4 to the environment via the processes of diffusion and advection) of the Saltstone PA (MMES 1992) nor has it altered the conclusions of the PA (i.e., disposal of the proposed waste in the SDF will meet DOE performance measures). Thus a PA revision is not required and this SA serves to update the disposal limits for Vault 4. In addition, projected doses have been calculated for comparison with the performance objectives laid out in 10 CFR 61. These doses are 0.05 mrem/year to a member of the public and 21.5 mrem/year to an inadvertent intruder in the resident scenario over a 10,000-year time-frame, which demonstrates that the 10 CFR 61 performance objectives will not be exceeded. This SA supplements the Saltstone PA and supersedes the two previous SAs (Cook et al. 2002; Cook and Kaplan 2003).

Performance monitoring of an improved disposal trench in a humid environment in a fractured geology

International Nuclear Information System (INIS)

Mills, D.; Razor, J.

1988-01-01

An engineering evaluation of an improved disposal trench at the Maxey Flats Waste Disposal Site is being conducted in order to demonstrate the feasibility of a burial trench suitable for use at a site in a humid environment and underlain by complex and fractured geologic media. This demonstration is one of several proposed final site stabilization alternatives which will have to be evaluated prior to final site closure. Due to requirements in the Central Midwest Compact Commission, no waste generated as a result of the site closure may be disposed in the Commission's disposal site. Hence, the waste will be disposed on-site. The demonstration trench was constructed and filled with waste during the fall of 1985 with final trench capping being completed in July 1986. Since that time the trench has been evaluated utilizing trench settlement monument elevations, leachate production measurements, leachate radionuclide analysis, chemical tracer analysis and trench water balance. Measurements performed to date indicated that the trench lower infiltration barrier has a permeability of about 1E-7 cm/sec. Water balance measurements indicated that less than one percent of the total rainfall crossed the trench capillary barrier. No settlement of the trench cap has been observed. No liquid has appeared in the leachate collection and monitoring sumps

[Prediction model of health workforce and beds in county hospitals of Hunan by multiple linear regression].

Science.gov (United States)

Ling, Ru; Liu, Jiawang

2011-12-01

To construct prediction model for health workforce and hospital beds in county hospitals of Hunan by multiple linear regression. We surveyed 16 counties in Hunan with stratified random sampling according to uniform questionnaires,and multiple linear regression analysis with 20 quotas selected by literature view was done. Independent variables in the multiple linear regression model on medical personnels in county hospitals included the counties' urban residents' income, crude death rate, medical beds, business occupancy, professional equipment value, the number of devices valued above 10 000 yuan, fixed assets, long-term debt, medical income, medical expenses, outpatient and emergency visits, hospital visits, actual available bed days, and utilization rate of hospital beds. Independent variables in the multiple linear regression model on county hospital beds included the the population of aged 65 and above in the counties, disposable income of urban residents, medical personnel of medical institutions in county area, business occupancy, the total value of professional equipment, fixed assets, long-term debt, medical income, medical expenses, outpatient and emergency visits, hospital visits, actual available bed days, utilization rate of hospital beds, and length of hospitalization. The prediction model shows good explanatory and fitting, and may be used for short- and mid-term forecasting.

Cleanup Verification Package for the 118-F-2 Burial Ground

International Nuclear Information System (INIS)

Capron, J.M.; Anselm, K.A.

2008-01-01

This cleanup verification package documents completion of remedial action, sampling activities, and compliance with cleanup criteria for the 118-F-2 Burial Ground. This burial ground, formerly called Solid Waste Burial Ground No. 1, was the original solid waste disposal site for the 100-F Area. Eight trenches contained miscellaneous solid waste from the 105-F Reactor and one trench contained solid waste from the biology facilities

Effect of seawater on consistency, infiltration rate and swelling characteristics of montmorillonite clay

Directory of Open Access Journals (Sweden)

Mohie Eldin Elmashad

2016-08-01

Full Text Available This paper presents the results of an experimental investigation performed to quantify the effect of mixing clayey soils with saltwater on consistency and swelling characteristics of clays. Massive natural clay deposits and compacted clay backfills either exist or are used in certain important and sensitive applications such as dams, liners, barriers and buffers in waste disposal facilities. In many cases, the clay deposits in these applications are subjected to saltwater. However, in standard laboratory classification tests, distilled or potable water are usually used in mixing test samples. This may lead to faulty interpretation of the actual in-situ consistency and volume change behaviors. In this research, an attempt is made to quantify the changes in consistency and swelling of clay soils from various locations around the Nile valley and possessing a wide range of consistency, when mixed with natural seawater with different salt concentrations. The results showed that the increase of the salt concentration of the mixing water may result in major decrease in the liquid limit and swelling characteristics of high plasticity montmorillonite clays. The reduction in the swelling of the clay soils is also proportional to the rate of saltwater infiltration. In an attempt to correlate the swelling of clays to the rate of water infiltration, a new simplified laboratory apparatus is proposed where swelling and infiltration are measured in one simple test “the swelling infiltrometer”.

Technical specifications for waste packages conditioned in a durable confining shell, with an hydraulic binder basis, intended to a ground disposal site

International Nuclear Information System (INIS)

1995-06-01

The aim of this document is to precise the general and particular conditions for the acceptance on a ground disposal site of a low- and middle-level radioactive waste package conditioned in a durable confining shell. This specification concerns the wastes that contain beta and gamma decay radionuclides and/or long life alpha decay radionuclides in higher quantities than accepted for the protective coatings. Physico-chemical and mechanical specifications are given for the wastes, the fixing material, the confining shell and the container. Accepted limits for degassing and dose rates, surface contamination, dimensions and weight are given. The agreement is delivered by the ANDRA after the package has satisfied the different mechanical, chemical, fire, moisture and radiation resistance tests. (J.S.). 1 fig., 3 tabs., 1 glossary

Water infiltration into exposed fractured rock surfaces

International Nuclear Information System (INIS)

Rasmussen, T.C.; Evans, D.D.

1993-01-01

Fractured rock media are present at many existing and potential waste disposal sites, yet characterization data and physical relationships are not well developed for such media. This study focused on water infiltration characteristics of an exposed fractured rock as an approach for defining the upper boundary condition for unsaturated-zone water percolation and contaminant transport modeling. Two adjacent watersheds of 0.24 and 1.73 ha with slopes up to 45% were instrumented for measuring rainfall and runoff. Fracture density was measured from readily observable fracture traces on the surface. Three methods were employed to evaluate the rainfall-runoff relationship. The first method used the annual totals and indicated that only 22.5% of rainfall occurred as runoff for the 1990-1991 water year, which demonstrates a high water intake rate by the exposed fracture system. The second method employed total rainfall and runoff for individual storms in conjunction with the commonly used USDA Soil Conservation Service curve number method developed for wide ranges of soils and vegetation. Curve numbers between 75 and 85 were observed for summer and winter storms with dry antecedent runoff conditions, while values exceeded 90 for wet conditions. The third method used a mass-balance approach for four major storms, which indicated that water intake rates ranged from 2.0 to 7.3 mm h -1 , yielding fracture intake velocities ranging from 122 to 293 m h -1 . The three analyses show the complexity of the infiltration process for fractured rock. However, they contribute to a better understanding of the upper boundary condition for predicting contaminant transport through an unsaturated fractured rock medium. 17 refs., 4 figs., 1 tab

Conceptual design of shallow ground repository (SGR)

International Nuclear Information System (INIS)

Roehl, J.L.; Franzen, H.R.

1986-01-01

A conceptual design to guide the development of the preliminary and final designs of a shallow ground waste disposal site for low and intermediate level radioactive wastes, complying with the Brazilian necessities, interpreted by Brazilian CNEN, is discussed. The general and specific criteria for the design of such installations, considering the reposing period, the isolation of personnel and environment, the operational activities, the characteristics of the site and of the subsoil and the set of necessary installations and services, are presented. An aboveground landfill, with concrete monoliths and concrete packages arranged in stacks disposed on an impermeable soil layer, is proposed. The disposed elements are covered by another impermeable soil stratum. (Author) [pt

Evaluating the Infiltration Performance of Eight Dutch Permeable Pavements Using a New Full-Scale Infiltration Testing Method

Directory of Open Access Journals (Sweden)

Floris Boogaard

2014-07-01

Full Text Available Permeable pavements are a type of sustainable urban drainage system (SUDS technique that are used around the world to infiltrate and treat urban stormwater runoff and to minimize runoff volumes. Urban stormwater runoff contains significant concentrations of suspended sediments that can cause clogging and reduce the infiltration capacity and effectiveness of permeable pavements. It is important for stormwater managers to be able to determine when the level of clogging has reached an unacceptable level, so that they can schedule maintenance or replacement activities as required. Newly-installed permeable pavements in the Netherlands must demonstrate a minimum infiltration capacity of 194 mm/h (540 l/s/ha. Other commonly used permeable pavement guidelines in the Netherlands recommend that maintenance is undertaken on permeable pavements when the infiltration falls below 0.50 m/d (20.8 mm/h. This study used a newly-developed, full-scale infiltration test procedure to evaluate the infiltration performance of eight permeable pavements in five municipalities that had been in service for over seven years in the Netherlands. The determined infiltration capacities vary between 29 and 342 mm/h. Two of the eight pavements show an infiltration capacity higher than 194 mm/h, and all infiltration capacities are higher than 20.8 mm/h. According to the guidelines, this suggests that none of the pavements tested in this study would require immediate maintenance.

Heat generation and heating limits for the IRUS LLRW disposal facility

International Nuclear Information System (INIS)

Donders, R.E.; Caron, F.

1995-10-01

Heat generation from radioactive decay and chemical degradation must be considered when implementing low-level radioactive waste (LLRW) disposal. This is particularly important when considering the management of spent radioisotope sources. Heating considerations and temperature calculations for the proposed IRUS (Intrusion Resistant Underground Structure) near-surface disposal facility are presented. Heat transfer calculations were performed using a finite element code with realistic but somewhat conservative heat transfer parameters and environmental boundary conditions. The softening-temperature of the bitumen waste-form (38 deg C) was found to be the factor that limits the heat generation rate in the facility. This limits the IRUS heat rate, assuming a uniform source term, to 0.34 W/m 3 . If a reduced general heat-limit is considered, then some higher-heat packages can be accepted with restrictions placed on their location within the facility. For most LLRW, heat generation from radioactive decay and degradation are a small fraction of the IRUS heating limits. However, heating restrictions will impact on the disposal of higher-activity radioactive sources. High activity 60 Co sources will require decay-storage periods of about 70 years, and some 137 Cs will need to bed disposed of in facilities designed for higher-heat waste. (author). 21 refs., 8 tabs., 2 figs

Environmental monitoring of subsurface low-level waste disposal facilities at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Ashwood, T.L.; Hicks, D.S.

1992-01-01

Oak Ridge National Laboratory (ORNL) generates low-level waste (LLW) as part of its research and isotope production activities. This waste is managed in accordance with US Department of Energy (DOE) Order 5820.2A. Solid LLW management includes disposal in above-ground, tumulus-type facilities as well as in various types of subsurface facilities. Since 1986, subsurface disposal has been conducted using various designs employing greater-confinement-disposal (GCD) techniques. The purpose of this paper is to present monitoring results that document the short-term performance of these GCD facilities

A geohydrological appraisal of the Vaalputs radioactive waste disposal facility in Namaqualand, South Africa

International Nuclear Information System (INIS)

Levin, M.

1988-10-01

The Vaalputs National Radioactive Waste Disposal Facility is located on the Bushmanland Plateau. The disposal site is situated close to the junction of three river basins. All the parameters neccessary were obtained, and methodology developed, to monitor the moisture content of the clay layers underlying the disposal site. Environmental isotope studies established the percolation only reached 3,5m in depth during the past 50 years. The depth was confirmed by neutron meter measurements. The depth to the piezometric surface below the site is, on average, 55m. Ground water is confined to both vertical and horizontal fractures and weathered joints. The high transmissivity of water-bearing structures below the site and the flat piezometric surface are seen as advantageous. In the event of a serious leak and radionuclides reaching the ground water, sustained pumping may lower the piezometric surface creating a basin effect and preventing contamination from reaching private boreholes. Regional hydrogeochemical studies have confirmed that regional flow away from the disposal site toward the Koa drainage is slow and nearly stagnant. The geochemical environment is favourable for attenuating any radionuclide leakage. 1 map, 93 figs., 47 tabs., 158 refs

Hydrogeological characterisation using cross-borehole ground penetration radar and electrical resistivity tomography

DEFF Research Database (Denmark)

Zibar, Majken Caroline Looms

2007-01-01

was characterized by ~30 m thick unsaturated zone consisting mainly of sands of varying coarseness. Following an instrumentation of 16 boreholes two geophysical methods (cross-borehole ground penetrating radar and electrical resistivity tomography) were applied during natural precipitation and forced infiltration...... properties of the subsurface. On the other hand, volumetric moisture content variations of up to 5% were observed during a 20-day long forced infiltration experiment. The cross-borehole electrical resistance tomography and ground penetrating radar data collected during this experiment were subsequently....... The methods provided estimates of soil moisture content and electrical resistivity variations among 12 m deep boreholes located 5 – 7 m apart. The moisture content change following natural precipitation was observed to be practically negligible, providing minimal information to constrain the dynamic...

Energy recovery from sewage sludge by means of fluidised bed gasification

International Nuclear Information System (INIS)

Gross, Bodo; Eder, Christian; Grziwa, Peter; Horst, Juri; Kimmerle, Klaus

2008-01-01

Because of its potential harmful impact on the environment, disposal of sewage sludge is becoming a major problem all over the world. Today the available disposal measures are at the crossroads. One alternative would be to continue its usage as fertiliser or to abandon it. Due to the discussions about soil contamination caused by sewage sludge, some countries have already prohibited its application in agriculture. In these countries, thermal treatment is now presenting the most common alternative. This report describes two suitable methods to directly convert sewage sludge into useful energy on-site at the wastewater treatment plant. Both processes consist mainly of four devices: dewatering and drying of the sewage sludge, gasification by means of fluidised bed technology (followed by a gas cleaning step) and production of useful energy via CHP units as the final step. The process described first (ETVS-Process) is using a high pressure technique for the initial dewatering and a fluidised bed technology utilising waste heat from the overall process for drying. In the second process (NTVS-Process) in addition to the waste heat, solar radiation is utilised. The subsequent measures - gasification, gas cleaning and electric and thermal power generation - are identical in both processes. The ETVS-Process and the NTVS-Process are self-sustaining in terms of energy use; actually a surplus of heat and electricity is generated in both processes

A reconsideration on deep sea bed disposal of high level radiological wastes. A post-Fukushima reflection on sustainable nuclear energy in Japan

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu

2013-01-01

The ultimate disposal of high-level radioactive waste (HLW) is a common issue among all nuclear developing countries. However, this becomes especially a hard issue for sustainable nuclear energy in Japan after Fukushima Daiichi accident. In this paper, the difficulty of realizing underground HLW disposal in Japanese islands is first discussed from socio-political aspects. Then, revival of old idea of deep seabed disposal of HLW in Pacific Ocean is proposed as an alternative way of HLW disposal. Although this old idea had been abandoned in the past for the reason that it would violate London Convention which prohibits dumping radioactive wastes in public sea, the author will stress the merit of seabed disposal of HLW deep in Pacific Ocean not only from the view point of more safe and ultimate way of disposing HLWs (both vitrified and spent fuel) than by underground disposal, but also the emergence of new marine project by synergetic collaboration of rare-earth resource exploration from the deep sea floor in Pacific Ocean. (author)

Final disposal of high-level radioactive waste in deep boreholes. An evaluation based on recent research on the bedrock at great depths

International Nuclear Information System (INIS)

Aahaell, Karl-Inge

2006-05-01

New knowledge in hydrogeology and boring technology have opened the possibility to use deep boreholes as a repository for the Swedish high-level radioactive wastes. The determining property is that the repository can be housed in the stable bedrock at levels where the ground water has no contact with the biosphere and disposal and sealing can take place without disturbing the ground water stratification outside the disposal area. An advantage compared to a shallow repository of KBS-3 type, that is now being planned in Sweden, is that a borehole repository is likely to be technologically more robust, since the concept 'deep boreholes' seems to admit such a deep disposal that the entire disposal area would be surrounded by stable density-layered ground water, while a KBS-3 repository would be surrounded by moving ground water in contact with level close to the surface. This hydrological difference is of great importance for the safety in scenarios with leaching of radioactive substances. A deep repository is also less vulnerable for effects from natural events such as glaciation and earthquakes as well as from technological mishaps and terrorist actions. A crucial factor is, however, that the radioactive waste can be disposed of, in a secure way, at the intended depth, which will require new research and technology development

Equity and nuclear waste disposal

International Nuclear Information System (INIS)

Shrader-Frechette, K.

1994-01-01

Following the recommendations of the US National Academy of Sciences and the mandates of the 1987 Nuclear Waste Policy Amendments Act, the US Department of Energy has proposed Yucca Mountain, Nevada as the site of the world's first permanent repository for high-level nuclear waste. The main justification for permanent disposal (as opposed to above-ground storage) is that it guarantees safety by means of waste isolation. This essay argues, however, that considerations of equity (safer for whom?) undercut the safety rationale. The article surveys some prima facie arguments for equity in the distribution of radwaste risks and then evaluates four objections that are based, respectively, on practicality, compensation for risks, scepticism about duties to future generations, and the uranium criterion. The conclusion is that, at least under existing regulations and policies, permanent waste disposal is highly questionable, in part, because it fails to distribute risk equitably or to compensate, in full, for this inequity

Low level radioactive waste disposal/treatment technology overview: Savannah River site

International Nuclear Information System (INIS)

Sturm, H.F. Jr.

1987-01-01

The Savannah River Site will begin operation of several low-level waste disposal/treatment facilities during the next five years, including a new low-level solid waste disposal facility, a low-level liquid effluent treatment facility, and a low-level liquid waste solidification process. Closure of a radioactive hazardous waste burial ground will also be completed. Technical efforts directed toward waste volume reduction include compaction, incineration, waste avoidance, and clean waste segregation. This paper summarizes new technology being developed and implemented. 11 refs., 1 fig

Co-disposal of sewage sludge and solid wastes-it works

Energy Technology Data Exchange (ETDEWEB)

Sussman, D B

1977-10-01

The problem of sludge disposal is one of more sludge than ever before, few suitable land disposal or land application sites, the ocean dumping option being phased out, and energy cost so high or supplies so few as to make incineration a questionable endeavor. The energy required to run a wastewater treatment plant and the heat needed to incinerate the sludge may be available in the same community in the form of municipal solid waste. Municipal sludge has a heat value of about 10,000 Btu/lb of dry solids; it is autogenous at>30% solids. Codisposal techniques are discussed which use the energy produced by the combustion of solid waste to dewater the sludge to its autogenous point. One approach is to use sewage sludge incinerators, in many cases already installed at the wastewater treatment plant, and to use the organic portion of solid waste as a fuel to dry, burn, and reduce the volume of the sludge that must ultimately be disposed. A second approach would use a solid waste incinerator, solid waste-fired steam generator, or waterwall combustion unit to burn dewatered sludge. Both approaches are being demonstrated or used. Thermal sludge disposal at wastewater treatment plants normally is carried out in multiple-hearth or fluidized-bed incinerators. The experiences of such plants in the US and Europe are summarized.

Permeability restoration and lowering of uranium leakage from leached ore beds

International Nuclear Information System (INIS)

Burgman, H.A.; Grant, D.C.

1981-01-01

The injection of an ammonium sulfite or bisulfite solution increases the permeability of an uranium ore bed that has suffered permeability losses during the in-situ mining of uranium with an alkaline leach solution containing a peroxide or dissolved oxygen oxidant. Such an injection recovers much of the lost formation permeability, thus decreasing costs and effort required to put needed restoration solutions or further leach solutions through the ore bed. In addition, uranium contamination of the ground water normally occurring after cessation of leaching is significantly lowered by such injection

Ground penetrating radar for fracture mapping in underground hazardous waste disposal sites: A case study from an underground research tunnel, South Korea

Science.gov (United States)

Baek, Seung-Ho; Kim, Seung-Sep; Kwon, Jang-Soon; Um, Evan Schankee

2017-06-01

Secure disposal or storage of nuclear waste within stable geologic environments hinges on the effectiveness of artificial and natural radiation barriers. Fractures in the bedrock are viewed as the most likely passage for the transport of radioactive waste away from a disposal site. We utilize ground penetrating radar (GPR) to map fractures in the tunnel walls of an underground research tunnel at the Korea Atomic Energy Research Institute (KAERI). GPR experiments within the KAERI Underground Research Tunnel (KURT) were carried out by using 200 MHz, 500 MHz, and 1000 MHz antennas. By using the high-frequency antennas, we were able to identify small-scale fractures, which were previously unidentified during the tunnel excavation process. Then, through 3-D visualization of the grid survey data, we reconstructed the spatial distribution and interconnectivity of the multi-scale fractures within the wall. We found that a multi-frequency GPR approach provided more details of the complex fracture network, including deep structures. Furthermore, temporal changes in reflection polarity between the GPR surveys enabled us to infer the hydraulic characteristics of the discrete fracture network developed behind the surveyed wall. We hypothesized that the fractures exhibiting polarity change may be due to a combination of air-filled and mineralogical boundaries. Simulated GPR scans for the considered case were consistent with the observed GPR data. If our assumption is correct, the groundwater flow into these near-surface fractures may form the water-filled fractures along the existing air-filled ones and hence cause the changes in reflection polarity over the given time interval (i.e., 7 days). Our results show that the GPR survey is an efficient tool to determine fractures at various scales. Time-lapse GPR data may be essential to characterize the hydraulic behavior of discrete fracture networks in underground disposal facilities.

Depth of Intestinal Wall Infiltration and Clinical Presentation of Deep Infiltrating Endometriosis: Evaluation of 553 Consecutive Cases.

Science.gov (United States)

Rossini, Roberto; Lisi, Giorgio; Pesci, Anna; Ceccaroni, Marcello; Zamboni, Giuseppe; Gentile, Irene; Rettore, Lorenzo; Ruffo, Giacomo

2018-02-01

Intestinal involvement in endometriosis was first described by Sampson in 1922. The reported incidence ranges between 3% and 37% in patients diagnosed with endometriosis. In literature, there are few studies that correlate the severity of endometriosis (in terms of intestinal infiltration) and its clinical presentation. The aim of this study was to review the correlation between the severity of symptoms, the depth of intestinal wall infiltration, and lymph node involvement in our tertiary referral center. We retrospectively analyzed 553 patients who had undergone intestinal resection for deep infiltrating endometriosis at our institution (Sacro Cuore Negrar Hospital) between 2004 and 2009. Based on intestinal wall infiltration, we divided patients into three groups (Group A: intestinal infiltration that reaches the muscle layer, Group B: infiltration to the submucosa, and Group C: endometriosis reaches the mucosa). Symptoms, intestinal stenosis, and positive lymph nodes were compared in the three groups with the chi-square test. No statistical correlation was found between symptoms and the intestinal wall infiltrations. The three groups were also compared on the basis of positive visceral lymph nodes and we did find a statistical difference (P = .05) in the lymph node count in the two main groups. There seems to be no statistically significant difference in symptoms between patients with different degrees of infiltration. Although visceral lymph node involvement has been occasionally described in literature, we found that it is related to submucosal infiltration.

Long-term surveillance plan for the Gunnison, Colorado disposal site

International Nuclear Information System (INIS)

1996-04-01

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR section 40.27(b) and 40 CFR section 192.03

Long-term surveillance plan for the Gunnison, Colorado, disposal site

International Nuclear Information System (INIS)

1997-04-01

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR section 40.27(b) and 40 CFR section 192.03

Long-term surveillance plan for the Gunnison, Colorado disposal site

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

Long-term surveillance plan for the Gunnison, Colorado, disposal site

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

Long-term surveillance plan for the Gunnison, Colorado, disposal site

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

Long-term surveillance plan for the Gunnison, Colorado, disposal site

International Nuclear Information System (INIS)

1996-05-01

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR section 40.27(b) and 40 CFR section 192.03

Commercial radioactive waste disposal: marriage or divorce

International Nuclear Information System (INIS)

Corbett, J.S.

1977-01-01

It is shown that the state (South Carolina) is doing a good job in regulating the South Carolina disposal facility of Chemo-Nuclear Inc., and that there is no need for the NRC to reassert Federal control. The efforts in developing a low-level site in New Mexico are described. The NRC Task Force report on Federal/state regulation of commercial low-level radioactive waste burial grounds is discussed

Assessment of the Impact of Radioactive Disposals and Discharges from the United Kingdom Low Level Waste Repository on the Ecosystem

International Nuclear Information System (INIS)

Barber, N.

2009-01-01

This paper describes an assessment of the impacts to ecosystems and wildlife species from radioactive discharges and disposals at the United Kingdom's low level waste disposal facility in West Cumbria. The assessment was undertaken in response to a requirement in the site's current authorisation and comprised a detailed desk based review along with an exercise to screen relevant monitoring data from the site against generic assessment criteria and undertake a numerical risk assessment. Much of the site is vegetated, comprising a variety of habitats including grassland, relict dune heath and surface water bodies. Furthermore, the site is located adjacent to a coastal/estuarine area which is protected as it provides a habitat of high ecological value and species of animals and plants are present that are rare, endangered or vulnerable. However, the current impact of aerial and liquid radioactive discharges from the low level waste repository on ecosystems and wildlife species is considered to be low. Site monitoring data also indicate that there has been a reduction of radionuclide activities in ground and surface water and leachates over time, a result of measures initiated to minimise rainwater infiltration and improve leachate management associated with the disposal area. A quantitative assessment was undertaken to assess future impacts to relevant terrestrial, fresh water and marine ecosystems. This showed that modelled peak radionuclide concentrations in the first 4,000 years after site closure were not sufficiently high to cause potential impact to any of these ecosystems or associated wildlife. This cut-off date was chosen as it is considered probable that, due to the effects of future climate and landscape change and, unless actions are taken to defend the coastline, the site is likely to be disrupted by coastal erosion in the next 4,000 years. (authors)

Impact of climate variations on Managed Aquifer Recharge infiltration basins.

Science.gov (United States)