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1

Long-term surveillance plan for the Shiprock Disposal site, Shiprock, New Mexico  

SciTech Connect

The long-term surveillance plan (LTSP) for the Shiprock, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Shiprock disposal cell. The U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents the land ownership interests and details how the long-term care of the disposal site will be carried out. It is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a).

Not Available

1994-09-01

2

Comment and response document for the long-term surveillance plan for the Shiprock, New Mexico, disposal site  

SciTech Connect

This document contains comments and responses regarding the long-term surveillance plan for the Shiprock, New Mexico uranium mine tailings disposal site. Discrepencies and errors within the plan document are noted and corrections are recorded.

Not Available

1994-09-01

3

Engineering assessment of inactive uranium mill tailings, Shiprock site, Shiprock, New Mexico  

SciTech Connect

Ford, Bacon and Davis Utah Inc. has reevaluated the Shiprock site in order to revise the March 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Shiprock, New Mexico. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 1.5 million dry tons of tailings at the Shiprock site constitutes the most significant environental impact, although windblown tailings and external gamma radiation also are factors. The eight alternative actions presented in this engineering assessment range from millsite decontamination with the addition of 3 m of stabilization cover material (Option I), to removal of the tailings to remote disposal sites and decontamination of the tailings site (Options II through VIII). Cost estimates for the eight options range from about $13,400,000 for stabilization in place to about $37,900,000 for disposal at a distance of about 16 miles. Three principal alternatives for the reprocessing of the Shiprock tailings were examined: (a) heap leaching; (b) treatment at an existing mill; and (c) reprocessing at a new conventional mill constructed for tailings reprocessing. The cost of the uranium recovered would be about $230/lb by heap leach and $250/lb by conventional plant processes. The spot market price for uranium was $25/lb early in 1981. Therefore, reprocessing the tailings for uranium recovery is not economically attractive.

Not Available

1981-07-01

4

RADIOACTIVE WASTE DISPOSAL IN THE SHIPROCK-TYPE URANIUM MILLING FLOWSHEET  

Microsoft Academic Search

A study was made of possible modifications in conventional uranium ore-; processing steps to confine and permit controlled disposal of radioactive wastes. ; A potential method of minimizing pollution from radioactive nuclides, principally ; radium-226, in uranium mill waste streams is to reuse the waste solutions within ; the mill. Such reuse of waste solution in the Kerr-McGee Shiprock-type process

K. E. Tame; E. G. Valdez; J. B. Rosenbaum

1961-01-01

5

Site observational work plan for the UMTRA project site at Shiprock, New Mexico  

SciTech Connect

The site observational work plan (SOWP) for the Shiprock, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project Site is the initial document for developing site-specific activities to achieve regulatory compliance in the UMTRA Ground Water Project. The regulatory framework used to select the proposed ground water compliance strategies is presented along with a discussion of the relationship of this SOWP to other UMTRA Ground Water Project programmatic documents. The Shiprock site consists of two, interconnected hydrogeologic systems: the terrace system and the floodplain system. Separate compliance strategies are proposed for these two systems. The compliance strategy for the terrace aquifer is no remediation with the application of supplemental standards based on classification of the terrace aquifer as having Class III (limited-use) ground water. The compliance strategy for the floodplain aquifer is active remediation using a subsurface biological barrier. These strategies were selected by applying site-specific data to the compliance framework developed in the UMTRA Ground Water programmatic environmental impact statement (PEIS) (DOE, 1994a). The site conceptual model indicates that milling-related contamination has impacted the ground water in the terrace and floodplain aquifers. Ground water occurs in both aquifers in alluvium and in fractures in the underlying Cretaceous age Mancos Shale. A mound of ground water related to fluids from the milling operations is thought to exist in the terrace aquifer below the area where settling ponds were in use during the mill operations. Most of the water occurring in the floodplain aquifer is from recharge from the San Juan River.

Not Available

1994-09-01

6

UMTRA project water sampling and analysis plan -- Shiprock, New Mexico  

SciTech Connect

Water sampling and analysis plan (WSAP) is required for each U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site to provide a basis for ground water and surface water sampling at disposal and former processing sites. This WSAP identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequency for the monitoring stations at the Navaho Reservation in Shiprock, New Mexico, UMTRA Project site. The purposes of the water sampling at Shiprock for fiscal year (FY) 1994 are to (1) collect water quality data at new monitoring locations in order to build a defensible statistical data base, (2) monitor plume movement on the terrace and floodplain, and (3) monitor the impact of alluvial ground water discharge into the San Juan River. The third activity is important because the community of Shiprock withdraws water from the San Juan River directly across from the contaminated alluvial floodplain below the abandoned uranium mill tailings processing site.

Not Available

1994-02-01

7

Hanford Site Mixed Waste Disposal  

Microsoft Academic Search

Significant volumes of mixed low-level waste (MLLW) will be generated as part of the management and remediation of the Hanford Site. The MLLW that is generated as part of the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA) process will largely be managed as part of that remediation effort, with disposal likely in the centralized Environmental Restoration Disposal

2001-01-01

8

Hanford Site Mixed Waste Disposal  

SciTech Connect

Significant volumes of mixed low-level waste (MLLW) will be generated as part of the management and remediation of the Hanford Site. The MLLW that is generated as part of the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA) process will largely be managed as part of that remediation effort, with disposal likely in the centralized Environmental Restoration Disposal Facility (ERDF). Other unique MLLW streams will be produced as part of the Hanford program to disposition tank wastes, and will include failed equipment (melters) and immobilized low-activity wastes. These disposal operations are in the early planning stages and will likely require development of specialized disposal facilities. This paper will focus on disposal of the more ''routine'' waste streams, those currently stored onsite in permitted Resource Conservation and Recover Act (RCRA) facilities, or those newly-generated MLLW streams requiring management in permitted RCRA facilities. These waste streams typically include RCRA regulated MLLW debris, sludges, soils and solidified liquids. In September 1999, the United States Department of Energy, Richland Operations Office and Fluor Hanford began disposing of Land Disposal Restrictions (LDR) compliant MLLW in a RCRA mixed waste disposal facility at the Hanford Site. This facility, one of two at Hanford, is an integral part of a comprehensive program to treat and dispose of the Hanford inventory of stored MLLW, and may aid the DOE Complex in disposing of its legacy of MLLW. The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) record-of-decision (ROD) for MLLW identifies Hanford as one of the disposal sites for much of the DOE complex MLLW. A few actions remain to be completed before waste from offsite generators can be shipped to the Hanford Mixed Waste Facilities for disposal. These actions include, but are not limited to, completion of the Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (SW EIS), resolving equity issues associated with the receipt of offsite MLLW, and verification that the candidate waste streams meet the Hanford Site Waste Acceptance Criteria (WAC). The ROD for the SW EIS is expected in 2002, equity discussions are ongoing, and waste acceptance criteria are already established and can be used to determine acceptability.

MCKENNEY, D.E.

2001-01-01

9

Site Characterization for the Saltstone Disposal Facility.  

National Technical Information Service (NTIS)

In 1980 a site was selected for the disposal of a solidified, decontaminated salt solution that will result from preparing feed for the Defense Waste Processing Facility. Since that time a number of field and laboratory investigations have been conducted ...

J. R. Cook

1985-01-01

10

40 CFR 228.3 - Disposal site management responsibilities.  

Code of Federal Regulations, 2013 CFR

...OCEAN DUMPING CRITERIA FOR THE MANAGEMENT OF DISPOSAL SITES FOR OCEAN DUMPING § 228.3 Disposal site management responsibilities. (a) Management of a site consists of regulating times, rates, and methods...

2013-07-01

11

43 CFR 2743.4 - Patented disposal sites.  

Code of Federal Regulations, 2010 CFR

...Interior 2 2010-10-01 2010-10-01 false Patented disposal sites. 2743.4 Section 2743.4 Public Lands...and Public Purposes Act: Solid Waste Disposal 2743.4 Patented disposal sites. (a) Upon request by or with...

2010-10-01

12

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE`s Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site`s waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-12-31

13

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-01-01

14

Specialized Disposal Sites for Different Reprocessing Plant Wastes  

SciTech Connect

Once-through fuel cycles have one waste form: spent nuclear fuel (SNF). In contrast, the reprocessed SNF yields multiple wastes with different chemical, physical, and radionuclide characteristics. The different characteristics of each waste imply that there are potential cost and performance benefits to developing different disposal sites that match the disposal requirements of different waste. Disposal sites as defined herein may be located in different geologies or in a single repository containing multiple sections, each with different characteristics. The paper describes disposal options for specific wastes and the potential for a waste management system that better couples various reprocessing plant wastes with disposal facilities. (authors)

Forsberg, Charles W. [Nuclear Science and Technology Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN, 37831 (United States); Driscoll, Michael J. [Department of Nuclear Science and Technology, Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge, MA, 02139 (United States)

2007-07-01

15

CONVECTIVE-DISPERSIVE TRANSPORT MODEL FOR WASTES DISPOSED AT THE 106-MILE OCEAN DISPOSAL SITE  

EPA Science Inventory

A two-dimensional, convective-dispersive transport model was used to predict bounds on the expected long-term time-averaged dilutions for wastes disposed of at the 106-Mile Ocean Disposal Site (between 38 degrees 40' and 39 degrees 00'N, and 72 degrees 00' and 72 degrees 30'W). o...

16

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs  

Microsoft Academic Search

Low-level radioactive waste (LLW) streams which have a clear, defined pathway to disposal are becoming less common as U.S. Department of Energy accelerated cleanup sites enters their closure phase. These commonly disposed LLW waste streams are rapidly being disposed and the LLW inventory awaiting disposal is dwindling. However, more complex waste streams that have no path for disposal are now

E. F. Di Sanza; J. T. Carilli

2006-01-01

17

10 CFR 61.50 - Disposal site suitability requirements for land disposal.  

Code of Federal Regulations, 2010 CFR

...table if it can be conclusively shown that disposal site characteristics will result in molecular diffusion being the predominant means of radionuclide movement and the rate of movement will result in the performance objectives of subpart C of...

2009-01-01

18

10 CFR 61.50 - Disposal site suitability requirements for land disposal.  

Code of Federal Regulations, 2010 CFR

...table if it can be conclusively shown that disposal site characteristics will result in molecular diffusion being the predominant means of radionuclide movement and the rate of movement will result in the performance objectives of subpart C of...

2010-01-01

19

On-site low-level waste disposal  

SciTech Connect

According to US Nuclear Regulatory Commission (NRC) regulations, low-level radioactive waste (LLW) may be disposed of in various ways. These include: (a) transfer to an LLW disposal site, (b) effluents to air and water, (c) release to a sanitary sewage system, (d) storage for decay, (e) incineration, (f) disposal of certain specific waste without regard to its radioactivity, and (g) specifically approved disposals that are not otherwise authorized in the regulations. This presentation addresses on-site disposal primarily by burial in soil. In addition, discussions focus primarily on considerations of on-site burials of radioactive waste generated by institutional (medical and academic) and industrial licensees. Radiological assessments are strongly dependent on site-specific information. This information is required from the licensee when submitting a request for disposal authorization. The estimated radiation dose equivalent will be the primary factor in determining whether the licensee's proposed disposal will or will not be authorized. Often, burials by the licensee under prescribed conditions along with imposed restrictions as to the proximity of water wells will ensure that the projected dose to an individual on or near the site will be within acceptable limits.

Neuder, S.M.; Kennedy, W.E. Jr.; Fasano, C.

1985-11-01

20

EVALUATION OF ON-SITE WASTEWATER TREATMENT AND DISPOSAL OPTIONS  

EPA Science Inventory

A literature review of published and unpublished data was conducted to identify all conceivable alternative on-site systems, including wastewater manipulation, treatment and disposal options. Wastewater manipulation options included flow reduction, wasteload reduction and waste s...

21

HANDBOOK FOR REMEDIAL ACTION AT WASTE DISPOSAL SITES  

EPA Science Inventory

This handbook is directed toward technical personnel in federal, state, regional, and municipal agencies involved in the cleanup of hazardous waste disposal sites, industrial surface impoundments, and municipal, industrial, and combined landfills. It contains a summary of the flo...

22

Hanford Site Grout Disposal Program interim management plan  

Microsoft Academic Search

This plan was developed to implement the Hanford Defense Waste-Environmental Impact Statement Record of Decision. The plan is also a management tool for use in defining Hanford Site Grout Disposal Program activities required to ensure the safe, environmentally sound, and cost-effective disposal of the low-level fraction of radioactive double-shell tank mixed wastes at the Hanford Site. This plan includes a

Wood

1992-01-01

23

Rodents as receptor species at a tritium disposal site.  

PubMed

New methods are being employed on the Department of Energy's Savannah River Site to deal with the disposal of tritium, including the irrigation of a hardwood/pine forest with tritiated water from an intercepted contaminant plume to reduce concentrations of tritium outcropping into Fourmile Branch, a tributary of the Savannah River. The use of this system has proven to be an effective means of tritium disposal. To evaluate the impact of this activity on terrestrial biota, rodent species were captured on the tritium disposal site and a control site during two trapping seasons in order to assess tritium exposure resulting from the forest irrigation. Control site mice had background levels of tritium, 0.02 Bq/mL, with disposal site mice having significantly higher tritium concentrations, mean=34.86 Bq/mL. Whole body tritium concentrations of the mice captured at the disposal site were positively correlated with tritium application and negatively correlated with precipitation at the site. PMID:15829339

Kelsey-Wall, Angel; Seaman, John C; Jagoe, Charles H; Dallas, Cham E; Gaines, Karen F

2005-01-01

24

Low-level radioactive waste disposal at a humid site  

SciTech Connect

Waste management in humid environments poses a continuing challenge because of the potential contamination of groundwater in the long term. Short-term needs for waste disposal, regulatory uncertainty, and unique site and waste characteristics have led to the development of a site-specific waste classification and management system proposed for the Oak Ridge Reservation. The overlying principle of protection of public health and safety is used to define waste classes compatible with generated waste types, disposal sites and technologies, and treatment technologies. 1 fig., 1 tab.

Lee, D.W.

1987-03-01

25

Remediation of a Former USAF Radioactive Material Disposal Site  

SciTech Connect

This paper describes the remediation of a low-level radiological waste burial site located at the former James Connally Air Force Base in Waco, Texas. Burial activities at the site occurred during the 1950's when the property was under the ownership of the United States Air Force. Included is a discussion of methods and strategies that were used to successfully exhume and characterize the wastes for proper disposal at offsite disposal facilities. Worker and environmental protection measures are also described. Information gained from this project may be used at other similar project sites. A total of nine burial tubes had been identified for excavation, characterization, and removal from the site. The disposal tubes were constructed of 4-ft lengths of concrete pipe buried upright with the upper ends flush with ground surface. Initial ground level observations of the burial tubes indicated that some weathering had occurred; however, the condition of the subsurface portions of the tubes was unknown. Soil excavation occurred in 1-foot lifts in order that the tubes could be inspected and to allow for characterization of the soils at each stage of the excavation. Due to the weight of the concrete pipe and the condition of the piping joints it was determined that special measures would be required to maintain the tubes intact during their removal. Special tube anchoring and handling methods were required to relocate the tubes from their initial positions to a staging area where they could be further characterized. Characterization of the disposal tubes was accomplished using a combination of gamma spectroscopy and activity mapping methods. Important aspects of the project included the use of specialized excavation and disposal tube reinforcement measures to maintain the disposal tubes intact during excavation, removal and subsequent characterization. The non-intrusive gamma spectroscopy and data logging methods allowed for effective characterization of the wastes while minimizing disposal costs. In addition, worker exposures were maintained ALARA as a result of the removal and characterization methods employed.

Hoffman, D. E.; Cushman, M; Tupyi, B.; Lambert, J.

2003-02-25

26

Health effects of a thorium waste disposal site.  

PubMed Central

A case-control study of 112 households residing in the vicinity of a thorium waste disposal site found a higher prevalence of birth defects (RR 2.1) and liver diseases (RR 2.3) among exposed than the unexposed group. The numbers were quite small and the confidence intervals wide, however, so that no definite conclusions can be drawn from these data.

Najem, G R; Voyce, L K

1990-01-01

27

Health effects of a thorium waste disposal site  

SciTech Connect

A case-control study of 112 households residing in the vicinity of a thorium waste disposal site found a higher prevalence of birth defects (RR 2.1) and liver diseases (RR 2.3) among exposed than the unexposed group. The numbers were quite small and the confidence intervals wide, however, so that no definite conclusions can be drawn from these data.

Najem, G.R.; Voyce, L.K. (UMDNJ-New Jersey Medical School, Newark (USA))

1990-04-01

28

Site characterization for LIL radioactive waste disposal in Romania  

SciTech Connect

Recent studies in radioactive waste management in Romania have focussed mainly on the disposal of low and intermediate level waste from the operation of the new nuclear power plant at Cernavoda. Following extensive geological, hydrological, seismological, physical and chemical investigations, a disposal site at Saligny has been selected. This paper presents description of the site at Saligny as well as the most important results of the site characterisation. These are reflected in the three-dimensional, stratigraphical representation of the loess and clay layers and in representative parameter values for the main layers. Based on these data, the simulation of the background, unsaturated-zone water flow at the Saligny site, calculated by the FEHM code, is in a good agreement with the measured moisture profile.

Diaconu, D. R. (Daniela R.); Birdsell, K. H. (Kay H.); Witkowski, M. S. (Marc S.)

2001-01-01

29

Remediation of Hanford's N-Reactor Liquid Waste Disposal Sites.  

PubMed

Hanford's N-Reactor operated from 1963 to 1987 generating approximately 9 x 10 m of radioactive and hazardous liquid effluent as a result of reactor operations. Two liquid waste disposal sites, essentially large trenches designed to filter contaminants from the water as it percolates through the soil column, were established to dispose of the effluent. The discharges to the sites included cooling water from the reactor primary, spent fuel storage, and periphery systems, along with miscellaneous drainage from reactor support facilities. Today, both sites are classified as Treatment Storage and Disposal Facilities under the Resource Conservation and Recovery Act of 1976, which makes them priority sites for remediation. The two sites cover approximately 4,100 m and 9,300 m, respectively. Remediation of the sites requires removing a combined total of approximately 2.6 x 10 kg of contaminated soil and debris. Principal radionuclides contained in the soil/debris are Co, Cs, Pu, and Sr. Remediation of these waste sites requires demolishing concrete structures and excavating, hauling, and disposing of contaminated soils in work areas containing high levels of contamination and whole body dose rates in excess of 1 mSv h. The work presents unique radiological control challenges, such as minimizing external dose to workers in a constantly changing outdoor work environment, maintaining contamination control during removal of a water distribution trough filled with highly contaminated sludge, and minimizing outdoor airborne contamination during size reduction of highly contaminated pipelines. Through innovative approaches to dose reduction and contamination control, Hanford's Environmental Restoration Contractor has met the challenge, completing the first phase on schedule and with a total project exposure below the goal of 0.1 person-Sv. PMID:12555036

Sitsler, Robert B.; DeMers, Steven K.

2003-02-01

30

Voluntary cleanup of the Ames chemical disposal site.  

SciTech Connect

The U.S. Department of Energy completed a voluntary removal action at the Ames chemical disposal site, a site associated with the early days of the Manhattan Project. It contained chemical and low-level radioactive wastes from development of the technology to extract uranium from uranium oxide. The process included the preparation of a Remedial Investigation, Feasibility Study, Baseline Risk Assessment, and, ultimately, issuance of a Record of Decision. Various stakeholder groups were involved, including members of the regulatory community, the general public, and the landowner, Iowa State University. The site was restored and returned to the landowner for unrestricted use.

Taboas, A. L.; Freeman, R.; Peterson, J.; Environmental Assessment; USDOE

2003-01-01

31

Waste disposal site selection using GIS-based simulated annealing  

NASA Astrophysics Data System (ADS)

The Markov-chain-based simulated annealing algorithm is applied to search a Geographic Information System (GIS) to locate potential waste disposal sites in the Indian Pine watershed of Indiana, on administrative scores that have been regulated by the Indiana Solid Waste Management Board. Results show that simulated annealing achieved an order of magnitude reduction in execution time over that of an exhaustive search method, and gives a policy maker the option of selecting the final site based on social factors that are not considered in the numerical model.

Muttiah, R. S.; Engel, B. A.; Jones, D. D.

1996-11-01

32

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs  

SciTech Connect

Low-level radioactive waste (LLW) streams which have a clear, defined pathway to disposal are becoming less common as U.S. Department of Energy accelerated cleanup sites enters their closure phase. These commonly disposed LLW waste streams are rapidly being disposed and the LLW inventory awaiting disposal is dwindling. However, more complex waste streams that have no path for disposal are now requiring attention. The U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NSO) Environmental Management Program is charged with the responsibility of carrying out the disposal of onsite and off-site defense-generated and research-related LLW at the Nevada. Test Site (NTS). The NSO and its generator community are constantly pursuing new LLW disposal techniques while meeting the core mission of safe and cost-effective disposal that protects the worker, the public and the environment. From trenches to present-day super-cells, the NTS disposal techniques must change to meet the LLW generator's disposal needs. One of the many ways the NTS is addressing complex waste streams is by designing waste specific pits and trenches. This ensures unusual waste streams with high-activity or large packaging have a disposal path. Another option the NTS offers is disposal of classified low-level radioactive-contaminated material. In order to perform this function, the NTS has a safety plan in place as well as a secure facility. By doing this, the NTS can accept DOE generated classified low-level radioactive-contaminated material that would be equivalent to U.S. Nuclear Regulatory Commission Class B, C, and Greater than Class C waste. In fiscal year 2006, the NTS will be the only federal disposal facility that will be able to dispose mixed low-level radioactive waste (MLLW) streams. This is an activity that is highly anticipated by waste generators. In order for the NTS to accept MLLW, generators will have to meet the stringent requirements of the NTS Waste Acceptance Criteria. The disposal operations previously mentioned take place at the NTS in two disposal facilities. The isolation protection and overall performance of the two LLW disposal facilities at the NTS transcend those of any federal radioactive waste disposal site in the United States. The first of the two disposal sites is the Area 5 Radioactive Waste Management Site (RWMS) which is situated on alluvial fan deposits in the Frenchman Flat basin, approximately 770 feet (235 meters) above the water table. The Area 5 RWMS utilizes a combination of engineered shallow land disposal cells and deep augured shafts for the disposal of a variety of waste streams. Fifteen miles (24 kilometers) north of the Area 5 RWMS is the Area 3 RWMS located approximately 1,600 feet (488 meters) above the water table in Yucca Flat. Disposal activities at the Area 3 RWMS center around the placement of bulk LLW in subsidence craters formed from underground testing of nuclear weapons. Native alluvium soil is used to cover waste placed in the disposal cells at both facilities. In addition, information on the technical attributes, facility performance, updates on waste disposal volumes and capabilities, and current and future disposal site requirements will also be described. (authors)

Di Sanza, E.F.; Carilli, J.T. [U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, P.O. Box 98518, Las Vegas, NV 89193-8518 (United States)

2006-07-01

33

40 CFR 61.154 - Standard for active waste disposal sites.  

Code of Federal Regulations, 2010 CFR

...Each owner or operator of an active waste disposal site that...to the outside air from any active waste disposal site where...the owner or operator of the active waste disposal site shall...telephone number of the waste generator. (ii) The name,...

2010-07-01

34

Application of studies on the overboard placement of dredged sediments to the management of disposal sites  

USGS Publications Warehouse

From the mid 1960's until 1991, dredging and disposal occurred in the northern Chesapeake Bay without guidelines to maximize the capacity and to minimize the spread of the deposits beyond the disposal sites, particularly toward the navigation channel. Planning for future dredging projects is dependant upon the remaining site capacity and the behavior of the disposed sediment. Recent studies have shown that the fate of the deposited sediments is determined primarily by the water depth and bathymetry in the vicinity of the disposal site, and the method of dredging and disposal utilized. Currently used open-water disposal sites in the northern Chesapeake Bay are reaching their maximum capacity. This makes the application of the information from these studies critical, both for the optimal use of current sites and for the evaluation of new sites. Management scenarios utilizing these studies are applied to a disposal site in the northern Chesapeake Bay.

Panageotou, William; Halka, Jeffrey

1994-01-01

35

Studies of current circulation at ocean waste disposal sites  

NASA Technical Reports Server (NTRS)

The author has identified the following significant results. Acid waste plume was observed in LANDSAT imagery fourteen times ranging from during dump up to 54 hours after dump. Circulation processes at the waste disposal site are highly storm-dominated, with the majority of the water transport occurring during strong northeasterlies. There is a mean flow to the south along shore. This appears to be due to the fact that northeasterly winds produce stronger currents than those driven by southeasterly winds and by the thermohaline circulation. During the warm months (May through October), the ocean at the dump site stratifies with a distinct thermocline observed during all summer cruising at depths ranging from 10 to 21 m. During stratified conditions, the near-bottom currents were small. Surface currents responded to wind conditions resulting in rapid movement of surface drogues on windy days. Mid-depth drogues showed an intermediate behavior, moving more rapidly as wind velocities increased.

Klemas, V. (principal investigator); Davis, G.; Henry, R.

1976-01-01

36

Evaluating off-site disposal of low-level waste at LANL-9498  

SciTech Connect

Los Alamos National Laboratory generates a wide range of waste types, including solid low-level radioactive waste (LL W), in conducting its national security mission and other science and technology activities. Although most ofLANL's LLW has been disposed on-site, limitations on expansion, stakeholder concerns, and the potential for significant volumes from environmental remediation and decontamination and demolition (D&D) have led LANL to evaluate the feasibility of increasing off-site disposal. It appears that most of the LL W generated at LANL would meet the Waste Acceptance Criteria at the Nevada Test Site or the available commercial LL W disposal site. Some waste is considered to be problematic to transport to off-site disposal even though it could meet the off-site Waste Acceptance Criteria. Cost estimates for off-site disposal are being evaluated for comparison to estimated costs under the current plans for continued on-site disposal.

Hargis, Kenneth M [Los Alamos National Laboratory; French, Sean B [Los Alamos National Laboratory; Boyance, Julien A [NORTH WIND, INC.

2009-01-01

37

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site  

SciTech Connect

The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan for the Disposal of Low-Level Waste with Regulated Asbestos Waste.'' A requirement of the authorization was that on or before October 9, 1999, a permit was required to be issued. Because of NDEP and NNSA/NSO review cycles, the final permit was issued on April 5, 2000, for the operation of the Area 5 Low-Level Waste Disposal Site, utilizing Pit 7 (P07) as the designated disposal cell. The original permit applied only to Pit 7, with a total design capacity of 5,831 cubic yards (yd{sup 3}) (157,437 cubic feet [ft{sup 3}]). NNSA/NSO is expanding the SWDS to include the adjacent Upper Cell of Pit 6 (P06), with an additional capacity of 28,037 yd{sup 3} (756,999 ft{sup 3}) (Figure 3). The proposed total capacity of ALLW in Pit 7 and P06 will be approximately 33,870 yd{sup 3} (0.9 million ft{sup 3}). The site will be used for the disposal of regulated ALLW, small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. The only waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM). The term asbestiform is used throughout this document to describe this waste. Other TSCA waste (i.e., polychlorinated biphenyls [PCBs]) will not be accepted for disposal at the SWDS. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the U.S. Department of Energy, Nevada Operations Office (DOE/NV) 325

NSTec Environmental Programs

2010-09-14

38

Studies of current circulation at ocean waste disposal sites. [Delaware  

NASA Technical Reports Server (NTRS)

The author has identified the following significant results. Circulation processes at the acid waste disposal site are highly event-dominated, with the majority of the water transport occurring during strong northeasters. There is a mean flow to the south alongshore. This appears to be due to the fact that northeasterly winds produce stronger currents than those driven by southeasterly winds and by the thermohaline circulation. During the warm months, the ocean stratifies with warm water over cold water. A distinct thermocline was observed with expendable bathythermographs during all summer cruises at depths ranging from 10 to 21 meters. During stratified conditions, the near-bottom drogues showed very little movements. The duPont waste plume was observed in LANDSAT satellite imagery during dump up to 54 hours after dump.

Klemas, V. (principal investigator); Davis, G.; Henry, R.

1975-01-01

39

Damos: Twenty Years of Dredged Material Disposal Site Monitoring. Isn'st That Enough?  

Microsoft Academic Search

Since 1977, the US Army Corps of Engineers Disposal Area Monitoring System (DAMOS) has monitored New England's offshore dredged material disposal sites. DAMOS has shown that by using monitoring information to make management decisions, open water disposal of dredged sediments is possible with minimal environmental impact. Over the past two decades, DAMOS has answered many of the key questions about

Thomas J. Fredette

1998-01-01

40

Characterization of organics in leachates from low-level radioactive waste disposal sites  

Microsoft Academic Search

Low-level radioactive wastes generated by the nuclear industry, universities, research institutions, and hospitals are disposed of in shallow-land trenches and pits. In 1962 the first commercial disposal site was opened in Beatty, Nevada. Since then, the industry has grown to include three private companies operating six disposal areas located in sparsely populated areas: at Maxey Flats (Morehead), Kentucky; Beatty, Nevada;

A. J. Francis; C. R. Iden; B. Nine; C. Chang

1979-01-01

41

Distribution of sewage indicated by Clostridium perfringens at a deep-water disposal site after cessation of sewage disposal.  

PubMed Central

Clostridium perfringens, a marker of domestic sewage contamination, was enumerated in sediment samples obtained from the vicinity of the 106-Mile Site 1 month and 1 year after cessation of sewage disposal at this site. C. perfringens counts in sediments collected at the disposal site and from stations 26 nautical miles (ca. 48 km) and 50 nautical miles (ca. 92 km) to the southwest of the site were, in general, more than 10-fold higher than counts from an uncontaminated reference site. C. perfringens counts at the disposal site were not significantly different between 1992 and 1993, suggesting that sewage sludge had remained in the benthic environment at this site. At stations where C. perfringens counts were elevated (i.e., stations other than the reference station), counts were generally higher in the top 1 cm and decreased down to 5 cm. In some cases, C. perfringens counts in the bottom 4 or 5 cm showed a trend of higher counts in 1993 than in 1992, suggesting bioturbation. We conclude that widespread sludge contamination of the benthic environment has persisted for at least 1 year after cessation of ocean sewage disposal at the 106-Mile Site.

Hill, R T; Straube, W L; Palmisano, A C; Gibson, S L; Colwell, R R

1996-01-01

42

Waste inventory and preliminary source term model for the Greater Confinement Disposal site at the Nevada Test Site  

SciTech Connect

Currently, there are several Greater Confinement Disposal (GCD) boreholes at the Radioactive Waste Management Site (RWMS) for the Nevada Test Site. These are intermediate-depth boreholes used for the disposal of special case wastes, that is, radioactive waste within the Department of Energy complex that do not meet the criteria established for disposal of high-level waste, transuranic waste, or low-level waste. A performance assessment is needed to evaluate the safety of the GCD site, and to examine the feasibility of the GCD disposal concept as a disposal solution for special case wastes in general. This report documents the effort in defining all the waste inventory presently disposed of at the GCD site, and the inventory and release model to be used in a performance assessment for compliance with the Environmental Protection Agency`s 40 CFR 191.

Chu, M.S.Y.; Bernard, E.A.

1991-12-01

43

Health Assessment for Asbestos Disposal Site (ADS) National Priorities List (NPL) Site, Morris County, New Jersey, Region 2.  

National Technical Information Service (NTIS)

The Asbestos Disposal Site consists of four sites located in Morris County, New Jersey which together comprise a National Priority List Site. On-site heavy metals and asbestos are the primary contaminants of concern for all of the sites. Off-site concerns...

1989-01-01

44

Groundwater hydrology study of the Ames Chemical Disposal Site  

SciTech Connect

The Ames Laboratory Chemical Disposal Site is located in northwestern Ames, Iowa west of Squaw Creek. From 1957 to 1966, Ames Laboratory conducted research to develop processes to separate uranium and thorium from nuclear power fuel and to separate yttrium from neutron shielding sources. The wastes from these processes, which contained both hazardous and radiological components, were placed into nine burial pits. Metal drums, plywood boxes, and steel pails were used to store the wastes. Uranium was also burned on the ground surface of the site. Monitoring wells were placed around the waste burial pits. Groundwater testing in 1993 revealed elevated levels of Uranium 234, Uranium 238, beta and alpha radiation. The north side of the burial pit had elevated levels of volatile organic compounds. Samples in the East Ravine showed no volatile organics; however, they did contain elevated levels of radionuclides. These analytical results seem to indicate that the groundwater from the burial pit is flowing down hill and causing contamination in the East Ravine. Although there are many avenues for the contamination to spread, the focus of this project is to understand the hydrogeology of the East Ravine and to determine the path of groundwater flow down the East Ravine. The groundwater flow data along with other existing information will be used to assess the threat of chemical migration down the East Ravine and eventually off-site. The primary objectives of the project were as follows: define the geology of the East Ravine; conduct slug tests to determine the hydraulic conductivity of both oxidized and unoxidized till; develop a three-dimensional mathematical model using ModIME and MODFLOW to simulate groundwater flow in the East Ravine.

Stickel, T.

1996-05-09

45

Final long-term surveillance plan for the Spook, Wyoming, disposal site  

SciTech Connect

A general license for the custody and long-term care of DOE Uranium Mill Tailings Remedial Action (UMTRA) Project permanent disposal sites was issued by the US Nuclear Regulatory Commission (NRC), and became effective on November 29, 1990. The general license will be in effect for a specific disposal site when the NRC accepts the disposal site`s long-term surveillance plan (LTSP) and concurs that remedial action is complete at that site. This document describes in detail the long-term surveillance activities for the Spook, Wyoming, disposal site, including monitoring, maintenance, and emergency measures necessary to fulfill the conditions of the general license, and to ensure that the disposal cell continues to comply with the UMTRA design standards.

NONE

1993-01-01

46

Hanford Site waste treatment/storage/disposal integration  

SciTech Connect

In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps.

MCDONALD, K.M.

1999-02-24

47

Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513  

SciTech Connect

The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

Mohamed, Yasser T. [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

2013-07-01

48

Sediment classification based on repetitive multibeam bathymetry surveys of an offshore disposal site  

Microsoft Academic Search

A disposal site near Saint John, New Brunswick, Canada, has been surveyed at six-month intervals for the past three years with Simrad EM3000 multibeam bathymetry systems. Analysis of the bathymetry data from surveys in the autumn show accumulation of sediments over the site due to disposal activities in the summer and autumn; surveys in the spring show that the sediment

J. M. Preston; D. R. Parrott; W. T. Collins

2003-01-01

49

Geographic information system (G.I.S.) research project at Navajo Community College - Shiprock Campus  

SciTech Connect

The Navajo and Hopi GIS Project was established to assess the feasibility and impact of implementing GIS techology at Tribal institutions. Los Alamos and Lawrence Livermore National Laboratories funded the Navajo and Hopi Geographic Information System (G.I.S.) Project and assigned a mentor from LANL to help guide the project for three summer months of 1995. The six organizations involved were: LANL, LLNL, Navajo Community College, Navajo Nation Land Office, Northern Arizona University and San Juan College. The Navajo Land Office provided the system software, hardware and training. Northern Arizona University selected two students to work at Hopi Water Resource Department. Navajo Community College provided two students and two faculty members. San Juan College provided one student to work with the N.C.C. group. This made up two project teams which led to two project sites. The project sites are the Water Resource Department on the Hopi reservation and Navajo Community College in Shiprock, New Mexico.

Yazzie, R.; Peter, C.; Aaspas, B.; Isely, D.; Grey, R.

1995-12-31

50

In situ radiological characterization to support a test excavation at a liquid waste disposal site  

SciTech Connect

An in situ radiological detection system was developed to support a small test excavation at a liquid waste disposal site at the Hanford Site in Richland, Washington. Instrumentation, calibration and comparisons to samples are discussed.

Keele, B.D.; Bauer, R.G.; Blewett, G.R.; Troyer, G.L.

1994-05-01

51

Long-term surveillance plan for the Cheney disposal site near Grand Junction, Colorado  

SciTech Connect

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 Cheney disposal site. The site is in Mesa County near Grand Junction, 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 are cared for in a manner that protects public health and safety and the environment. Before each disposal site may be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Cheney disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete and the NRC formally accepts this plan. This document describes the long-term surveillance program the DOE will implement to ensure that the Cheney disposal site performs as designed. The program is based on site inspections to identify potential threats to disposal cell integrity. 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.

NONE

1997-04-01

52

Long-term surveillance plan for the Maybell, Colorado Disposal Site  

SciTech Connect

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 Maybell disposal site in Moffat 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 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 Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1997-09-01

53

Long-term surveillance plan for the South Clive Disposal Site, Clive, Utah  

SciTech Connect

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 South Clive disposal site in Clive, Utah. 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 CRF 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 South Clive disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the South Clive site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the South Clive disposal site performs as designed. The program`s primary activity is site inspections to identify threats to disposal cell integrity.

NONE

1996-03-01

54

Identification of sites for the low-level waste disposal development and demonstration program  

Microsoft Academic Search

This report presents the results of site selection studies for potential low-level radioactive waste disposal sites on the Oak Ridge Reservation (ORR). Summaries of the site selection procedures used and results of previous site selection studies on the ORR are included. This report includes recommendations of sites for demonstration of shallow land burial using engineered trench designs and demonstration of

R. H. Ketelle; D. W. Lee

1988-01-01

55

40 CFR 228.9 - Disposal site monitoring.  

Code of Federal Regulations, 2013 CFR

...agencies, or contractors, special studies by permittees, and the analysis and interpretation of data from remote or automatic sampling and/or sensing devices. The primary purpose of the monitoring program is to evaluate the impact of disposal...

2013-07-01

56

Long-term surveillance plan for the Estes Gulch disposal site near Rifle, Colorado  

SciTech Connect

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 Estes Gulch disposal site near Rifle, Colorado. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Estes Gulch disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP.

NONE

1997-07-01

57

40 CFR 61.151 - Standard for inactive waste disposal sites for asbestos mills and manufacturing and fabricating...  

Code of Federal Regulations, 2010 CFR

...for inactive waste disposal sites for asbestos mills and manufacturing and fabricating...POLLUTANTS National Emission Standard for Asbestos § 61.151 Standard for inactive waste disposal sites for asbestos mills and manufacturing and...

2010-07-01

58

15 CFR Appendix B to Subpart M of... - Dredged Material Disposal Sites Adjacent to the Monterey Bay National Marine Sanctuary  

Code of Federal Regulations, 2010 CFR

...false Dredged Material Disposal Sites Adjacent to the... Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) NATIONAL...Dredged Material Disposal Sites Adjacent to the...and within one of three study areas described in...

2009-01-01

59

Water sampling and disposal apparatus for an offshore operating site  

SciTech Connect

Apparatus is disclosed for sampling and disposing of water which has been separated from a water polluting element, the latter being lighter than the water. The apparatus includes an elongated upright caisson or pile which is disposed in a body of water, and which is adapted to contain a quantity of the water as well as the pollutant element. A submerged sampling apparatus is positioned at the lower end of the caisson and is actuated by gas pressure controlled from the water's surface to periodically withdraw a measured sample of the pollutant free water to assure its purity.

Leboeuf, H.P.

1982-05-18

60

Radioactive waste disposal in Germany: no site decision - Keeping competence  

SciTech Connect

The research programme of the Institut fuer Nukleare Entsorgung (INE) at the Forschungszentrum Karlsruhe is dedicated to elaborate the fundamental understanding of radionuclide/actinide interactions with various components of the groundwater and with the relevant host rock materials at disposal relevant trace concentrations. INE's research programme was not biased after enactment of the Gorleben moratorium in 2001. This paper presents current R and D with respect to application in performance assessment/safety case of nuclear waste disposal. Focus is given to the leading role of the institute in various projects within EU framework programmes. (authors)

Kienzler, Bernhard; Geckeis, Horst; Gompper, Klaus; Klenze, Reinhardt [Forschungszentrum Karlsruhe, Institut fuer Nukleare Entsorgung - INE, Postfach 3640, 76021 Karlsruhe (Germany)

2007-07-01

61

Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado  

SciTech Connect

This long-term surveillance plan (LTSP) for the Durango, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Durango (Bodo Canyon) disposal site, which will be referred to as the disposal site throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). RRMs include tailings and other uranium ore processing wastes still at the site, which the DOE determines to be radioactive. This LTSP is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992).

Not Available

1994-03-01

62

Disposal site-selection technical appendix. Phase 2. (North and South Puget Sound)  

Microsoft Academic Search

This document is a technical appendix to both the Proposed Management Plan Report and the Environmental Impact Statement (EIS) for the Puget Sound Dredged Disposal Analysis (PSDDA) Phase II study covering north and south Puget Sound. Results of disposal-site-selection studies for Phase II of PSDDA, are summarized herein. Phase II includes the southern portion of Puget Sound south of the

D. Kendall; D. Jamison; J. Malek; P. Ehlers

1989-01-01

63

Hydrogeologic investigation at a waste disposal site in northern New Jersey  

Microsoft Academic Search

A hydrogeologic investigation was performed near a waste disposal site in northern New Jersey to determine the adverse effects of past waste disposal activities on local groundwater. Major elements of the investigation included drilling, well installations, aquifer testing, and groundwater sampling. Two groundwater flow systems within glacial drift deposits and two within bedrock were identified and characterized during the study.

Orient

1990-01-01

64

Management and disposal of waste from sites contaminated by radioactivity  

NASA Astrophysics Data System (ADS)

Various methods of managing and disposing of wastes generated by decontamination and decommissioning (D & D) activities are described. This review of current waste management practices includes a description of waste minimization and volume reduction techniques and their applicability to various categories of radwaste. The importance of the physical properties of the radiation and radioactivity in determining the methodology of choice throughout the D & D process is stressed. The subject is introduced by a survey of the common types of radioactive contamination that must be managed and the more important hazards associated with each type. Comparisons are made among high level, transuranic, low level, and radioactive mixed waste, and technologically-enhanced, naturally-occurring radioactive material (TENORM). The development of appropriate clean-up criteria for each category of contaminated waste is described with the aid of examples drawn from actual practice. This includes a discussion of the application of pathway analysis to the derivation of residual radioactive material guidelines. The choice between interim storage and permanent disposal of radioactive wastes is addressed. Approaches to permanent disposal of each category of radioactive waste are described and illustrated with examples of facilities that have been constructed or are planned for implementation in the near future. Actual experience at older, existing, low-level waste disposal facilities is discussed briefly.

Roberts, Carlyle J.

1998-06-01

65

Management and disposal of waste from sites contaminated by radioactivity  

Microsoft Academic Search

Various methods of managing and disposing of wastes generated by decontamination and decommissioning (D & D) activities are described. This review of current waste management practices includes a description of waste minimization and volume reduction techniques and their applicability to various categories of radwaste. The importance of the physical properties of the radiation and radioactivity in determining the methodology of

C. J. Roberts

1998-01-01

66

DREDGED MATERIAL TRANSPORT AT DEEP-OCEAN DISPOSAL SITES  

EPA Science Inventory

Assessment of environmental impact of dredged material disposal in deep ocean water calls for predictions of water column concentration, exposure time as well as the impacted area of the bottom (footprint). redictions based on vertical willing and horizontal advection of single p...

67

Mitigation action plan for remedial action at the Uranium Mill Tailing Sites and Disposal Site, Rifle, Colorado  

SciTech Connect

The Estes Gulch disposal site is approximately 10 kilometers (6 miles) north of the town of Rifle, off State Highway 13 on Federal land administered by the Bureau of Land Management. The Department of Energy (DOE) will transport the residual radioactive materials (RRM) by truck to the Estes Gulch disposal site via State Highway 13 and place it in a partially below-grade disposal cell. The RRM will be covered by an earthen radon barrier, frost protection layers, and a rock erosion protection layer. A toe ditch and other features will also be constructed to control erosion at the disposal site. After removal of the RRM and disposal at the Estes Gulch site, the disturbed areas at all three sites will be backfilled with clean soils, contoured to facilitate surface drainage, and revegetated. Wetlands areas destroyed at the former Rifle processing sites will be compensated for by the incorporation of now wetlands into the revegetation plan at the New Rifle site. The UMTRA Project Office, supported by the Remedial Action Contractor (RAC) and the Technical Assistance Contractor (TAC), oversees the implementation of the MAP. The RAC executes mitigation measures in the field. The TAC provides monitoring of the mitigation actions in cases where mitigation measures are associated with design features. Site closeout and inspection compliance will be documented in the site completion report.

Not Available

1992-07-01

68

Dose and risk assessment for intrusion into mixed waste disposal sites.  

National Technical Information Service (NTIS)

Sites previously used for disposal of radioactive and hazardous chemical materials have resulted in situations that pose a potential threat to humans from inadvertent intrusion. An example generic scenario analysis was developed to demonstrate the evaluat...

W. E. Kennedy R. L. Aaberg

1991-01-01

69

Project Summary: Alternative Onsite Wastewater Treatment and Disposal Systems on Severely Limited Sites.  

National Technical Information Service (NTIS)

Several research and evaluation studies were performed on alternative onsite wastewater treatment and disposal systems at sites with severe limitations for conventional systems. The soil properties, soil moisture regime, and shallow groundwater table at t...

M. M. Cashell D. D. Effert J. M. Morand

1987-01-01

70

LINERS FOR SANITARY LANDFILLS AND CHEMICAL AND HAZARDOUS WASTE DISPOSAL SITES  

EPA Science Inventory

This report lists addresses of sanitary landfills and chemical and hazardous waste disposal sites and holding ponds with some form of impermeable lining. Liners included are polyethylene, polyvinyl chloride, Hypalon R, ethylene propylene diene monomer, butyl rubber, conventional ...

71

Long-term surveillance plan for the Collins Ranch Disposal Site, Lakeview, Oregon. Revision 2  

SciTech Connect

This long-term surveillance plan (LTSP) for the Lakeview, Oregon, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Lakeview (Collins Ranch) disposal cell, which will be referred to as the Collins Ranch disposal cell throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States or an Indian tribe, and details how the long-term care of the disposal site will be carried out. It is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a).

Not Available

1993-12-01

72

Mapping of soil nutrients in an abandoned Chinese coal mine and waste disposal site  

Microsoft Academic Search

The present paper attempts to identify the spatial patterns of soil nutrients in the abandoned Haizhou opencast coal mine and waste disposal site, in China. A geostatistical approach was used to overcome problems due to the heterogeneity of the site (some parts have been abandoned for more than 30years, lack of clean soil, presence of overburden and low-grade ore, co-disposal

Kostas Komnitsas; Xiangyun Guo; Daoliang Li

2010-01-01

73

Siting Study for the Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect

The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

2010-10-01

74

Engineering geological aspects of replacing a solid waste disposal site with a sanitary landfill  

Microsoft Academic Search

The current solid waste disposal site in the Mamak district of Ankara is being engulfed by the growing city. All varieties of solid wastes, including medical wastes, are stored at the present site in an irregular manner. Topographical and geological conditions at Mamak waste site are favorable for constructing a sanitary landfill. Located at the edge of a topographical depression,

Kamil Kayabali

1996-01-01

75

A Probabilistic Performance Assessment Study of Potential Low-Level Radioactive Waste Disposal Sites in Taiwan  

Microsoft Academic Search

For several years now, Taiwan has been engaged in a process to select a low-level radioactive waste (LLW) disposal site. Taiwan is generating LLW from operational and decommissioning wastes associated with nuclear power reactors, as well as research, industrial, and medical radioactive wastes. The preliminary selection process has narrowed the search to four potential candidate sites. These sites are to

R. G. Knowlton; B. W. Arnold; P. D. Mattie; M. Kuo; N. Tien

2006-01-01

76

Navajo birth outcomes in the Shiprock uranium mining area  

SciTech Connect

The role of environmental radiation in the etiology of birth defects, stillbirths, and other adverse outcomes of pregnancy was evaluated for 13,329 Navajos born at the Public Health Service/Indian Health Service Hospital in the Shiprock, NM, uranium mining area (1964-1981). More than 320 kinds of defective congenital conditions were abstracted from hospital records. Using a nested case-control design, families of 266 pairs of index and control births were interviewed. The only statistically significant association between uranium operations and unfavorable birth outcome was identified with the mother living near tailings or mine dumps. Among the fathers who worked in the mines, those of the index cases had histories of more years of work exposure but not necessarily greater gonadal dosage of radiation. Also, birth defects increased significantly when either parent worked in the Shiprock electronics assembly plant. Overall, the associations between adverse pregnancy outcome and exposure to radiation were weak and must be interpreted with caution with respect to implying a biogenetic basis.

Shields, L.M.; Wiese, W.H.; Skipper, B.J.; Charley, B.; Benally, L. (Navajo Community College, Shiprock, NM (United States))

1992-11-01

77

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

SciTech Connect

This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Falls City disposal site, Falls City, Texas, describes the surveillance activities for the disposal site. DOE will carry out these activities to ensure that the disposal cell continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States and details how long-term care of the disposal site will be carried out. It is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a).

NONE

1995-06-01

78

Long-term Surveillance Plan for the Falls City Disposal Site, Falls City, Texas. Revision 1  

SciTech Connect

This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Falls City disposal site, Falls City, Texas, describes the surveillance activities for the disposal site. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States and details how long-term care of the disposal site will be carried out. It is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a).

NONE

1995-08-01

79

Radioactive waste disposal sites: Two successful closures at Tinker Air Force Base  

SciTech Connect

This article describes remediation and closure of two radioactive waste disposal sites at Tinker Air Force Base, Oklahoma, making them exemption regulatory control. The approach consisted of careful exhumation and assessment of soils in sites expected to be contaminated based on historical documentation, word of mouth, and geophysical surveys; removal of buried objects that had gamma radiation exposure levels above background; and confirmation that the soil containing residual radium-226 was below an activity level equal to no more than a 10 mrem/yr annual dose equivalent. In addition, 4464 kg of chemically contaminated excavated soils were removed for disposal. After remediation, the sites met standards for unrestricted use. These sites were two of the first three Air Force radioactive disposal sites to be closed and were the first to be closed under Draft NUREG/CR-5512.

McKenzie, G.; Mohatt, J.V.; Kowall, S.J.; Jarvis, M.F.

1993-06-01

80

Health effects of hazardous chemical waste disposal sites in New Jersey and in the United States: a review  

Microsoft Academic Search

The hazardous chemical waste disposal issue is a widespread problem. Large quantities of chemical wastes have been produced by the chemical industries in the past forty years. Estimates now number disposal sites in the United States at least 30,000. The public and scientists have grown increasingly concerned about the effects of these waste disposal sites not only on the environment,

G. R. Najem; J. L. Cappadona

1991-01-01

81

Long-Term Performance of Transuranic Waste Inadvertently Disposed in a Shallow Land Burial Trench at the Nevada Test Site  

Microsoft Academic Search

In 1986, 21 m3 of transuranic (TRU) waste was inadvertently disposed in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site. U.S. Department of Energy (DOE) TRU waste must be disposed in accordance with Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standard for Management and Disposal

Gregory J. Shott; Vefa Yucel

2009-01-01

82

Utilizing a Chirp Sonar to Accurately Characterize Newly Deposited Material at the Calcasieu Ocean Dredged Material Disposal Site, Louisiana.  

National Technical Information Service (NTIS)

The distribution of dredged sediments is measured at the Calcasieu Ocean Dredged Material Disposal Site (ODMDS) using a chirp sonar immediately after disposal and two months later. Subbottom reflection data, generated by a chirp sonar transmitting a 4 to ...

S. G. Schock D. J. Keith D. L. Debruin E. Dettmann G. Tracey

1992-01-01

83

Remediation of a Former USAF Radioactive Material Disposal Site.  

National Technical Information Service (NTIS)

This paper describes the remediation of a low-level radiological waste burial site located at the former James Connally Air Force Base in Waco, Texas. Burial activities at the site occurred during the 1950's when the property was under the ownership of th...

D. E. Hoffman B. Tupyi J. Lambert

2003-01-01

84

Surface-water hydrology at three coal-refuse disposal sites in southern Illinois: Staunton 1, New Kathleen, and Superior  

Microsoft Academic Search

Hydrologic data were collected and analyzed for three coal refuse disposal sites in southern Illinois. The disposal sites were associated with underground mines and consisted of piles of coarse waste (gob) and slurry areas where fine waste rejected from coal washing was deposited. Prereclamation data were available for the Superior washer site in Macoupin County and the New Kathleen site

L. M. Mele; P. F. Prodan

1983-01-01

85

Low level radioactive waste disposal\\/treatment technology overview: Savannah River site  

Microsoft Academic Search

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,

Sturm; H. F. Jr

1987-01-01

86

Native Plant Uptake Model for Radioactive Waste Disposal Areas at the Nevada Test Site  

Microsoft Academic Search

This report defines and defends the basic framework, methodology, and associated input parameters for modeling plant uptake of radionuclides for use in Performance Assessment (PA) activities of Radioactive Waste Management Sites (RWMS) at the Nevada Test Site (NTS). PAs are used to help determine whether waste disposal configurations meet applicable regulatory standards for the protection of human health, the environment,

THERESA J. BROWN; SHARON WIRTH

1999-01-01

87

Environmental geological assessment of a solid waste disposal site: a case study in Sivas, Turkey  

NASA Astrophysics Data System (ADS)

The selection of the disposal site is probably the most important step in the development of solid waste management. In site selection, geology plays a determining role. This study evaluates the characteristics of the environment on the basis of the geological, hydrogeological and geo-engineering properties of the solid waste site of the Sivas city, Turkey. The area is underlain by the Oligocene-Miocene rocks which have limited aquifer properties. Thin Quaternary alluvium and soil cover overlie the Oligo-Miocene rocks, which are represented as well graded sand and inorganic silt of low plasticity. The Quaternary alluvium and soil cover are classified as inorganic clays having a low plasticity and the permeability varies from 1.210-6 to 3.1110-6 m/s. These values are much higher than 110-8 m/s, which is accepted for waste disposal standards. Seepage waters have a potential to pollute the ground water and the K?z?l?rmak River, which is 500 m to the southwest of the waste disposal area and because the disposal site is close to the river, the potential for flash flooding poses a high pollution risk. The waste disposal area must be covered by clay layers or an impervious artificial membrane. In addition, seepage must be controlled and removed from the site.

Y?lmaz, A.; Atmaca, E.

2006-07-01

88

Long-term surveillance plan for the Lowman, Idaho, disposal site  

SciTech Connect

The long-term surveillance plan (LTSP) for the Lowman, Idaho, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Lowman disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This preliminary final LTSP is being submitted to the US Nuclear Regulatory Commission (NRC) as a requirement for issuance of a general license for custody and long-term care for the disposal site. The general license requires that the disposal cell be cared for in accordance with the provisions of this LTSP. The LTSP documents whether the land and interests are owned by the United States or an Indian tribe, and describes, in detail, how the long-term care of the disposal site will be carried out through the UMTRA Project long-term surveillance program. The Lowman, Idaho, LTSP is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program, (DOE, 1992).

Not Available

1993-09-01

89

A data base for low-level radioactive waste disposal sites  

SciTech Connect

A computerized database was developed to assist the US Environmental Protection Agency (EPA) in evaluating methods and data for characterizing health hazards associated with land and ocean disposal options for low-level radioactive wastes. The data cover 1984 to 1987. The types of sites considered include Nuclear Regulatory Commission (NRC) licensed commercial disposal sites, EPA National Priority List (NPL) sites, US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Project (FUSRAP) and DOE Surplus Facilities Management Program (SFMP) sites, inactive US ocean disposal sites, and DOE/Department of Defense facilities. Sources of information include reports from EPA, the US Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC), as well as direct communication with individuals associated with specific programs. The data include site descriptions, waste volumes and activity levels, and physical and radiological characterization of low-level wastes. Additional information on mixed waste, packaging forms, and disposal methods were compiled, but are not yet included in the database. 55 refs., 4 figs., 2 tabs.

Daum, M.L.; Moskowitz, P.D.

1989-07-01

90

Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado. Revision 1  

SciTech Connect

This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Act on (UMTRA) Project Bodo Canyon disposal site at Durango, Colorado, describes the surveillance activities for the disposal site. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal call continues to function as designed This LTSP was prepared as a requirement for DOE acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM) from processing uranium ore. This LTSP documents that the land and interests are owned by the United States and details how long-term care of the disposal site will be carried out. It is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a). Following the introduction, contents of this report include the following: site final condition; site drawings and photographs; permanent site surveillance features; ground water monitoring; annual site inspections; unscheduled inspections; custodial maintenance; corrective action; record keeping and reporting requirements; emergency notification and reporting; quality assurance; personal health and safety; list of contributions; and references.

NONE

1995-11-01

91

Transport Assessment and Cost Analysis of the Shipment of M55 Rockets to Possible Disposal Sites. M55 Rocket Disposal Program Study: M55-CD-1.  

National Technical Information Service (NTIS)

The US Army is currently studying ways to dispose of M55 rockets. This report identifies the methods that are available to transport the rockets to disposal sites from three storage Depots (the Anniston Army Depot, the Kentucky-Blue Grass Depot, and the U...

L. B. Shappert D. S. Joy J. M. Begovich I. G. Harrison

1985-01-01

92

NWTS program criteria for mined geologic disposal of nuclear wasite: site performance criteria  

SciTech Connect

This report states ten criteria governing the suitability of sites for mined geologic disposal of high-level radioactive waste. The Department of Energy will use these criteria in its search for sites and will reevaluate their use when the Nuclear Regulatory Commission issues radioactive waste repository rules. These criteria encompass site geometry, geohydrology, geochemistry, geologic characteristics, tectonic environment, human intrusion, surface characteristics, environment, and potential socioeconomic impacts. The contents of this document include background discussion, site performance criteria, and appendices. The background section describes the waste disposal system, the application of the site criteria, and applicable criteria from NWTS-33(1) - Program Objectives, Functional Requirements and System Performance Criteria. Appendix A, entitled Comparison with Other Siting Criteria compares the NWTS criteria with those recommended by other agencies. Appendix B contains DOE responses to public comments received on the January 1980 draft of this document. Appendix C is a glossary.

None

1981-02-01

93

43 CFR 2743.3 - Leased disposal sites.  

Code of Federal Regulations, 2013 CFR

...lease and any violations and enforcement problems that occurred during the term of the...Consultation with the lessee and users of the landfill concerning site management and a review...amount of solid waste deposited at the landfill; (iii) A visual inspection of...

2013-10-01

94

Site Selection Experience for a New Low-Level Radioactive Waste Storage/Disposal Facility at the Savannah River Plant.  

National Technical Information Service (NTIS)

Preliminary performance criteria and site selection guides specific to the Savannah River Plant, were developed for a new low-level radioactive waste storage/disposal facility. These site selection guides were applied to seventeen potential sites identifi...

O. A. Towler J. R. Cook B. D. Helton

1985-01-01

95

Long-term surveillance plan for the Tuba City, Arizona disposal site  

SciTech Connect

This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site at Tuba City, Arizona, describes the site surveillance activities. The U.S. Department of Energy (DOE) will carry out these activities to ensure the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM) (10 CFR {section}40.27).

NONE

1996-02-01

96

Selected hydrologic data from a wastewater spray disposal site on Hilton Head Island, South Carolina  

USGS Publications Warehouse

This study presents data collected during a study of the effects on the water table aquifer from wastewater application at rates of up to 5 inches per week on a wastewater spray disposal site on Hilton Head Island, South Carolina. The study was conducted from April 1982 through December 1983. The disposal site covers approximately 14 acres. Water level and water quality data from organic, inorganic, and nutrient analyses from the water table aquifer to a depth of 30 ft and similar water quality data from the wastewater treatment plant are included. (USGS)

Speiran, G. K.; Belval, D. L.

1985-01-01

97

COMPLETION OF THE TRANSURANIC GREATER CONFINEMENT DISPOSAL BOREHOLE PERFORMANCE ASSESSMENT FOR THE NEVADA TEST SITE  

SciTech Connect

Classified transuranic material that cannot be shipped to the Waste Isolation Pilot Plant in New Mexico is stored in Greater Confinement Disposal boreholes in the Area 5 Radioactive Waste Management Site on the Nevada Test Site. A performance assessment was completed for the transuranic inventory in the boreholes and submitted to the Transuranic Waste Disposal Federal Review Group. The performance assessment was prepared by Sandia National Laboratories on behalf of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office using an iterative methodology that assessed radiological releases from the intermediate depth disposal configuration against the regulatory requirements of the 1985 version of 40 CFR 191 of the U.S. Environmental Protection Agency. The transuranic materials are stored at 21 to 37 m depth (70 to 120 ft) in large diameter boreholes constructed in the unsaturated alluvial deposits of Frenchman Flat. Hydrologic processes that affect long- term isolation of the radionuclides are dominated by extremely slow upward rates of liquid/vapor advection and diffusion; there is no downward pathway under current climatic conditions and there is no recharge to groundwater under future ''glacial'' climatic conditions. A Federal Review Team appointed by the Transuranic Waste Disposal Federal Review Group reviewed the Greater Confinement Disposal performance assessment and found that the site met the majority of the regulatory criteria of the 1985 and portions of the 1993 versions of 40 CFR 191. A number of technical and procedural issues required development of supplemental information that was incorporated into a final revision of the performance assessment. These issues include inclusion of radiological releases into the complementary cumulative distribution function for the containment requirements associated with drill cuttings from inadvertent human intrusion, verification of mathematical models used in the performance assessment, inclusion of dose calculations from collocated low-level waste in the boreholes for the individual protection requirements, further assessments of engineered barriers and conditions associated with the assurance requirements, and expansion of documentation provided for assessing the groundwater protection requirements. The Transuranic Waste Disposal Federal Review Group approved the performance assessment for Greater Confinement Disposal boreholes in 2001 and did not approve the Application of the Assurance Requirements. Remaining issues concerned with engineered barriers and the multiple aspects of the Assurance Requirements will be resolved at the time of closure of the Area 5 Radioactive Waste Management Site. This is the first completion and acceptance of a performance assessment for transuranic materials under the U.S. Department of Energy self-regulation. The Greater Confinement Disposal boreholes are only the second waste disposal configuration to meet the safety regulatory requirements of 40 CFR 191.

Colarusso, Angela; Crowe, Bruce; Cochran, John R.

2003-02-27

98

Utilizing gamma isotope tracers to determine sediment source at reef sites near the Charleston Ocean Dredged Material Disposal Site.  

PubMed

The Charleston, South Carolina Ocean Dredged Material Disposal Site (ODMDS) has been heavily utilized as a disposal site for dredged material resulting from maintenance and channel deepening in the Charleston Harbor. Continuous monitoring by the South Carolina Department of Natural Resources at the ODMDS has indicated the presence of fine-grained sediment within the monitoring zones. However, since the Charleston Harbor is formed by the conjunction of three rivers, it has been suggested that some of the fine-grained sediment surrounding the ODMDS could be due to river transport rather than solely by disposal activities. In order to trace the outflow of sediment from the harbor, natural and man-made isotopes were utilized. (7)Be (natural cosmogenic isotope) and (137)Cs (man-made isotope) are often associated with estuarine sediments. Both isotopes were used as tracers in an attempt to determine the extent of density driven sediment flow from the Charleston Harbor. (7)Be was detected in many of the offshore sampling stations indicating a direct correlation to the harbor. (137)Cs was only found in one sediment trap sample offshore, but none the less indicated some transport from the harbor. Further study for utilizing isotopic tracers in determining offshore sediment transport is still being conducted at the disposal site. It is anticipated that further (7)Be and (137)Cs isotopic monitoring offshore Charleston will aid in determining the role that tidal and density driven sediments play in the sediment budgets at the hard bottom reef sites. PMID:16359711

Noakes, Scott E; Jutte, Pamela C

2006-06-01

99

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

National Technical Information Service (NTIS)

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 t...

1994-01-01

100

Evaluation of groundwater monitoring results at the Hanford Site 200 Area Treated Effluent Disposal Facility  

Microsoft Academic Search

The Hanford Site 200 Area Treated Effluent Disposal Facility (TEDF) has operated since June 1995. Groundwater monitoring has been conducted quarterly in the three wells surrounding the facility since 1992, with contributing data from nearby B Pond System wells. Cumulative hydrologic and geochemical information from the TEDF well network and other surrounding wells indicate no discernable effects of TEDF operations

Barnett

1998-01-01

101

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

USGS Publications Warehouse

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.

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

1988-01-01

102

Water quality impacts from on-site waste disposal systems to coastal areas through groundwater discharge  

Microsoft Academic Search

This report summarizes research studies linking on-site waste disposal systems (OSDS) to pathogen and nutrient concentrations in groundwater with the potential to impact coastal embayments. Few studies connect OSDS to coastal water quality. Most studies examined pathogen and nutrient impacts to groundwater and omitted estimations of contaminants discharged to surface water. The majority of studies focused on nitrogen, with little

P. J. Harris

1995-01-01

103

NEAR-BOTTOM PELAGIC BACTERIA AT A DEEP-WATER SEWAGE SLUDGE DISPOSAL SITE  

EPA Science Inventory

The epibenthic bacterial community at deep-ocean sewage sludge disposal site DWD-106, located approximately 106 miles (ca. 196 km) off the coast of New Jersey, was assessed for changes associated with the introduction of large amounts of sewage sludge. ixed cultures and bacterial...

104

Hydrologic study and evaluation of Ish Creek watershed (West Chestnut Ridge proposed disposal site)  

Microsoft Academic Search

As part of site characterization work for the proposed West Chestnut Ridge Central Waste Disposal Facility, hydrologic information has been assembled from literature sources and direct field measurements. Earlier studies provide the basis for estimating flow frequency and expected high and low flows for catchments on Knox Group formations. Seven waterflow-gaging installations were established and used to characterize runoff patterns

D. D. Huff; J. L. Elmore; D. C. Farmer

1984-01-01

105

Site selection for waste disposal through Spatial Multiple Criteria Decision Analysis by  

Microsoft Academic Search

This article deals with the application of spatial multiple criteria evaluation concepts and methods to support the decision-making process for site selection for waste disposal. The process makes use of a recently developed Spatial Multiple Criteria Evaluation (SMCE) module, integrated into ITC's existing geographic information system called \\

M. A. Sharifi; V. Retsios

2003-01-01

106

Analysis of Core Soil and Water Samples from the Cactus Crater Disposal Site at Enewetak Atoll.  

National Technical Information Service (NTIS)

Core soil samples and water samples were collected from the Cactus Crater Disposal Site at Enewetak for analysis of exp 137 Cs, exp 90 Sr, exp 239+240 Pu and exp 241 Am by both gamma spectroscopy and, through a contractor laboratory, by wet chemistry proc...

W. L. Robison V. E. Noshkin

1981-01-01

107

Revised Procedural Guide For Designation Surveys of Ocean Dredged Material Disposal Sites  

National Technical Information Service (NTIS)

This procedural guide is a revision of that issued in 1981 and has been prepared to meet the needs of the Corps of Engineers in conducting surveys for the designation of ocean disposal sites for dredged material. Basic purposes of the guide are to provide...

B. J. Gallaway T. D. Wright W. E. Pequegnat

1990-01-01

108

TRACE METALS IN SCALLOPS FROM WITHIN AND AROUND TWO OCEAN DISPOSAL SITES  

EPA Science Inventory

The areal distributions of the concentrations of 13 metals in sea scallop tissues were examined in the vicinity of two ocean disposal sites located off the U.S. mid-Atlantic coast. Patterns of metals distribution show that: (1) Five specific metals may be used as identification t...

109

RESTORATION OF FAILING ON-SITE WASTEWATER DISPOSAL SYSTEMS USING WATER CONSERVATION  

EPA Science Inventory

A study was made to determine the ability of existing water conservation hardware to correct malfunctioning on-site wastewater disposal systems resulting from soil clogging and to document, under actual use conditions, possible reduction of wastewater with water conservation hard...

110

NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147  

SciTech Connect

As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in coordination with South Carolina Department of Health and Environmental Control (SCDHEC). DOE has completed or begun additional work related to salt waste disposal to address these factors. NRC staff continues to evaluate information related to the performance of the SDF and has been working with DOE and SCDHEC to resolve NRC staff's technical concerns. (authors)

Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D. [U.S. Nuclear Regulatory Commission (United States)] [U.S. Nuclear Regulatory Commission (United States)

2013-07-01

111

Modeling contaminant migration from a mixed-waste disposal site: Studies of controlling factors and processes  

Microsoft Academic Search

The Radioactive Waste Management Complex (RWMC) is located in the southwestern part of the Idaho National Engineering Laboratory in southeastern Idaho. Since the mid-1950s, the RWMC has served as a low-level and transuranic (TRU) waste disposal site. It is currently estimated that 180,000 m³ of solid waste has been buried at the site. Early modeling studies of contaminant migration concluded

R. G. Baca; J. C. Walton; R. R. Piscitella

1989-01-01

112

A multiattribute utility analysis of alternative sites for the disposal of nuclear waste.  

PubMed

Five potential sites nominated for the Nation's first geologic repository for disposing of nuclear waste are evaluated using multiattribute utility analysis. The analysis was designed to aid the Department of Energy in its selection of 3 sites for characterization, a detailed data-gathering process that will involve the construction of exploratory shafts for underground testing and that may cost as much as $1 billion per site. The analysis produced insights into the relative advantages and disadvantages of the nominated sites and clarified current uncertainties regarding repository performance. PMID:3615998

Merkhofer, M W; Keeney, R L

1987-06-01

113

Methodology for selecting low-level radioactive waste disposal sites with application to the Oak Ridge Reservation. [Shallow land burial  

Microsoft Academic Search

A methodology was developed to select an environmentally acceptable site for low-level radioactive waste disposal for a predetermined region of interest using prescribed site suitability requirements. The methodology provides a defensible means for identifying candidate areas within the region, candidate sites within the areas, and an environmentally preferred site from the candidate sites. This is accomplished in site screening and

D. W. Lee; R. H. Ketelle

1984-01-01

114

Should high-level nuclear waste be disposed of at geographically dispersed sites?  

SciTech Connect

Consideration of the technical feasibility of Yucca Mountain in Nevada as the site for a high-level nuclear waste repository has led to an intense debate regarding the economic, social, and political impacts of the repository. Impediments to the siting process mean that the nuclear waste problem is being resolved by adhering to the status quo, in which nuclear waste is stored at scattered sites near major population centers. To assess the merits of alternative siting strategies--including both the permanent repository and the status quo- we consider the variables that would be included in a model designed to select (1) the optimal number of disposal facilities, (2) the types of facilities (e.g., permanent repository or monitored retrievable facility), and (3) the geographic location of storage sites. The objective function in the model is an all-inclusive measure of social cost. The intent of the exercise is not to demonstrate the superiority of any single disposal strategy; uncertainties preclude a conclusive proof of optimality for any of the disposal options. Instead, we want to assess the sensitivity of a variety of proposed solutions to variations in the physical, economic, political, and social variables that influence a siting strategy.

Bassett, G.W. Jr. [Chicago Univ., IL (United States). Dept. of Economics; Hemphill, R.; Kohout, E. [Argonne National Lab., IL (United States)

1992-07-01

115

Small mammal populations at hazardous waste disposal sites near Houston, Texas, USA  

USGS Publications Warehouse

Small mammals were trapped, tagged and recaptured in 0?45 ha plots at six hazardous industrial waste disposal sites to determine if populations, body mass and age structures were different from paired control site plots. Low numbers of six species of small mammals were captured on industrial waste sites or control sites. Only populations of hispid cotton rats at industrial waste sites and control sites were large enough for comparisons. Overall population numbers, age structure, and body mass of adult male and female cotton rats were similar at industrial waste sites and control sites. Populations of small mammals (particularly hispid cotton rats) may not suffice as indicators of environments with hazardous industrial waste contamination.

Flickinger, E.L.; Nichols, J.D.

1990-01-01

116

Aquatic Disposal Field Investigations Duwamish Waterway Disposal Site Puget Sound, Washington. Appendix D. Chemical and Physical Analyses of Water and Sediment in Relation to Disposal of Dredged Material in Elliott Bay. Volume I. February-June 1976.  

National Technical Information Service (NTIS)

A study was conducted on the chemical and physical effects of open-water disposal of dredged material from the Duwamish River into Elliott Bay, Washington. The water column at the disposal and reference sites was monitored during and after the dredged mat...

D. J. Baumgartner D. W. Shults J. B. Carkin

1978-01-01

117

Development of a prototype plan for the effective closure of a waste disposal site in Los Alamos, New Mexico  

Microsoft Academic Search

The purpose of this study was to develop a prototype plan for the effective closure and stabilization of a semiarid low-level waste disposal site. This prototype plan will provide demonstrated closure techniques for a trench in a disposal site at Los Alamos based on previous shallow land burial (SLB) field research both at the Los Alamos Experimental Engineered Test Facility

J. Nyhan; F. Barnes

1989-01-01

118

Classified Component Disposal at the Nevada National Security Site (NNSS) - 13454  

SciTech Connect

The Nevada National Security Site (NNSS) has added the capability needed for the safe, secure disposal of non-nuclear classified components that have been declared excess to national security requirements. The NNSS has worked with U.S. Department of Energy, National Nuclear Security Administration senior leadership to gain formal approval for permanent burial of classified matter at the NNSS in the Area 5 Radioactive Waste Management Complex owned by the U.S. Department of Energy. Additionally, by working with state regulators, the NNSS added the capability to dispose non-radioactive hazardous and non-hazardous classified components. The NNSS successfully piloted the new disposal pathway with the receipt of classified materials from the Kansas City Plant in March 2012. (authors)

Poling, Jeanne; Arnold, Pat [National Security Technologies, LLC (NSTec), P.O. Box 98521, Las Vegas, NV 89193-8521 (United States)] [National Security Technologies, LLC (NSTec), P.O. Box 98521, Las Vegas, NV 89193-8521 (United States); Saad, Max [Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States)] [Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); DiSanza, Frank [E. Frank DiSanza Consulting, 2250 Alanhurst Drive, Henderson, NV 89052 (United States)] [E. Frank DiSanza Consulting, 2250 Alanhurst Drive, Henderson, NV 89052 (United States); Cabble, Kevin [U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, P.O. Box 98518, Las Vegas, NV 89193-8518 (United States)] [U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, P.O. Box 98518, Las Vegas, NV 89193-8518 (United States)

2013-07-01

119

Audit of the deactivation, decontamination, and disposal of surplus facilities at the Savannah River Site  

SciTech Connect

Westinghouse Savannah River Company (Westinghouse) is responsible for managing the Department of Energy`s (Department) surplus facilities at the Savannah River Site (Site). In Fiscal Year (FY) 1996, the Site had 162 surplus facilities and anticipated that 118 more would become surplus within the next 5 years. The objective of this audit was to determine whether the Savannah River Operations Office (Operations Office) and Westinghouse had economically and promptly deactivated, decontaminated, and disposed of surplus facilities at the Site. Departmental regulations require that surplus facilities be deactivated, decontaminated, and disposed of economically and promptly. However, Westinghouse only disposed of one facility and did not completely deactivate or decontaminate any of the 162 facilities identified as surplus at the Site in FY 1996. This occurred because the Operations Office did not compile a Site-wide list, establish priorities, or provide sufficient funding for the deactivation, decontamination, and disposal of surplus facilities. As a result, the Department incurred unnecessary costs for the surveillance and maintenance of surplus facilities. For example, the Department could have avoided annual costs of about $1.3 million in surveillance and maintenance costs by spending $1.2 million to perform a deactivation project on the P-Reactor process-water storage tanks. The Operations Office could have funded the project out of its unobligated FY 1996 operating funds. However, it returned the unobligated funds to the Department`s Headquarters at the end of the fiscal year. The Operations Office concurred with the finding and recommendations and initiated corrective action.

NONE

1997-10-23

120

Assessment of compost application to coal ash disposal sites to promote the rapid vegetation establishment  

NASA Astrophysics Data System (ADS)

In the city of Tuzla, located in Bosnia and Herzegovina, a coal fired thermo electric power plant is operated by the company JP ELEKTROPRIVERDA BIH TERMOELEKTRANA "TUZLA". High amounts of ash are produced by the power plant, which are currently disposed into settlement ponds bordered by dams in natural valleys. A total of four ash disposal sites covering an area of approx. 170 ha have been established during the last decades. Due to the fact that residual ash from coal combustion was found to contain a variety of trace elements (Ni, Cr, As, B), it must be assumed that ash disposal of that magnitude constitutes an environmental problem which is investigated within the EU-FP6 / STREP project "Reintegration of Coal Ash Disposal Sites and Mitigation of Pollution in the West Balkan Area" RECOAL. The main hazards relate to soil and groundwater contamination due to leaching toxins, dust dispersion, and toxins entering the food chain as these disposal sites are used for agricultural purposes. In order to rapidly establish a vegetation cover on barren ash dumps that particularly would prevent dust erosion we assessed the applicability of compost, produced from locally available municipal and industrial organic residues as an amendment to ash to improve substrate fertility. The envisaged remediation technology was considered to be a low cost, easy applicable and rapid method capable of substantially enhancing living conditions of residents in the vicinity of the abandoned disposal sites. Various compost application rates were evaluated in the field on experimental site Divkovici I in Tuzla and additionally in the greenhouse environment at Brandenburg Technical University Cottbus. Field and laboratory tests revealed that plant growth and cover rate can substantially be improved by mixing compost into the upper ash layer to a maximum depth of approx. 20 cm. Besides direct growth observations in the field analysis of soil parameters gave evidence that the fertility of ashy substrates amended with compost produced from locally available sewage sludge and saw dust can be improved. The metal content of grass grown in the various treatments was considered to be elevated compared to normal contents. However, metal uptake in compost treatments was lower than in untreated plots. A preliminary cost assessment, comparing the remediation technology tested on site Divkovici with a standard soil covering technique revealed financial benefits for the compost method due to significant lower application rates.

Repmann, F.; Slazak, A.; Babic, M.; Schneider, B. U.; Schaaf, W.; Httl, R. F.

2009-04-01

121

Site selection experience for a new low-level radioactive waste storage/disposal facility at the Savannah River Plant  

SciTech Connect

Preliminary performance criteria and site selection guides specific to the Savannah River Plant, were developed for a new low-level radioactive waste storage/disposal facility. These site selection guides were applied to seventeen potential sites identified at SRP. The potential site were ranked based on how well they met a set of characteristics considered important in site selection for a low-level radioactive waste disposal facility. The characteristics were given a weighting factor representing its relative importance in meeting site performance criteria. A candidate site was selected and will be the subject of a site characterization program.

Towler, O A; Cook, J R; Helton, B D

1985-10-01

122

Modeling Groundwater Flow and Infiltration at Potential Low-Level Radioactive Waste Disposal Sites in Taiwan  

NASA Astrophysics Data System (ADS)

Taiwan is evaluating representative sites for the potential disposal of low-level radioactive waste (LLW), including consideration of shallow land burial and cavern disposal concepts. A representative site for shallow land burial is on a small island in the Taiwan Strait with basalt bedrock. The shallow land burial concept includes an engineered cover to limit infiltration into the waste disposal cell. A representative site for cavern disposal is located on the southeast coast of Taiwan. The tunnel system for this disposal concept would be several hundred meters below the mountainous land surface in argillite bedrock. The LLW will consist of about 966,000 drums, primarily from the operation and decommissioning of four nuclear power plants. Sandia National Laboratories and the Institute of Nuclear Energy Research have collaborated to develop performance assessment models to evaluate the long-term safety of LLW disposal at these representative sites. Important components of the system models are sub-models of groundwater flow in the natural system and infiltration through the engineered cover for the shallow land burial concept. The FEHM software code was used to simulate groundwater flow in three-dimensional models at both sites. In addition, a higher-resolution two-dimensional model was developed to simulate flow through the engineered tunnel system at the cavern site. The HELP software was used to simulate infiltration through the cover at the island site. The primary objective of these preliminary models is to provide a modeling framework, given the lack of site-specific data and detailed engineering design specifications. The steady-state groundwater flow model at the island site uses a specified recharge boundary at the land surface and specified head at the island shoreline. Simulated groundwater flow vectors are extracted from the FEHM model along a cross section through one of the LLW disposal cells for utilization in radionuclide transport simulations in the performance assessment model with the BLT-MS software. Infiltration through the engineered cover is simulated to be about 3 mm/yr and 49 mm/yr, with and without a geomembrane layer, respectively. For the cavern LLW disposal site, the FEHM basin-scale flow model uses specified recharge flux, constant head at the ocean shoreline, and head-dependent flux boundaries along flowing streams. Groundwater flow vectors are extracted along a cross section for use in radionuclide transport simulations. Transport simulations indicate that a significant fraction of contaminants may ultimately discharge to nearby streams. FEHM flow simulations with the drift-scale model indicate that the flow rates within the backfilled tunnels may be more than two orders of magnitude lower than in the host rock. Sandia National Laboratories is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under Contract DE-AC04-94AL85000.

Arnold, B. W.; Lee, C.; Ma, C.; Knowlton, R. G.

2006-12-01

123

Quantifying Deep Vadose Zone Soil Water Potential Changes at a Waste Disposal Site  

SciTech Connect

Recent advances in moisture monitoring using tensiometers has resulted in long-duration, high quality data sets from within the deep vadose zone. A network of about 30 advanced tensiometers in 18 wells provided field-scale data to monitor soil water potential conditions and movement in the subsurface in and around a mixed waste disposal site at depths ranging from 6 to over 67 m below land surface (bls). Sensors are located in both sediments and fractured rock within the geologic profile and some have been in operation for over 10 years. The moisture monitoring was able to detect long term declines in soil water potential in response to lower than normal precipitation and resultant infiltration over the time period from 2000 to 2004. This trend was reversed in 2005 and 2006 in more than half of the monitoring sites over the 6 to 33 m depth interval and in several monitoring sites from 33 to 67 m, in response to above normal precipitation. These tensiometer data have the potential to effectively and rapidly validate that a remedial action such as placement of an ET cover would be successful in reducing the water moisture movement inside the disposal area to levels similar to those in undisturbed sites outside of the disposal area. This paper will describe the instrument design, how the instruments were installed, and the resultant data from this monitoring system.

Joel M. Hubbell; Deborah L. McElroy

2007-08-01

124

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

SciTech Connect

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.

NONE

1996-11-01

125

The siting dilemma: Low-level radioactive waste disposal in the United States  

SciTech Connect

The 1980 Low-Level Radioactive Waste Policy Act ushered in a new era in low-level waste disposal; one with vastly increased state responsibilities. By a 1985 amendment, states were given until January 1993 to fulfill their mandate. In this dissertation, their progress is reviewed. The focus then turns to one particularly intractable problem: that of finding technically and socially acceptable sites for new disposal facilities. Many lament the difficulty of siting facilities that are intended to benefit the public at large but are often locally unwanted. Many label local opposition as purely self-interested; as simply a function of the NIMBY (Not In My Backyard) syndrome. Here, it is argued that epithets such as NIMBY are unhelpful. Instead, to lay the groundwork for widely acceptable solutions to siting conflicts, deeper understanding is needed of differing values on issues concerning authority, trust, risk, and justice. This dissertation provides a theoretical and practical analysis of those issues as they pertain to siting low-level waste disposal facilities and, by extension, other locally unwanted facilities.

English, M.R.

1991-01-01

126

Description of Site Operations at the Low-Level Radioactive Waste Disposal Site  

Microsoft Academic Search

The purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than

Y. T. Mohamed; M. A. Hasan; Y. F. Lasheen

2007-01-01

127

Treatment and disposal of high-level radioactive waste at the Hanford Site: The technical challenge  

SciTech Connect

The US Department of Energy`s (DOE) Hanford Site, located in southeastern Washington State, has the most diverse and largest amount of radioactive tank waste in the US. A Tank Waste Remediation System (TWRS) Program was established in 1991 to safely store, treat, and dispose of those wastes. This paper describes the technical challenge in conducting the TWRS Program that will take more than 30 years and cost tens of billions of dollars to complete.

Wodrich, D.D.; Honeyman, J.O.; Wojtasek, R.D.

1994-07-01

128

Analysis of core soil and water samples from the Cactus Crater Disposal Site at Enewetak atoll  

SciTech Connect

Core soil samples and water samples were collected from the Cactus Crater Disposal Site at Enewetak for analysis of /sup 137/Cs, /sup 90/Sr, /sup 239 +240/Pu and /sup 241/Am by both gamma spectroscopy and, through a contractor laboratory, by wet chemistry procedures. The samples processing methods, the analytical methods and the analytical quality control are all procedures developed for the continuing Marshall Island radioecology and dose assessment work.

Robison, W.L.; Noshkin, V.E.

1981-02-18

129

Analysis of core soil and water samples from the Cactus Crater Disposal Site at Enewetak atoll  

Microsoft Academic Search

Core soil samples and water samples were collected from the Cactus Crater Disposal Site at Enewetak for analysis of ¹³⁷Cs, ⁹°Sr, \\/sup 239 +240\\/Pu and ²⁴¹Am by both gamma spectroscopy and, through a contractor laboratory, by wet chemistry procedures. The samples processing methods, the analytical methods and the analytical quality control are all procedures developed for the continuing Marshall Island

W. L. Robison; V. E. Noshkin

1981-01-01

130

Recommended Procedures for Measuring Radon Fluxes from Disposal Sites of Residual Radioactive Materials  

SciTech Connect

This report recornmenrls instrumentation and methods suitable for measuring radon fluxes emanating from covered disposal sites of residual radioactive materials such as uranium mill tailings. Problems of spatial and temporal variations in radon flux are discussed and the advantages and disadvantages of several instruments are examined. A year-long measurement program and a two rnonth measurement rnethodology are then presented based on the inherent difficulties of measuring average radon flux over a cover using the recommended instrumentation.

Young,, J. A.; Thomas, V. W.; Jackson, P. 0.

1983-03-01

131

Aquifer test plan for two wells at the proposed C-018H disposal site  

Microsoft Academic Search

Aquifer testing will be conducted at groundwater monitoring well No. 3 at the proposed State-Approved Land Disposal Site (SALDS) north of the 200 West Area. Hydrologic testing will consist of instantaneous slug tests and constant rate discharge tests in a ``drill-and-test`` type sequence. Well No. 2 will be installed as a shallow groundwater monitoring well prior to testing, and used

1994-01-01

132

A temporal and spatial assessment of TBT concentrations at dredged material disposal sites around the coast of England and Wales.  

PubMed

Despite legislative interventions since the 1980s, contemporary concentrations of organotin compounds in marine sediments still impose restrictions on the disposal of dredged material in the UK. Here, we analyse temporal and spatial data to assess the effectiveness of the ban on the use of TBT paints in reducing concentrations at disposal sites. At a national scale, there was a statistically significant increase in the proportion of samples in which the concentration was below the limit of detection (LOD) from 1998 to 2010. This was observed for sediments both inside and outside the disposal sites. However, this temporal decline in organotin concentration is disposal site-specific. Of the four sites studied in detail, two displayed significant increases in proportion of samples below LOD over time. We argue that site-specificity in the effectiveness of the TBT ban results from variations in historical practices at source and unique environmental characteristics of each site. PMID:24368118

Bolam, Thi; Barry, Jon; Law, Robin J; James, David; Thomas, Boby; Bolam, Stefan G

2014-02-15

133

Radionuclide migration pathways analysis for the Oak Ridge Central Waste Disposal Facility on the West Chestnut Ridge site  

Microsoft Academic Search

A dose-to-man pathways analysis is performed for disposal of low-level radioactive waste at the Central Waste Disposal Facility on the West Chestnut Ridge Site. Both shallow land burial (trench) and aboveground (tumulus) disposal methods are considered. The waste volumes, characteristics, and radionuclide concentrations are those of waste streams anticipated from the Oak Ridge National Laboratory, the Y-12 Plant, and the

F. G. Pin; J. P. Witherspoon; D. W. Lee; J. B. Cannon; R. H. Ketelle

1984-01-01

134

Possibilities of detecting health effects by studies of populations exposed to chemicals from waste disposal sites.  

PubMed Central

Factors affecting the design of an epidemiologic study assessing possible health effects from chemical waste disposal sites are reviewed. Such epidemiologic studies will most likely be prompted either by a known release of chemicals into the environment around the site, or by an unusual disease cluster in a population near the site. In the latter situation, a method for evaluating the health effects is needed, and one possible approach is discussed. In the former situation, it may not be obvious what health outcomes are relevant. Reported associations between health effects and chemicals in humans were reviewed. Studies from the occupational and environmental literature were classified by chemical and target organ affected and presented in tabular form. No attempt was made to critically evaluate the quality of evidence for each health effect, although bibliographic documentation was provided where possible. Episodes of chemical contamination of food, drinking water and other media were also reviewed and presented in a separate table. The organ sites likely to be affected by toxic chemicals from waste disposal sites depend heavily on the route of exposure and the dose that is received. Ingestion is the most frequently reported route of exposure in episodes of environmental contamination. These have affected the hepatic, renal, hematopoietic, reproductive, and central nervous systems. The type and severity of effects were dose-dependent. Direct skin contact is important in the occupational environment where dermal and central nervous system effects have been reported but seems less likely as a route of exposure for populations around waste disposal sites. Inhalation, unless at relative high concentrations or as a result of fire, is unlikely to be important, although hematopoietic, reproductive, and central nervous system effects have been reported in occupational studies.

Buffler, P A; Crane, M; Key, M M

1985-01-01

135

Siting low-level radioactive waste disposal facilities: The public policy dilemma  

SciTech Connect

The book's focus is on one overwhelming problems facing the compacts and states: figuring out where low-level waste disposal sites should be located. The author discusses the central issues underlying this dilemma - authority, trust, risk, justice - and the roles each plays in determining whether the siting processes are regarded as legitimate. The structure of the book provides a mix of narrative, fact and philosophy and adds to the body of well researched information saying that is is not only right but more efficient to develop and implement a just process.

English, M.R.

1993-01-01

136

Assessment of site conditions for disposal of low- and intermediate-level radioactive wastes: A case study in southern China  

Microsoft Academic Search

Near surface disposal of low- and intermediate-level radioactive wastes (LILW) requires evaluating the field conditions of the candidate site. However, assessment of the site conditions may be challenging due to the limited prior knowledge of some remote sites, and various multi-disciplinary data requirements at any given site. These situations arise in China as in the rest of the industrialized world,

Shuping Yi; Haiyi Ma; Chunmiao Zheng; Xuebin Zhu; Hua'an Wang; Xueshan Li; Xueling Hu; Jianbo Qin

137

Long-term surveillance plan for the Canonsburg, Pennsylvania, disposal site  

SciTech Connect

This document establishes elements of the US Department of Energy`s (DOE) Long-Term Surveillance Plan for the Canonsburg, Pennsylvania, disposal site. The US Nuclear Regulatory Commission (NRC) will use this plan in support of license issuance for the long-term surveillance of the Canonsburg site. The Canonsburg (CAN) site is located within the borough of Canonsburg, Washington County, in southwestern Pennsylvania. The Canonsburg site covers approximately 30 acres (74 hectares). The disposal cell contains approximately 226,000 tons (241,000 tons) of residual radioactive material (RRM). Area C is southeast of the Canonsburg site, between Strabane Avenue and Chartiers Creek. Contaminated soils were removed from Area C during the remedial action, and the area was restored with uncontaminated fill material.After this cleanup, residual quantities of thorium-230 were detected at several Area C locations. The remedial action plan did not consider the ingrowth of radium-226 from thorium-230 as part of the Area C cleanup, and only two locations contained sufficient thorium-230 concentrations to result in radium-226 concentrations slightly above the US Environmental Protection Agency (EPA) standards.

NONE

1995-10-01

138

Quantifying Deep Vadose Zone Soil Water Potential Changes At A Waste Disposal Site  

SciTech Connect

Recent advances in moisture monitoring using tensiometers has allowed long-duration, high quality data sets from within the deep vadose zone. A network of about 30 advanced tensiometers in 18 wells provided field-scale data to monitor moisture conditions and movement in the subsurface in and around a mixed waste disposal site at depths ranging from 6 to over 67 m below land surface (bls). Sensors are located in both sediments and fractured rock within the geologic profile and some have been in operation for over 10 years. The moisture monitoring was able to detect long term declines in moisture content presumably in response to lower than normal precipitation and resultant infiltration over the time period from 2000 to 2004. This trend was reversed in 2005 and 2006 in more than half of the monitoring sites over the 6 to 33 m depth interval and in several monitoring sites from 33 to 67 m, in response to normal to above normal precipitation. This tensiometer data can be used to evaluate the appropriateness of the current conceptual model of flow at this site. It also shows that a moisture monitoring system should be effective to rapidly validate that a proposed remedial action (such as placement of an ET cover) would be effective in reducing the moisture movement to levels similar to those in undisturbed sites outside of the disposal area. This paper will describe the instrument design, how the instruments were installed, and the resultant data from this monitoring system.

Joel M. Hubbell; Deborah L. McElroy

2007-10-01

139

UTILIZING A CHIRP SONAR TO ACCURATELY CHARACTERIZE NEWLY DEPOSITED MATERIAL AT THE CALCASIEU OCEAN DREDGED MATERIAL DISPOSAL SITE, LOUISIANA  

EPA Science Inventory

The distribution of dredged sediments is measured at the Calcasieu Ocean Dredged Material Disposal Site (ODMDS) using a chirp sonar immediately after disposal and two months later. ubbottom reflection data, generated by a chirp sonar transmitting a 4 to 20 kHz FM sweep, is proces...

140

1984 State-by-State Assessment of Low-Level Radioactive Wastes Shipped to Commercial Disposal Sites.  

National Technical Information Service (NTIS)

The 1984 report uses the volume of low-level waste reported as received at each commercial disposal site as the national baseline figure. A volume of 75,429 m exp 3 of radioactive waste containing 600,909 Ci of activity was reported disposed at the commer...

1985-01-01

141

Fuzzy multicriteria disposal method and site selection for municipal solid waste.  

PubMed

The use of fuzzy multiple criteria analysis (MCA) in solid waste management has the advantage of rendering subjective and implicit decision making more objective and analytical, with its ability to accommodate both quantitative and qualitative data. In this paper a modified fuzzy TOPSIS methodology is proposed for the selection of appropriate disposal method and site for municipal solid waste (MSW). Our method is superior to existing methods since it has capability of representing vague qualitative data and presenting all possible results with different degrees of membership. In the first stage of the proposed methodology, a set of criteria of cost, reliability, feasibility, pollution and emission levels, waste and energy recovery is optimized to determine the best MSW disposal method. Landfilling, composting, conventional incineration, and refuse-derived fuel (RDF) combustion are the alternatives considered. The weights of the selection criteria are determined by fuzzy pairwise comparison matrices of Analytic Hierarchy Process (AHP). It is found that RDF combustion is the best disposal method alternative for Istanbul. In the second stage, the same methodology is used to determine the optimum RDF combustion plant location using adjacent land use, climate, road access and cost as the criteria. The results of this study illustrate the importance of the weights on the various factors in deciding the optimized location, with the best site located in Catalca. A sensitivity analysis is also conducted to monitor how sensitive our model is to changes in the various criteria weights. PMID:20303733

Ekmekio?lu, Mehmet; Kaya, Tolga; Kahraman, Cengiz

2010-01-01

142

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

SciTech Connect

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.

Not Available

1994-08-01

143

Waste Disposal.  

National Technical Information Service (NTIS)

Waste solids (dredge spoil, rubble, sewage sludge, and industrial sludge) are dumped at six major disposal sites in New York Bight. Amounts of waste solids discharged increased between 1968 and 1975 although the number of individual disposal operations de...

M. G. Gross

1976-01-01

144

Radiological audit of remedial action activities at the processing site, transfer site, and Cheney disposal site Grand Junction, Colorado: Audit date, August 9--11, 1993. Final report  

SciTech Connect

The Uranium Mill Tailing Remedial Action (UMTRA) Project`s Technical Assistance Contractor (TAC) performed a radiological audit of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site, transfer site, and Cheney disposal site in Grand Junction, Colorado. Jim Hylko and Bill James of the TAC conducted this audit August 9 through 11, 1993. Bob Cornish and Frank Bosiljevec represented the US Department of Energy (DOE). This report presents one programmatic finding, eleven site-specific observations, one good practice, and four programmatic observations.

Not Available

1993-08-01

145

Example of a Risk-Based Disposal Approval: Solidification of Hanford Site Transuranic Waste  

SciTech Connect

The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained polychlorinated biphenyls (PCBs) regulated under TSCA. The prescribed disposal method for liquid PCB waste under TSCA regulations is either thermal treatment or decontamination. Due to the radioactive nature of the waste, however, neither thermal treatment nor decontamination was a viable option. As a result, the proposed treatment consisted of solidifying the material to comply with waste acceptance criteria at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico, or possibly the Environmental Restoration Disposal Facility at the Hanford Site, depending on the resulting transuranic (TRU) content of the stabilized waste. The RBDA evaluated environmental risks associated with potential airborne PCBs. In addition, the RBDA made use of waste management controls already in place at the treatment unit. The treatment unit, the T Plant Complex, is a Resource Conservation and Recovery Act of 1976 (RCRA)-permitted facility used for storing and treating radioactive waste. The EPA found that the proposed activities did not pose an unreasonable risk to human health or the environment. Treatment took place from October 26, 2005 to June 9, 2006, and 332 208-liter (55-gallon) containers of solidified waste were produced. All treated drums assayed to date are TRU and will be disposed at WIPP. (authors)

Barnes, B.M.; Hyatt, J.E.; Martin, P.W.; Prignano, A.L. [Fluor Hanford, Inc., Richland, WA (United States)

2008-07-01

146

EXAMPLE OF A RISK BASED DISPOSAL APPROVAL SOLIDIFICATION OF HANFORD SITE TRANSURANIC (TRU) WASTE  

SciTech Connect

The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained polychlorinated biphenyls (PCBs) regulated under TSCA. The prescribed disposal method for liquid PCB waste under TSCA regulations is either thermal treatment or decontamination. Due to the radioactive nature of the waste, however, neither thermal treatment nor decontamination was a viable option. As a result, the proposed treatment consisted of solidifying the material to comply with waste acceptance criteria at the Waste Isolation Pilot Plant (WPP) in Carlsbad, New Mexico, or possibly the Environmental Restoration Disposal Facility at the Hanford Site, depending on the resulting transuranic (TRU) content of the stabilized waste. The RBDA evaluated environmental risks associated with potential airborne PCBs. In addition, the RBDA made use of waste management controls already in place at the treatment unit. The treatment unit, the T Plant Complex, is a Resource Conservation and Recovery Act of 1976 (RCRA)-permitted facility used for storing and treating radioactive waste. The EPA found that the proposed activities did not pose an unreasonable risk to human health or the environment. Treatment took place from October 26,2005 to June 9,2006, and 332 208-liter (55-gallon) containers of solidified waste were produced. All treated drums assayed to date are TRU and will be disposed at WIPP.

PRIGNANO AL

2007-11-14

147

Assessment and analysis of industrial liquid waste and sludge disposal at unlined landfill sites in arid climate  

SciTech Connect

Municipal solid waste disposal sites in arid countries such as Kuwait receive various types of waste materials like sewage sludge, chemical waste and other debris. Large amounts of leachate are expected to be generated due to the improper disposal of industrial wastewater, sewage sludge and chemical wastes with municipal solid waste at landfill sites even though the rainwater is scarce. Almost 95% of all solid waste generated in Kuwait during the last 10 years was dumped in five unlined landfills. The sites accepting liquid waste consist of old sand quarries that do not follow any specific engineering guidelines. With the current practice, contamination of the ground water table is possible due to the close location of the water table beneath the bottom of the waste disposal sites. This study determined the percentage of industrial liquid waste and sludge of the total waste dumped at the landfill sites, analyzed the chemical characteristics of liquid waste stream and contaminated water at disposal sites, and finally evaluated the possible risk posed by the continuous dumping of such wastes at the unlined landfills. Statistical analysis has been performed on the disposal and characterization of industrial wastewater and sludge at five active landfill sites. The chemical analysis shows that all the industrial wastes and sludge have high concentrations of COD, suspended solids, and heavy metals. Results show that from 1993 to 2000, 5.14{+-}1.13 million t of total wastes were disposed per year in all active landfill sites in Kuwait. The share of industrial liquid and sludge waste was 1.85{+-}0.19 million t representing 37.22{+-}6.85% of total waste disposed in all landfill sites. Such wastes contribute to landfill leachate which pollutes groundwater and may enter the food chain causing adverse health effects. Lined evaporation ponds are suggested as an economical and safe solution for industrial wastewater and sludge disposal in the arid climate of Kuwait.

Al Yaqout, Anwar F

2003-07-01

148

Assessment and analysis of industrial liquid waste and sludge disposal at unlined landfill sites in arid climate.  

PubMed

Municipal solid waste disposal sites in arid countries such as Kuwait receive various types of waste materials like sewage sludge, chemical waste and other debris. Large amounts of leachate are expected to be generated due to the improper disposal of industrial wastewater, sewage sludge and chemical wastes with municipal solid waste at landfill sites even though the rainwater is scarce. Almost 95% of all solid waste generated in Kuwait during the last 10 years was dumped in five unlined landfills. The sites accepting liquid waste consist of old sand quarries that do not follow any specific engineering guidelines. With the current practice, contamination of the ground water table is possible due to the close location of the water table beneath the bottom of the waste disposal sites. This study determined the percentage of industrial liquid waste and sludge of the total waste dumped at the landfill sites, analyzed the chemical characteristics of liquid waste stream and contaminated water at disposal sites, and finally evaluated the possible risk posed by the continuous dumping of such wastes at the unlined landfills. Statistical analysis has been performed on the disposal and characterization of industrial wastewater and sludge at five active landfill sites. The chemical analysis shows that all the industrial wastes and sludge have high concentrations of COD, suspended solids, and heavy metals. Results show that from 1993 to 2000, 5.14+/-1.13 million t of total wastes were disposed per year in all active landfill sites in Kuwait. The share of industrial liquid and sludge waste was 1.85+/-0.19 million t representing 37.22+/-6.85% of total waste disposed in all landfill sites. Such wastes contribute to landfill leachate which pollutes groundwater and may enter the food chain causing adverse health effects. Lined evaporation ponds are suggested as an economical and safe solution for industrial wastewater and sludge disposal in the arid climate of Kuwait. PMID:14583244

Al Yaqout, Anwar F

2003-01-01

149

Technical site characterization of the Mercer County Ash Disposal Facility: A case history  

SciTech Connect

The Waste-Tech Services, Inc., Mercer County Ash Disposal Facility is a proposed Resource Conservation and Recovery Act (RCRA) permitted hazardous waste treatment, storage and disposal facility located SW of Princeton, Missouri. The facility is to accept, store, treat and landfill ash residues from RCRA-permitted hazardous waste incineration. The site was characterized for a permit application submitted to the Missouri Department of Natural Resource (MDNR). MDNR was involved during all site characterization stages, including MDNR review, input and oversight during the planning, field execution and report-preparation stages. Both parties agreed upon the needs required for characterizing the sites prior field work, and the MDNR ensured that scope of work stipulations were implemented in the field and reported. Three broad characterization categories were defined: (1) physical characteristics; (2) biological characteristics; and, (3) socio-economic considerations. Physical criteria include the geologic, geotechnical, hydrogeologic and hydrologic site conditions. Threatened and Endangered Species and Wetlands comprised the biologic issues. Socio-economics considered cultural resources, such as history and archeology, market proximity, capacity assurance and transportation.

Allen, R.C.; Walton, C.G.; Zweig, L.T. (Waste-Tech Services, Inc., Golden, CO (United States))

1993-03-01

150

Near-bottom pelagic bacteria at a deep-water sewage sludge disposal site  

SciTech Connect

The epibenthic bacterial community at deep-ocean sewage sludge disposal site DWD-106, located approximately 106 miles (ca. 196 km) off the coast of New Jersey, was assessed for changes associated with the introduction of large amounts of sewage sludge. Mixed cultures and bacterial isolates obtained from water overlying sediment core samples collected at the deep-water (2,500 m) municipal sewage disposal site were tested for the ability to grow under in situ conditions of temperature and pressure. The responses of cultures collected at a DWD-106 station heavily impacted by sewage sludge were compared with those of samples collected from a station at the same depth which was not contaminated by sewage sludge. Significant differences were observed in the ability of mixed bacterial cultures and isolates from the two sites to grow under deep-sea pressure and temperature conditions. The levels of sludge contamination were established by enumerating Clostridium perfringens, a sewage indicator bacterium, in sediment samples from the two sites. (Copyright (c) 1993, American Society for Microbiology.)

Takizawa, M.; Straube, W.L.; Hill, R.T.; Colwell, R.R.

1994-01-01

151

Second performance assessment iteration of the Greater Confinement Disposal facility at the Nevada Test Site  

SciTech Connect

The Greater Confinement Disposal (GCD) facility was established in Area 5 at the Nevada Test Site for containment of waste inappropriate for shallow land burial. Some transuranic (TRU) waste has been disposed of at the GCD facility, and compliance of this disposal system with EPA regulation 40 CFR 191 must be evaluated. We have adopted an iterative approach in which performance assessment results guide site data collection, which in turn influences the parameters and models used in performance assessment. The first iteration was based upon readily available data, and indicated that the GCD facility would likely comply with 40 CFR 191 and that the downward flux of water through the vadose zone (recharge) had a major influence on the results. Very large recharge rates, such as might occur under a cooler, wetter climate, could result in noncompliance. A project was initiated to study recharge in Area 5 by use of three environmental tracers. The recharge rate is so small that the nearest groundwater aquifer will not be contaminated in less than 10,000 years. Thus upward liquid diffusion of radionuclides remained as the sole release pathway. This second assessment iteration refined the upward pathway models and updated the parameter distributions based upon new site information. A new plant uptake model was introduced to the upward diffusion pathway; adsorption and erosion were also incorporated into the model. Several modifications were also made to the gas phase radon transport model. Plutonium solubility and sorption coefficient distributions were changed based upon new information, and on-site measurements were used to update the moisture content distributions. The results of the assessment using these models indicate that the GCD facility is likely to comply with all sections of 40 CFR 191 under undisturbed conditions.

Baer, T.A.; Emery, J.N. [GRAM, Inc., Albuquerque, NM (United States)] [GRAM, Inc., Albuquerque, NM (United States); Price, L.L. [Science Applications International Corp., Albuquerque, NM (United States)] [Science Applications International Corp., Albuquerque, NM (United States); Olague, N.E. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States)

1994-04-01

152

40 CFR 228.13 - Guidelines for ocean disposal site baseline or trend assessment surveys under section 102 of the...  

Code of Federal Regulations, 2011 CFR

...likely to be most severe, or when pollutant impact within disposal sites is...persistent organohalogens, and heavy metals. Discrete water samples shall...organohalogens, pesticides, and heavy metals: (i) A predominant...

2011-07-01

153

40 CFR 228.13 - Guidelines for ocean disposal site baseline or trend assessment surveys under section 102 of the...  

Code of Federal Regulations, 2012 CFR

...likely to be most severe, or when pollutant impact within disposal sites is...persistent organohalogens, and heavy metals. Discrete water samples shall...organohalogens, pesticides, and heavy metals: (i) A predominant...

2012-07-01

154

Superfund Record of Decision (EPA Region 6): Bailey Waste Disposal Site, Orange, Texas, June 1988. First Remedial Action.  

National Technical Information Service (NTIS)

The Bailey Waste Disposal site is an inactive industrial waste facility located approximately 3 miles southwest of Bridge City, Orange County, Texas and is part of a saltwater marshland which includes two ponds. Industrial wastes, primarily organics, were...

1988-01-01

155

40 CFR 61.151 - Standard for inactive waste disposal sites for asbestos mills and manufacturing and fabricating...  

Code of Federal Regulations, 2013 CFR

...or (4) For inactive waste disposal sites for asbestos tailings, a resinous or petroleum-based dust suppression agent...manner and frequency recommended for the particular asbestos tailings by the manufacturer of the dust suppression agent to...

2013-07-01

156

A Probabilistic Performance Assessment Study of Potential Low-Level Radioactive Waste Disposal Sites in Taiwan  

NASA Astrophysics Data System (ADS)

For several years now, Taiwan has been engaged in a process to select a low-level radioactive waste (LLW) disposal site. Taiwan is generating LLW from operational and decommissioning wastes associated with nuclear power reactors, as well as research, industrial, and medical radioactive wastes. The preliminary selection process has narrowed the search to four potential candidate sites. These sites are to be evaluated in a performance assessment analysis to determine the likelihood of meeting the regulatory criteria for disposal. Sandia National Laboratories and Taiwan's Institute of Nuclear Energy Research have been working together to develop the necessary performance assessment methodology and associated computer models to perform these analyses. The methodology utilizes both deterministic (e.g., single run) and probabilistic (e.g., multiple statistical realizations) analyses to achieve the goals. The probabilistic approach provides a means of quantitatively evaluating uncertainty in the model predictions and a more robust basis for performing sensitivity analyses to better understand what is driving the dose predictions from the models. Two types of disposal configurations are under consideration: a shallow land burial concept and a cavern disposal concept. The shallow land burial option includes a protective cover to limit infiltration potential to the waste. Both conceptual designs call for the disposal of 55 gallon waste drums within concrete lined trenches or tunnels, and backfilled with grout. Waste emplaced in the drums may be solidified. Both types of sites are underlain or placed within saturated fractured bedrock material. These factors have influenced the conceptual model development of each site, as well as the selection of the models to employ for the performance assessment analyses. Several existing codes were integrated in order to facilitate a comprehensive performance assessment methodology to evaluate the potential disposal sites. First, a need existed to simulate the failure processes of the waste containers, with subsequent leaching of the waste form to the underlying host rock. The Breach, Leach, and Transport Multiple Species (BLT-MS) code was selected to meet these needs. BLT-MS also has a 2-D finite-element advective-dispersive transport module, with radionuclide in-growth and decay. BLT-MS does not solve the groundwater flow equation, but instead requires the input of Darcy flow velocity terms. These terms were abstracted from a groundwater flow model using the FEHM code. For the shallow land burial site, the HELP code was also used to evaluate the performance of the protective cover. The GoldSim code was used for two purposes: quantifying uncertainties in the predictions, and providing a platform to evaluate an alternative conceptual model involving matrix-diffusion transport. Results of the preliminary performance assessment analyses using examples to illustrate the computational framework will be presented. Sandia National Laboratories is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under Contract DE AC04 94AL85000.

Knowlton, R. G.; Arnold, B. W.; Mattie, P. D.; Kuo, M.; Tien, N.

2006-12-01

157

Delineation of soil and groundwater contamination using geophysical methods at a waste disposal site in anakkale, Turkey  

Microsoft Academic Search

Direct current (DC) resistivity, self potential (SP) and very low frequency electromagnetic (VLF-EM) measurements are carried\\u000a out to detect the spread of groundwater contamination and to locate possible pathways of leachate plumes, that resulted from\\u000a an open waste disposal site of ?anakkale municipality. There is no proper management of the waste disposal site in which industrial\\u000a and domestic wastes were

M. Ali Kaya; Glin zrlan; Ebru ?engl

2007-01-01

158

Arsenic concentration in porewater of an alkaline coal ash disposal site: Roles of siderite precipitation\\/dissolution and soil cover  

Microsoft Academic Search

The geochemical behavior of As in porewaters of an alkaline coal ash disposal site was investigated using multilevel samplers. The disposal site was in operation from 1983 until 1994 and was covered with 0.30.5m thick soils in 2001 when this study was initiated. Sequential extraction analyses and batch leaching experiments were also performed using the coal ash samples collected from

Kangjoo Kim; Sung-Min Park; Jinsam Kim; Seok-Hwi Kim; Yeongkyoo Kim; Jeong-Tae Moon; Gab-Soo Hwang; Wang-Seog Cha

2009-01-01

159

Assessment of Potential Flood Events and Impacts at INL's Proposed Remote-Handled Low-Level Waste Disposal Facility Sites  

Microsoft Academic Search

Rates, depths, erosion potential, increased subsurface transport rates, and annual exceedance probability for potential flooding scenarios have been evaluated for the on-site alternatives of Idaho National Laboratorys proposed remote handled low-level waste disposal facility. The on-site disposal facility is being evaluated in anticipation of the closure of the Radioactive Waste Management Complex at the INL. An assessment of flood impacts

A. Jeff Sondrup; Annette L. Schafter

2010-01-01

160

Closure Report for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada  

SciTech Connect

This Closure Report (CR) documents closure activities for Corrective Action Unit (CAU) 543, Liquid Disposal Units, according to the Federal Facility Agreement and Consent Order (FFACO, 1996) and the Corrective Action Plan (CAP) for CAU 543 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2007). CAU 543 is located at the Nevada Test Site (NTS), Nevada (Figure 1), and consists of the following seven Corrective Action Sites (CASs): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; CAS 15-23-03, Contaminated Sump, Piping; and CAS 06-07-01 is located at the Decontamination Facility in Area 6, adjacent to Yucca Lake. The remaining CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm in Area 15. The purpose of this CR is to provide a summary of the completed closure activities, to document waste disposal, and to present analytical data confirming that the remediation goals were met. The closure alternatives consisted of closure in place for two of the CASs, and no further action with implementation of best management practices (BMPs) for the remaining five CASs.

NSTec Environmental Restoration

2008-01-01

161

Meeting performance objectives for Low-Level Radioactive Disposal Waste Facility at the Savannah River Site  

SciTech Connect

A new Low-Level Radioactive Waste (LLW) disposal facility at the Savannah River Site is presently being constructed. The facility was designed to meet specific performance objectives (derived from DOE Order 5820.2A and proposed EPA Regulation 40CFR 193) in the disposal of containerized Class A and B wastes. The disposal units have been designed as below-grade concrete vaults. These vaults will be constructed using uniquely designed blast furnace slag + fly as concrete mix, surrounded by a highly permeable drainage layer, and covered with an engineered clay cap to provide the necessary environmental isolation of the waste form to meet the stated performance objectives. The concrete mix used in this facility, is the first such application in the United States. These vaults become operational in September 1992 and will become the first active facility of its kind, several years ahead of those planned in the commercial theater. This paper will discuss the selection of the performance objectives and conceptual design.

Taylor, G.E.

1992-04-01

162

Meeting performance objectives for Low-Level Radioactive Disposal Waste Facility at the Savannah River Site  

SciTech Connect

A new Low-Level Radioactive Waste (LLW) disposal facility at the Savannah River Site is presently being constructed. The facility was designed to meet specific performance objectives (derived from DOE Order 5820.2A and proposed EPA Regulation 40CFR 193) in the disposal of containerized Class A and B wastes. The disposal units have been designed as below-grade concrete vaults. These vaults will be constructed using uniquely designed blast furnace slag + fly as concrete mix, surrounded by a highly permeable drainage layer, and covered with an engineered clay cap to provide the necessary environmental isolation of the waste form to meet the stated performance objectives. The concrete mix used in this facility, is the first such application in the United States. These vaults become operational in September 1992 and will become the first active facility of its kind, several years ahead of those planned in the commercial theater. This paper will discuss the selection of the performance objectives and conceptual design.

Taylor, G.E.

1992-01-01

163

Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory  

SciTech Connect

Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledge (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.

Dorries, Alison M [Los Alamos National Laboratory

2010-11-09

164

Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960`s through 1990`s)  

SciTech Connect

During the time period covered in this report (1960`s through early 1990`s), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site`s general design, (2) each site`s inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site`s chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington.

NONE

1996-11-01

165

Leachate migration from a pesticide waste disposal site in Hardeman County, Tennessee  

USGS Publications Warehouse

Between 1964 and 1972, approximately 300,000 drums (55-gallon steel barrels) of waste derived from the manufacturing of pesticides were buried on 45 acres of land in northern Hardemen County, Tennessee. Leachates from these wastes are migrating from the disposal site in surface runoff, through shallow perched water zones, and through the local water-table aquifer. Compounds identified in the leachates included: dieldrin, endrin , chlordene, heptachlor, heptachlor epoxide, pentachlorocyclopentadiene, and hexachloro-bicycloheptadiene. The rate of migration of some of the leachate compounds in the water-table aquifer was found to be at least 80 feet per year. (Woodard-USGS)

Sprinkle, C. L.

1978-01-01

166

CLASSIFICATION OF THE MGR SITE-GENERATED HAZAROUS NONHAZARDOUS & SANITARY WASTE DISPOSAL SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site generated hazardous, non-hazardous and sanitary waste disposal system system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

J.A. Ziegler

1999-08-31

167

Radionuclide disequilibria studies for investigating the integrity of potential nuclear waste disposal sites: subseabed studies.  

SciTech Connect

This study of subseabed sediments indicates that natural radionuclides can be employed to define past long-term migration rates and thereby evaluate the integrity of potential disposal sites in ocean sediments. The study revealed the following conclusions: (1) the sedimentation rate of both the long and short cores collected in the North Pacific is 2.5 mm/1000 yr or 2.5 m/m.yr in the upper 3 meters; (2) the sedimentation rate has been rather constant over the last one million years; and (3) slow diffusive processes dominate within the sediment. Reworking of the sediment by physical processes or organisms is not observed.

Laul, J.C.; Thomas, C.W.; Petersen, M.R.; Perkins, R.W.

1981-09-01

168

Probabilistic Performance Assessment of a Low-Level Radioactive Waste Disposal Site on the Nevada Test Site  

SciTech Connect

The Area 5 Radioactive Waste Management Site on the Nevada Test Site has been disposing of low-level, mixed low-level, and transuranic radioactive waste since 1961. In 1988, the U.S. Department of Energy implemented performance objectives for low-level radioactive waste disposal site performance and required all site operators to prepare a performance assessment. Since then, an iterative performance assessment process has been implemented that consists of repeated cycles of site characterization, conceptual model formation/revision, and performance assessment modeling. At the end of each cycle uncertainty and sensitivity analysis are used to determine the need for revision and to identify topics requiring additional research and development. The performance assessment model is implemented in the GoldSim{reg_sign} probabilistic simulation platform. The current site conceptual model, based on site characterization data and process model results, assumes that there is no groundwater pathway under current climatic conditions and that radionuclide releases are predominately upward to the land surface. Radionuclides are released to the land surface by upward liquid advection/diffusion, gas diffusion, biointrusion, and inadvertent human intrusion. The model calculates dose for four members of public exposure scenarios and two intruder scenarios. The highest mean-dose, 0.04 mSv yr{sup -1}, is expected for a low-probability exposure scenario: establishment of a rural community at the site boundary at the end of institutional control. At the end of institutional control, doses are contributed primarily by {sup 3}H in agricultural products produced onsite. After approximately 300 years, the doses are contributed equally by {sup 99}Tc and {sup 210}Pb ingested in vegetables grown at the residence. Technetium is released to the surface by the coupled processes of liquid advection/diffusion occurring deep in the cover and plant uptake/animal burrowing occurring at shallower depths. Lead-210 is deposited in shallow cover soil by the radioactive decay of {sup 222}Rn diffusing in the gas phase. The highest mean dose for the more likely exposure scenario of transient recreational use of the site is 0.002 mSv yr{sup -1}. The transient visitor's dose is contributed predominantly by external irradiation from {sup 214}Pb and {sup 214}Bi, deposited in the cover by diffusion of {sup 222}Rn.

G. J. Shott; V. Yucel; L. T. Desotell

2008-03-01

169

Geohydrologic aspects for siting and design of low-level radioactive-waste disposal  

USGS Publications Warehouse

The objective for siting and design of low-level radioactive-waste repository sites is to isolate the waste from the biosphere until the waste no longer poses an unacceptable hazard as a result of radioactive decay. Low-level radioactive waste commonly is isolated at shallow depths with various engineered features to stabilize the waste and to reduce its dissolution and transport by ground water. The unsaturated zone generally is preferred for isolating the waste. Low-level radioactive waste may need to be isolated for 300 to 500 years. Maintenance and monitoring of the repository site are required by Federal regulations for only the first 100 years. Therefore, geohydrology of the repository site needs to provide natural isolation of the waste for the hazardous period following maintenance of the site. Engineering design of the repository needs to be compatible with the natural geohydrologic conditions at the site. Studies at existing commercial and Federal waste-disposal sites provide information on the problems encountered and the basis for establishing siting guidelines for improved isolation of radioactive waste, engineering design of repository structures, and surveillance needs to assess the effectiveness of the repositories and to provide early warning of problems that may require remedial action. Climate directly affects the hydrology of a site and probably is the most important single factor that affects the suitability of a site for shallow-land burial of low-level radioactive waste. Humid and subhumid regions are not well suited for shallow isolation of low-level radioactive waste in the unsaturated zone; arid regions with zero to small infiltration from precipitation, great depths to the water table, and long flow paths to natural discharge areas are naturally well suited to isolation of the waste. The unsaturated zone is preferred for isolation of low-level radioactive waste. The guiding rationale is to minimize contact of water with the waste and to minimize transport of waste from the repository. The hydrology of a flow system containing a repository is greatly affected by the engineering of the repository site. Prediction of the performance of the repository is a complex problem, hampered by problems of characterizing the natural and manmade features of the flow system and by the limitations of models to predict flow and geochemical processes in the saturated and unsaturated zones. Disposal in low-permeability unfractured clays in the saturated zone may be feasible where the radionuclide transport is controlled by diffusion rather than advection.

Bedinger, M. S.

1989-01-01

170

APPLICATION OF A HAZARD-ASSESSMENT RESEARCH STRATEGY FOR WASTE DISPOSAL AT 106-MILE OCEAN DISPOSAL SITE  

EPA Science Inventory

An application of a hazard-assessment research strategy was made using waste disposal at Deepwater Dumpsite-l06 (DWD-106) as an example. The strategy involved the synthesis of results from separate exposure and effects components in order to provide a scientific basis for estimat...

171

Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site  

SciTech Connect

This report documents a preliminary evaluation of the ability of the greater confinement disposal boreholes at the Nevada Test Site to provide long-term isolation of radionuclides from the disposal of vitrified byproduct material. The byproduct material is essentially concentrated residue from processing uranium ore that contains a complex mixture of radionuclides, many of which are long-lived and present in concentrations greater than 100,000 picoCuries per gram. This material has been stored in three silos at the fernald Environmental Management Project since the early 1950s and will be vitrified into 6,000 yd{sup 3} (4,580 m{sup 3}) of glass gems prior to disposal. This report documents Sandia National Laboratories` preliminary evaluation for disposal of the byproduct material and includes: the selection of quantitative performance objectives; a conceptual model of the disposal system and the waste; results of the modeling; identified issues, and activities necessary to complete a full performance assessment.

Cochran, J.R.; Brown, T.J.; Stockman, H.W.; Gallegos, D.P.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); Price, L.L. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); [Beta Inc. (United States)

1997-09-01

172

Application of Probabilistic Performance Assessment Modeling for Optimization of Maintenance Studies for Low-Level Radioactive Waste Disposal Sites at the Nevada Test Site  

SciTech Connect

The U.S. Department of Energy (DOE), National Nuclear Security Administration of the Nevada Operations Office (NNSA/NV) operates and maintains two active facilities on the Nevada Test Site (NTS) that dispose defense-generated low-level radioactive waste (LLW), mixed radioactive waste, and ''classified waste'' in shallow trenches and pits. The operation and maintenance of the LLW disposal sites are self-regulated by the DOE under DOE Order 435.1. This Order requires formal review of a performance assessment (PA) and composite analysis (CA; assessment of all interacting radiological sources) for each LLW disposal system followed by an active maintenance program that extends through and beyond the site closure program. The Nevada disposal facilities continue to receive NTS-generated LLW and defense-generated LLW from across the DOE complex. The PA/CAs for the sites have been conditionally approved and the facilities are now under a formal maintenance program that requires testing of conceptual models, quantifying and attempting to reduce uncertainty, and implementing confirmatory and long-term background monitoring, all leading to eventual closure of the disposal sites. To streamline and reduce the cost of the maintenance program, the NNSA/NV is converting the deterministic PA/CAs to probabilistic models using GoldSim, a probabilistic simulation computer code. The output of probabilistic models will provide expanded information supporting long-term decision objectives of the NTS disposal sites.

Crowe, B.; Yucel, V.; Rawlinson, S.; Black, P.; Carilli, J.; DiSanza, F.

2002-02-25

173

The application of magnetic gradiometry and electromagnetic induction at a former radioactive waste disposal site.  

PubMed

A former radioactive waste disposal site is surveyed with two non-intrusive geophysical techniques, including magnetic gradiometry and electromagnetic induction. Data were gathered over the site by towing the geophysical equipment mounted to a non-electrically conductive and non-magnetic fibre-glass cart. Magnetic gradiometry, which detects the location of ferromagnetic material, including iron and steel, was used to map the existence of a previously unknown buried pipeline formerly used in the delivery of liquid waste to a number of surface disposal trenches and concrete vaults. The existence of a possible pipeline is reinforced by historical engineering drawing and photographs. The electromagnetic induction (EMI) technique was used to map areas of high and low electrical conductivity, which coincide with the magnetic gradiometry data. The EMI also provided information on areas of high electrical conductivity unrelated to a pipeline network. Both data sets demonstrate the usefulness of surface geophysical surveillance techniques to minimize the risk of exposure in the event of future remediation efforts. PMID:20124318

Rucker, Dale Franklin

2010-04-01

174

Water quality impacts from on-site waste disposal systems to coastal areas through groundwater discharge  

NASA Astrophysics Data System (ADS)

This report summarizes research studies linking on-site waste disposal systems (OSDS) to pathogen and nutrient concentrations in groundwater with the potential to impact coastal embayments. Few studies connect OSDS to coastal water quality. Most studies examined pathogen and nutrient impacts to groundwater and omitted estimations of contaminants discharged to surface water. The majority of studies focused on nitrogen, with little information on pathogens and even less on phosphorus. Nitrogen discharged from OSDS poses the greatest threat to water quality. Vertical distance of septic tank infiltration system from the water table, septic system design, and siting remain the key components in minimizing potential impacts from OSDS for control of both pathogens and nutrients. The most comprehensive information connecting nutrient contributions from OSDS to surface water quality was the study conducted on Buttermilk Bay in Massachusetts where 74% of nitrogen to the bay was attributed to onsite disposal systems. In conclusion, further studies on the viability and transport of pathogens and nutrients through the groundwater aquifer and across the groundwater/surface-water interface are needed. Additional research on the importance of septic system design on the availability of contaminants to groundwater as well as the minimum distance between the septic system and water table necessary to protect groundwater are also indicated.

Harris, P. J.

1995-12-01

175

Dose and risk assessment for intrusion into mixed waste disposal sites  

SciTech Connect

Sites previously used for disposal of radioactive and hazardous chemical materials have resulted in situations that pose a potential threat to humans from inadvertent intrusion. An example generic scenario analysis was developed to demonstrate the evaluation of potential exposure to either cleanup workers or members of the public who intrude into buried waste containing both radioactive and hazardous chemical contaminants. The example scenarios consist of a collection of exposure routes (or pathways) with specific modeling assumptions for well-drilling and for excavation to construct buildings. These scenarios are used to describe conceptually some potential patterns of activity by non-protected human beings during intrusion into mixed-waste disposal sites. The dose from exposure to radioactive materials is calculated using the GENII software system and converted to risk by using factors from ICRP Publication 60. The hazard assessment for nonradioactive materials is performed using recent guidelines from the US Environmental Protection Agency (EPA). The example results are in the form of cancer risk for carcinogens and radiation exposure.

Kennedy, W.E. Jr.; Aaberg, R.L.

1991-10-01

176

Trees as indicators of subterranean water flow from a retired radioactive waste disposal site  

SciTech Connect

Tree sampling helped locate a subterranean flow of tritiated water from a low-level radioactive waste disposal site that had not been detected by well water monitoring alone. Deciduous trees growing in a natural forest on the hillsides downslope from the site were sampled for the presence of tritiated water in sap of maple trees and in leaf water extracted from oak and hickory trees. Elevated concentrations of /sup 3/H were detected in the leaf water extracted from several trees located 50 m downslope from the western boundary of the fenced exclusion zone. A 3-m-deep well drilled near these trees indicated that the source of tritiated water was a narrow zone of subterranean flow.

Rickard, W.H.; Kirby, L.J.

1987-02-01

177

Decision Support System For Management Of Low-Level Radioactive Waste Disposal At The Nevada Test Site  

SciTech Connect

The long-term safety of U.S. Department of Energy (DOE) low-level radioactive disposal facilities is assessed by conducting a performance assessment -- a systematic analysis that compares estimated risks to the public and the environment with performance objectives contained in DOE Manual 435.1-1, Radioactive Waste Management Manual. Before site operations, facilities design features such as final inventory, waste form characteristics, and closure cover design may be uncertain. Site operators need a modeling tool that can be used throughout the operational life of the disposal site to guide decisions regarding the acceptance of problematic waste streams, new disposal cell design, environmental monitoring program design, and final site closure. In response to these needs the National Nuclear Security Administration Nevada Site Office (NNSA/NSO) has developed a decision support system for the Area 5 Radioactive Waste Management Site in Frenchman Flat on the Nevada Test Site. The core of the system is a probabilistic inventory and performance assessment model implemented in the GoldSim{sup R} simulation platform. The modeling platform supports multiple graphic capabilities that allow clear documentation of the model data sources, conceptual model, mathematical implementation, and results. The combined models have the capability to estimate disposal site inventory, contaminant concentrations in environmental media, and radiological doses to members of the public engaged in various activities at multiple locations. The model allows rapid assessment and documentation of the consequences of waste management decisions using the most current site characterization information, radionuclide inventory, and conceptual model. The model is routinely used to provide annual updates of site performance, evaluate the consequences of disposal of new waste streams, develop waste concentration limits, optimize the design of new disposal cells, and assess the adequacy of environmental monitoring programs. (authors)

Shott, G.; Yucel, V.; Desotell, L. [Bechtel Nevada, P.O. Box 98521, Las Vegas, NV 89193-8521 (United States); Carilli, J.T. [U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office, P.O. Box 98518, Las Vegas, NV 89193-8518 (United States)

2006-07-01

178

Modeling of Carbon Tetrachloride Flow and Transport in the Subsurface of the 200 West Disposal Sites: Large-Scale Model Configuration and Prediction of Future Carbon Tetrachloride Distribution Beneath the 216-Z-9 Disposal Site  

SciTech Connect

Three-dimensional simulations considered migration of dense, nonaqueous phase liquid (DNAPL) consisting of CT and co disposed organics in the subsurface as a function of the properties and distribution of subsurface sediments and of the properties and disposal history of the waste. Simulations of CT migration were conducted using the Water-Oil-Air mode of Subsurface Transport Over Multiple Phases (STOMP) simulator. A large-scale model was configured to model CT and waste water discharge from the major CT and waste-water disposal sites.

Oostrom, Mart; Thorne, Paul D.; Zhang, Z. F.; Last, George V.; Truex, Michael J.

2008-12-17

179

Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory  

SciTech Connect

This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau.

Reneau, S.L.; Raymond, R. Jr. [eds.

1995-12-01

180

Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site  

SciTech Connect

The U.S. Department of Energy, National Security Administration Nevada Site Office (NNSA/NSO) is planning to close the 92-Acre Area of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada. Closure planning for this facility must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. This paper provides a brief background of the Area 5 RWMS, identifies key closure issues, and presents the closure strategy. Disposals have been made in 25 shallow excavated pits and trenches and 13 Greater Confinement Disposal (GCD) boreholes at the 92-Acre Area since 1961. The pits and trenches have been used to dispose unclassified low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform waste, and to store classified low-level and low-level mixed materials. The GCD boreholes are intermediate-depth disposal units about 10 feet (ft) in diameter and 120 ft deep. Classified and unclassified high-specific activity LLW, transuranic (TRU), and mixed TRU are disposed in the GCD boreholes. TRU waste was also disposed inadvertently in trench T-04C. Except for three disposal units that are active, all pits and trenches are operationally covered with 8-ft thick alluvium. The 92-Acre Area also includes a Mixed Waste Disposal Unit (MWDU) operating under Resource Conservation and Recovery Act (RCRA) Interim Status, and an asbestiform waste unit operating under a state of Nevada Solid Waste Disposal Site Permit. A single final closure cover is envisioned over the 92-Acre Area. The cover is the evapotranspirative-type cover that has been successfully employed at the NTS. Closure, post-closure care, and monitoring must meet the requirements of the following regulations: U.S. Department of Energy Order 435.1, Title 40 Code of Federal Regulations (CFR) Part 191, Title 40 CFR Part 265, Nevada Administrative Code (NAC) 444.743, RCRA requirements as incorporated into NAC 444.8632, and the Federal Facility Agreement and Consent Order (FFACO). A grouping of waste disposal units according to waste type, location, and similarity in regulatory requirements identified six closure units: LLW Unit, Corrective Action Unit (CAU) 111 under FFACO, Asbestiform LLW Unit, Pit 3 MWDU, TRU GCD Borehole Unit, and TRU Trench Unit. The closure schedule of all units is tied to the closure schedule of the Pit 3 MWDU under RCRA.

L. Desotell; D. Wieland; V. Yucel; G. Shott; J. Wrapp

2008-03-01

181

Investigative studies for the use of an inactive asbestos mine as a disposal site for asbestos wastes.  

PubMed

Although, according to European legislation the use of Asbestos Containing Materials is forbidden, many buildings in Greece still contain asbestos products, which must be removed at some point in the near future. Therefore, suitable disposal sites must be found within Greece, so that the unverified disposal of asbestos waste in municipal waste Landfills is brought to an end. In the present work, an innovative approach to the disposal problem of asbestos wastes in Greece has been examined, through a risk assessment analysis of the inactive asbestos mine of Northern Greece and an evaluation of its suitability as a disposal site for asbestos wastes in the future. According to the research carried out, two areas (Site 1 and Site 2) inside the mine area are suitable for the construction of a disposal site for asbestos wastes. The geological investigations showed that in Site 1 and Site 2 ultrabasic rocks of ophiolite complex were prevalent, which have been intensely serpentinized and converted into the fibrous shape of serpentine (asbestos). Concentrations of hazardous substances such as heavy metals in the soil of Site 1 and Site 2 oscillate at low levels, with the exception of the concentrations of nickel and chrome which are high. The investigative work also included the collection of meteorological data and the monitoring of the water level of the artificial lake, which has developed inside the open mine. The main aim is to safely dispose asbestos wastes inside the mine, to minimize any pollution of the wider vicinity of the mine, as well as to engage in restoration activities. PMID:18029091

Gidarakos, Evangelos; Anastasiadou, Kalliopi; Koumantakis, Emmanuil; Nikolaos, Stappas

2008-05-30

182

Superfund record of decision (EPA Region 8): Williams Pipe Line Disposal Pit Superfund Site, Sioux Falls, SD, September 1994  

SciTech Connect

This decision document presents the selected remedial action for the Williams Pipe Line Disposal Pit Superfund Site (Site) in Sioux Falls, South Dakota. EPA has decided that No Action is necessary to address the Superfund contamination at the Site. A minimum or two years of quarterly groundwater monitoring will be performed to verify that unacceptable exposure will not occur in the future. This decision applies only to the Superfund Site. DENR is addressing groundwater petroleum contamination, which is exempt from regulation under CERCLA.

Not Available

1994-09-29

183

Public health assessment for Resin Disposal Site, Jefferson Borough, Allegheny County, Pennsylvania, Region 3. Cerclis No. PAD063766828. Final report  

SciTech Connect

Resin Disposal is a National Priorities List (NPL) site located approximately one-half mile west of the town of West Elizabeth in Jefferson Borough, Allegheny County, Pennsylvania. The landfill waste is chemically and physically heterogeneous but generally contains elevated concentrations of benzene, styrene, naphthalene and lead. Approximately 85,000 tons of waste were deposited in the landfill. Site soils, groundwater, surface water, sediment and seeps are contaminated with volatile organic compounds and other chemicals. The Resin Disposal site currently represents an indeterminate public health hazard since comprehensive data are not available for all environmental media to which humans may be exposed.

Not Available

1994-01-06

184

Development and comparison of five site-specific biosphere models for safety assessment of radioactive waste disposal  

Microsoft Academic Search

This paper describes the development and application of site-specific biosphere models that might be used for assessment of potential exposures in the framework of performance assessment studies of nuclear waste disposals. Model development follows the Reference Biosphere Methodology that has been set up in the framework of the BIOMASS study. In this paper, the application is to real sites at

G. Prhl; G. Olyslaegers; B. Kanyar; P. Pinedo; U. Bergstrm; S. Mobbs; K. Eged; T. Katona; I. Simn; U. B. Hallberg; Q. Chen; R Kowe; T. Zeevaert

2005-01-01

185

PAST, PRESENT, AND ANTICIPATED LOW-LEVEL RADIOACTIVE WASTE DISPOSAL VOLUMES AND CHARACTERISTICS AT THE NEVADA TEST SITE (NTS)  

Microsoft Academic Search

The Nevada Test Site (NTS) has been identified in recent, national U.S. Department of Energy (DOE) reports as playing a key role in the future disposal of low-level radioactive waste (LLW) originating from waste management, site remediation, and other programs of the DOE Complex. The potential volumes and characteristics of these wastes -- as well as their proposed shipment to

E. J. Bentz; C. B. Bentz; T. D. O'Hora

186

Impact of Construction Waste Disposal Charging Scheme on work practices at construction sites in Hong Kong.  

PubMed

Waste management in the building industry in Hong Kong has become an important environmental issue. Particularly, an increasing amount of construction and demolition (C&D) waste is being disposed at landfill sites. In order to reduce waste generation and encourage reuse and recycling, the Hong Kong Government has implemented the Construction Waste Disposal Charging Scheme (CWDCS) to levy charges on C&D waste disposal to landfills. In order to provide information on the changes in reducing waste generation practice among construction participants in various work trades, a study was conducted after 3 years of implementation of the CWDCS via a structured questionnaire survey in the building industry in Hong Kong. The study result has revealed changes with work flows of the major trades as well as differentiating the levels of waste reduced. Three building projects in the public and private sectors were selected as case studies to demonstrate the changes in work flows and the reduction of waste achieved. The research findings reveal that a significant reduction of construction waste was achieved at the first 3 years (2006-2008) of CWDCS implementation. However, the reduction cannot be sustained. The major trades have been influenced to a certain extent by the implementation of the CWDCS. Slight improvement in waste management practices was observed, but reduction of construction waste in the wet-finishing and dry-finishing trades has undergone little improvement. Implementation of the CWDCS has not yet motivated subcontractors to change their methods of construction so as to reduce C&D waste. PMID:23122205

Yu, Ann T W; Poon, C S; Wong, Agnes; Yip, Robin; Jaillon, Lara

2013-01-01

187

Definition of intrusion scenarios and example concentration ranges for the disposal of near-surface waste at the Hanford Site  

SciTech Connect

The US Department of Energy (DOE) is in the process of conducting performance assessments of its radioactive waste sites and disposal systems to ensure that public health and safety are protected, the environment is preserved, and that no remedial actions after disposal are required. Hanford Site low-level waste performance assessments are technical evaluations of waste sites or disposal systems that provide a basis for making decisions using established criteria. The purpose of this document is to provide a family of scenarios to be considered when calculating radionuclide exposure to individuals who may inadvertently intrude into near-surface waste disposal sites. Specific performance assessments will use modifications of the general scenarios described here to include additional site/system details concerning the engineering design, waste form, inventory, and environmental setting. This document also describes and example application of the Hanford-specific scenarios in the development of example concentration ranges for the disposal of near-surface wastes. The overall goal of the example calculations is to illustrate the application of the scenarios in a performance assessment to assure that people in the future cannot receive a dose greater than an established limit. 24 refs., 2 figs., 5 tabs.

Aaberg, R.L.; Kennedy, W.E. Jr.

1990-10-01

188

The performance assessment impacts of disposal of high-moisture, low-level radioactive waste at the Nevada Test Site  

SciTech Connect

A panel of independent scientists was convened by the Department of Energy to assess the performance impacts of disposal of low-level radioactive waste from the Fernald Environmental Management Project. This waste stream was involved in a transportation incident in December 1997. A resulting outgrowth of investigations of the transportation incident was the recognition that the waste was transported and disposed in stress-fractured metal boxes and some of the waste contained excess moisture (high volumetric water contents). The panel was charged with determining whether disposal of this waste in the Area 5 radioactive waste management site on the Nevada Test Site has impacted the conclusions of the completed performance assessment. Three questions were developed by the panel to assess performance impacts: (1) the performance impacts of reduced container integrity, (2) the impact of reduced container integrity on subsidence of waste in the disposal pits and (3) the performance impacts of excess moisture. No performance or subsidence impacts were noted from disposal of the Fernald waste. The impacts of excess moisture were assessed through simulation modeling of the movement of moisture in the vadose zone assuming high water contents (wet waste) for different percentages of the waste inventory. No performance impacts were noted for either the base-case scenario (ambient conditions) or a scenario involving subsidence and flooding of the waste cells. The absence of performance impacts results form the extreme conservatism used in the Area 5-performance assessment and the robust nature of the disposal site.

Crowe, B.M.; Hansen, W. [Los Alamos National Lab., NM (United States); Hechnova, A. [Univ. of Nevada, Las Vegas, NV (United States). Harry Reid Center of Environmental Studies; Jacobson, R. [Desert Research Inst., Reno, NV (United States); Voss, C. [Golder Associates, Inc. (United States); Waters, R. [Sandia National Labs., Albuquerque, NM (United States); Sully, M.; Levitt, D. [Bechtel Nevada, Las Vegas, NV (United States)

1999-03-01

189

Recommended Radiation Protection Practices for Low-Level Waste Disposal Sites  

SciTech Connect

The United States Nuclear Regulatory Commission contracted with Pacific Northwest Laboratory (PNL) to provide technical assistance in estsblishing operational guidelines, with respect to radiation control programs and methods of minimizing occupational radiation exposure, at Low-Level Waste (LLW) dis- posal sites. The PNL, through site visits, evaluated operations at LLW dis- posal sites to determine the adequacy of current practices in maintaining occupational exposures as low as is reasonably achievable (ALARA). The data sought included the specifics of: ALARA programs, training programs, external exposure control , internal exposure control , respiratory protection, survei 1 - lance, radioactive waste management, facilities and equipment, and external dose analysis. The results of the study indicated the following: The Radiation Protection and ALARA programs at the three commercial LLW disposal sites were observed to be adequate in scope and content compared to similar programs at other types of nuclear facilities. However, it should be noted that there were many areas that could be improved upon to help ensure the health and safety of the occupa- tionally exposed individuals. As a result, radiation protection practices were recommended with related rationales in order to reduce occupational exposures as far below specified radiation limits as is reasonably achievable. In addition, recommendations were developed for achieving occupational exposure ALARA under the Regulatory Requirements issued in 10 CFR Part 61.

D. E. Hadlock, C. D. Hooker, W. N. Herrington, R. L. Gilchrist

1983-12-01

190

Introduction to Special Section on Geophysical Investigations of Proposed Radioactive Waste Disposal Sites  

NASA Astrophysics Data System (ADS)

A symposium on "Geophysical Investigations of Proposed Radioactive Waste Disposal Sites" was held at the Fall Meeting of the American Geophysical Union, December 13, 1982. Since then, five of the papers presented at the symposium have been published in the Journal of Geophysical Research and an additional six papers are included in this issue. Three of the current papers involve geophysical research at Yucca Mountain, Nevada; two papers are on subsurface structure and fracturing of the Strath-Halladale granite in northern Scotland, a prime candidate for rad waste storage in the United Kingdom; and a general paper is included on the application of various geophysical methods for characterizing all the potential storage sites in the United States under consideration by the U.S. Department of Energy. In 1982, the following nine sites in the United States (Figure 1) were under consideration by the U.S. Department of Energy for the first U.S. repository of high-level radioactive waste (HLW). The host rock at each site is noted in parentheses (from NW to SE): Hanford, Washington (Miocene basalt flows); Yucca Mountain, Nevada (Tertiary tuff); Davis Canyon, Utah, (bedded salt); Lavender Canyon, Utah (bedded salt); Deaf Smith, Texas (Permian bedded salt); Swisher County, Texas (Permian bedded salt); Vacherie dome, Louisiana (domal salt); Richton dome, Mississippi (domal salt); and Cypress Creek dome, Mississippi (domal salt)

Oliver, H. W.

1987-07-01

191

Regulatory Framework for Salt Waste Disposal and Tank Closure at the Savannah River Site - 13663  

SciTech Connect

The end of the Cold War has left a legacy of approximately 37 million gallons of radioactive waste in the aging waste tanks at the Department of Energy's Savannah River Site (SRS). A robust program is in place to remove waste from these tanks, treat the waste to separate into a relatively small volume of high-level waste and a large volume of low-level waste, and to actively dispose of the low-level waste on-site and close the waste tanks and associated ancillary structures. To support performance-based, risk-informed decision making and to ensure compliance with all regulatory requirements, the U.S. Department of Energy (DOE) and its current and past contractors have worked closely with the South Carolina Department of Health and Environmental Control (SCDHEC), the U.S. Environmental Protection Agency (EPA) and the Nuclear Regulatory Commission (NRC) to develop and implement a framework for on-site low-level waste disposal and closure of the SRS waste tanks. The Atomic Energy Act of 1954, as amended, provides DOE the authority to manage defense-related radioactive waste. DOE Order 435.1 and its associated manual and guidance documents detail this radioactive waste management process. The DOE also has a requirement to consult with the NRC in determining that waste that formerly was classified as high-level waste can be safely managed as either low-level waste or transuranic waste. Once DOE makes a determination, NRC then has a responsibility to monitor DOE's actions in coordination with SCDHEC to ensure compliance with the Title 10 Code of Federal Regulations Part 61 (10CFR61), Subpart C performance objectives. The management of hazardous waste substances or components at SRS is regulated by SCDHEC and the EPA. The foundation for the interactions between DOE, SCDHEC and EPA is the SRS Federal Facility Agreement (FFA). Managing this array of requirements and successfully interacting with regulators, consultants and stakeholders is a challenging task but ensures thorough and thoughtful processes for disposing of the SRS low-level waste and the closure of the tank farm facilities. (authors)

Thomas, Steve; Dickert, Ginger [Savannah River Remediation LLC, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River Remediation LLC, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01

192

1997 Hanford site report on land disposal restrictions for mixed waste  

SciTech Connect

The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tn-Party Agreement) Milestone M-26-00 (Ecology et al, 1989). The text of this milestone is below. ''LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the U.S. Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration of other action plan milestones and will not become effective until approved by the U.S. Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: Waste characterization plan; Storage report; Treatment report; Treatment plan; Waste minimization plan; A schedule depicting the events necessary to achieve full compliance with LDR requirements; and A process for establishing interim milestones.

Black, D.G.

1997-04-07

193

Long-Term Performance of Uranium Tailings Disposal Cells - 13340  

SciTech Connect

Recently, there has been interest in the performance and evolution of Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell covers because some sites are not compliant with groundwater standards. Field observations of UMTRA disposal cells indicate that rock covers tend to become vegetated and that saturated conductivities in the upper portion of radon barriers may increase due to freeze/thaw cycles and biointrusion. This paper describes the results of modeling that addresses whether these potential changes and transient drainage of moisture in the tailings affect overall performance of the disposal cells. A numerical unsaturated/saturated 3-dimensional flow model was used to simulate whether increases in saturated conductivities in radon barriers with rock covers affect the overall performance of the disposal cells using field data from the Shiprock, NM, UMTRA site. A unique modeling approach allowed simulation with daily climatic conditions to determine changes in moisture and moisture flux from the disposal cell. Modeling results indicated that increases in the saturated conductivity at the top of radon barrier do not influence flux from the tailings with time because the tailings behave similar hydraulically to the radon barrier. The presence of a thin layer of low conductivity material anywhere in the cover or tailings restricts flux in the worst case to the saturated conductivity of that material. Where materials are unsaturated at depth within the radon barrier of tailings slimes, conductivities are typically less than 10{sup -8} centimeters per second. If the low conductivity layer is deep within the disposal cell, its saturated properties are less likely to change with time. The significance of this modeling is that operation and maintenance of the disposal cells can be minimized if they are allowed to progress to a natural condition with some vegetation and soil genesis. Because the covers and underlying tailings have a very low saturated hydraulic conductivity after transient drainage, eventually the amount of moisture leaving the tailings has a negligible effect on groundwater quality. Although some of the UMTRA sites are not in compliance with the groundwater standards, the explanation may be legacy contamination from mining, or earlier higher fluxes from the tailings or unlined processing ponds. Investigation of other legacy sources at the UMTRA sites may help explain persistent groundwater contamination. (authors)

Bostick, Kent; Daniel, Anamary; Pill, Ken [Professional Project Services, Inc., 1100 Bethel Valley Road, Oak Ridge, TN, 37922 (United States)] [Professional Project Services, Inc., 1100 Bethel Valley Road, Oak Ridge, TN, 37922 (United States); Tachiev, Georgio; Noosai, Nantaporn; Villamizar, Viviana [Florida International University, 10555 W. Flagler St., EC 2100, Miami FL, 33174 (United States)] [Florida International University, 10555 W. Flagler St., EC 2100, Miami FL, 33174 (United States)

2013-07-01

194

Disposal Site Selection Technical Appendix. Phase 2. (North and South Puget Sound).  

National Technical Information Service (NTIS)

This document is a technical appendix to both the Proposed Management Plan Report and the Environmental Impact Statement (EIS) for the Puget Sound Dredged Disposal Analysis (PSDDA) Phase II study covering north and south Puget Sound. Results of disposal s...

D. Jamison D. Kendall J. Malek P. Ehlers

1989-01-01

195

Geologic and hydrologic investigations of a potential nuclear waste disposal site at Yucca Mountain, southern Nevada  

SciTech Connect

Yucca Mountain in southern Nye County, Nevada, has been selected by the United States Department of Energy as one of three potential sites for the nation`s first high-level nuclear waste repository. Its deep water table, closed-basin ground-water flow, potentially favorable host rock, and sparse population have made the Yucca Mountain area a viable candidate during the search for a nuclear waste disposal site. Yucca Mountain, however, lies within the southern Great Basin, a region of known contemporary tectonism and young volcanic activity, and the characterization of tectonism and volcanism remains as a fundamental problem for the Yucca Mountain site. The United States Geological Survey has been conducting extensive studies to evaluate the geologic setting of Yucca Mountain, as well as the timing and rates of tectonic and volcanic activity in the region. A workshop was convened by the Geologic Survey in Denver, Colorado, on August 19, 20, and 21, 1985, to review the scientific progress and direction of these studies. Considerable debate resulted. This collection of papers represents the results of some of the studies presented at the workshop, but by no means covers all of the scientific results and viewpoints presented. Rather, the volume is meant to serve as a progress report on some of the studies within the Geological Survey`s continuing research program toward characterizing the tectonic framework of Yucca Mountain. Individual papers were processed separately for the data base.

Carr, M.D.; Yount, J.C. (eds.)

1988-12-31

196

Siting Study for the Remote-Handled Low-Level Waste Disposal Project  

Microsoft Academic Search

The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose

Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

2010-01-01

197

Design and operation of a low-level solid-waste disposal site at Los Alamos  

Microsoft Academic Search

Approximately 185000 cu m of low level and transuranic radioactive solid waste, were disposed of by onsite shallow land burial. Procedures and facilities were designed and evaluated in the areas of waste acceptance, treatment and storage, disposal, traffic control, and support systems. The methodologies assuring the proper management and disposal of radioactive solid waste are summarized.

K. A. Balo; N. E. Wilson; J. L. Warren

1982-01-01

198

Corrective Action Decision Document/Closure Report for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada (Revision 0) with ROTC 1 and 2  

SciTech Connect

The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation for closure of CAU 137 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from February 28 through August 17, 2006, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites. The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective process: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent. Provide sufficient information and data to complete appropriate corrective actions. ROTC-1: Downgrade FFACO UR at CAU 137, CAS 07-23-02, Radioactive Waste Disposal Site to an Administrative UR. ROTC-2: Downgrade FFACO UR at CAU 137, CAS 01-08-01, Waste Disposal Site to an Administrative UR.

Krauss, Mark J

2007-03-01

199

CENSUS AND STATISTICAL CHARACTERIZATION OF SOIL AND WATER QUALITY AT ABANDONED AND OTHER CENTRALIZED AND COMMERCIAL DRILLING-FLUID DISPOSAL SITES IN LOUISIANA, NEW MEXICO, OKLAHOMA, AND TEXAS  

Microsoft Academic Search

Commercial and centralized drilling-fluid disposal (CCDD) sites receive a portion of spent drilling fluids for disposal from oil and gas exploration and production (E&P) operations. Many older and some abandoned sites may have operated under less stringent regulations than are currently enforced. This study provides a census, compilation, and summary of information on active, inactive, and abandoned CCDD sites in

Alan R. Dutton; H. Seay Nance

2003-01-01

200

Siting a municipal solid waste disposal facility, Part One: An evaluation of different scenarios for a site selection procedure.  

PubMed

This study includes an application of the first two phases of a new three-phased decision-making structure that was developed to overcome the problems related to ecological safety and social justice in site selection applications. It was conducted on a current site selection problem related to the municipal solid waste disposal facilities in Kocaeli, the most industrialized region of Turkey. In order to assess the deficiencies of the legal site selection procedures related to ecological safety, two different decision tree modes were applied separately. The first mode ("Legislation") concerns the current buffer zone applications given in the regulations, while the second one ("Proposed") includes the applications of the new decision-making structure proposed in this study. Since it was assumed that the subjective tendencies of the decision makers on the weightings would have a significant effect on the final decision, these two modes were assessed by employing two different weighting models. The results were obtained from all of the scenarios related to selection of suitable sites with three different area requirements (15, 250, and 500 acres) for the solid wastes generated in the Kocaeli region. The results showed that the possible changes in the decision structure could cause significant differences in the final decision related to selection of the most suitable sites. The most highest and lowest differences were at the "Legislation" mode for 15 acres and 500 acres, respectively. Furthermore, the results obtained in the study showed that the possible differentiations in the criteria weightings could also cause significant differences in the suitability ranking. Therefore, to get a reliable final decision, a statistical assessment of these differentiations should be made. Implications: The results showed that the possible changes in the decision structure could cause significant differences in the final decision related to selection of the most suitable sites. Furthermore, the results obtained in the study showed that the possible differentiations in the criteria weightings could also cause significant differences in the suitability ranking. Therefore, to get a reliable final decision, a statistical assessment of these differentiations should be made. PMID:24010368

Korucu, M Kemal; Arslan, Ozan; Karademir, Aykan

2013-08-01

201

Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong  

NASA Astrophysics Data System (ADS)

Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr+ ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10-2 g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

Setiawan, Budi; Mila, Oktri; Safni

2014-03-01

202

Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

SciTech Connect

Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval.

Alfred Wickline

2007-06-01

203

Environmental geophysics at Kings Creek Disposal Site and 30th Street Landfill, Aberdeen Proving Ground, Maryland  

SciTech Connect

Geophysical studies on the Bush River Peninsula in the Edgewood Area of Aberdeen Proving Ground, Maryland, delineate landfill areas and provide diagnostic signatures of the hydrogeologic framework and possible contaminant pathways. These studies indicate that, during the Pleistocene Epoch, alternating stands of high and low seal levels resulted in a complex pattern of shallow channel-fill deposits in the Kings Creek area. Ground-penetrating radar studies reveal a paleochannel greater than 50 ft deep, with a thalweg trending offshore in a southwest direction into Kings Creek. Onshore, the ground-penetrating radar data indicate a 35-ft-deep branch to the main channel, trending to the north-northwest directly beneath the 30th Street Landfill. Other branches are suspected to meet the offshore paleochannel in the wetlands south and east of the 30th Street Landfill. This paleochannel depositional system is environmentally significant because it may control the shallow groundwater flow regime beneath the site. Electromagnetic surveys have delineated the pre-fill lowland area currently occupied by the 30th Street Landfill. Magnetic and conductive anomalies outline surficial and buried debris throughout the study area. On the basis of geophysical data, large-scale dumping has not occurred north of the Kings Creek Disposal Site or east of the 30th Street Landfill.

Davies, B.E.; Miller, S.F.; McGinnis, L.D.; Daudt, C.R.; Thompson, M.D.; Stefanov, J.E.; Benson, M.A.; Padar, C.A.

1995-01-01

204

Health effects of hazardous chemical waste disposal sites in New Jersey and in the United States: a review  

SciTech Connect

The hazardous chemical waste disposal issue is a widespread problem. Large quantities of chemical wastes have been produced by the chemical industries in the past forty years. Estimates now number disposal sites in the United States at least 30,000. The public and scientists have grown increasingly concerned about the effects of these waste disposal sites not only on the environment, but also on the human body. In this article, we review the number of hazardous chemical waste disposal sites (HCWDS), their construction, difficulties in defining their contents, and the establishment of the Superfund Act. We then discuss various studies in the literature that have attempted to define adverse health effects of HCWDS, particularly those examining Love Canal and sites in New Jersey. In our conclusions, we note the difficulties in establishing direct causal links between HCWDS and dangerous health effects. We suggest that more epidemiological studies are needed, with improved methodology for gathering complete data and studying large samples. Both positive and negative findings of epidemiological studies are important. Positive results will substantiate an association of health effects with HCWDS. Negative results may reduce the concerns of people living near HCWDS. Future investigators need sufficient information about HCWDS materials, possible routes of exposure, and measurements of exposure, as well as sufficient statistical power to detect even modest associations of health effects with HCWDS exposure.71 references.

Najem, G.R.; Cappadona, J.L. (Department of Preventive Medicine and Community Health, New Jersey Medical School, University of Medicine and Dentistry of New Jersey, Newark (United States))

1991-11-01

205

Strategy for identifying natural analogs of the long-term performance of low-level waste disposal sites  

SciTech Connect

The US Department of Energy's Low-Level Waste (LLW) Management Program has asked Pacific Northwest Laboratory (PNL) to explore the feasibility of using natural analogs of anticipated waste site and conditions to help validate predictions of the performance of LLW disposal sites. Current regulations require LLW facilities to control the spread of hazardous substances into the environment for at least the next 500 years. Natural analog studies can provide information about processes affecting waste containment that cannot be fully explored through laboratory experimentation and modeling because of the extended period of required performance. For LLW applications, natural analogs include geochemical systems, pedogenic (soil formation) indicators, proxy climate data, and ecological and archaeological settings that portray long-term changes in disposal site environments and the survivability of proposed waste containment materials and structures. Analog data consist of estimates of performance assessment (PA) model input parameters that define possible future environmental states of waste sites, validation parameters that can be predicted by PA models, and descriptive information that can build public confidence in waste disposal practices. This document describes PNL's overall stategy for identifying analogs for LLW disposal systems, reviews lessons learned from past analogs work, outlines the findings of the workshop, and presents examples of analog studies that workshop participants found to be applicable to LLW performance assessment. The lessons from the high-level waste analogs experience and workshop discussions will be used to develop detailed study plans during FY 1990. 39 refs.

Chatters, J.C.; Waugh, W.J.; Foley, M.G.; Kincaid, C.T.

1990-07-01

206

Comment and response document for the long-term surveillance plan for the Collins Ranch Disposal Site, Lakeview, Oregon  

SciTech Connect

This document contains comments made by the U.S. Nuclear Regulatory Commission addressing their concerns over the long-term monitoring program for the Collins Ranch Disposal Site, UMTRA project. Responses are included as well as plans for implementation of changes, if any are deemed necessary.

Not Available

1994-08-01

207

Comment and response document for the long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas  

SciTech Connect

This document contains the comments made by the US Nuclear Regulatory Commission on the Department of Energy`s (DOE) Long-Term Surveillance Plan for the Falls City Disposal Site, Falls City, Texas. DOE`s responses to the comments are also included.

NONE

1996-10-01

208

77 FR 63312 - Notice of Intent: Designation of an Ocean Dredged Material Disposal Site (ODMDS) in Eastern Long...  

Federal Register 2010, 2011, 2012, 2013

...Disposal Site (ODMDS) in Eastern Long Island Sound; Connecticut, New York, and Rhode Island...ODMDS) to serve the eastern Long Island Sound region (Connecticut, New York, and Rhode...were conducted for the 2005 Long Island Sound Environmental Impact Statement that...

2012-10-16

209

Guidelines for the Selection of Sites for Disposal of Radioactive Waste on or Beneath the Ocean Floor.  

National Technical Information Service (NTIS)

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 availabl...

R. C. Searle

1979-01-01

210

Evaluation of shale hosted low-level waste disposal sites in semi-arid environments: Final report  

Microsoft Academic Search

This report covers the findings of a multidisciplinary investigation intended to delineate critical factors and concerns associated with shale hosted, low-level radioactive waste disposal sites located in semiarid environments. The investigations focus primarily upon concerns regarding the hydrology, geochemistry, and meteorology of such an environment. The studies described within this report specifically do not constitute an evaluation of any one

W. M. Roggenthen; P. H. Rahn; R. C. Arthur; J. R. Miller; W. J. Bangsund; J. Eberlin

1985-01-01

211

Three-dimensional electrical resistivity model of a nuclear waste disposal site  

SciTech Connect

A three-dimensional (3D) modeling study was completed on a very large electrical resistivity survey conducted at a nuclear waste site in eastern Washington. The acquisition included 47 pole-pole two dimensional (2D) resistivity profiles collected along parallel and orthogonal lines over an area of 850 m570 m. The data were geo-referenced and inverted using EarthImager3D (EI3D). EI3D runs on a Microsoft 32-bit operating system (e.g. WIN-2K, XP) with a maximum usable memory of 2 GB. The memory limits the size of the domain for the inversion model to 200 m200 m, based on the survey electrode density. Therefore, a series of increasing overlapping models were run to evaluate the effectiveness of dividing the survey area into smaller subdomains. The results of the smaller subdomains were compared to the inversion results of a single domain over a larger area using an upgraded form of EI3D that incorporates multi-processing capabilities and 32 GB of RAM memory. The contours from the smaller subdomains showed discontinuity at the boundaries between the adjacent models, which do not match the hydrogeologic expectations given the nature of disposal at the site. At several boundaries, the contours of the low resistivity areas close, leaving the appearance of disconnected plumes or open contours at boundaries are not met with a continuance of the low resistivity plume into the adjacent subdomain. The model results of the single large domain show a continuous monolithic plume within the central and western portion of the site, directly beneath the elongated trenches. It is recommended that where possible, the domain not be subdivided, but instead include as much of the domain as possible given the memory of available computing resources.

Rucker, Dale F.; Levitt, Marc T.; Greenwood, William J.

2009-12-11

212

Nutrient couplings between on-site sewage disposal systems, groundwaters, and nearshore surface waters of the Florida Keys  

Microsoft Academic Search

We performed a one-year study to determine the effects of on-site sewage disposal systems (OSDS, septic tanks) on the nutrient\\u000a relations of limestone groundwaters and nearshore surface waters of the Florida Keys. Monitor wells were installed on canal\\u000a residences with OSDS and a control site in the Key Deer National Wildlife Refuge on Big Pine Key. Groundwater and surface\\u000a water

Brian E. Lapointe; Julie D. O'Connell; George S. Garrett

1999-01-01

213

Comment and response document for the long-term surveillance plan for the Falls City disposal site, Falls City, Texas  

SciTech Connect

This is the Comment and Response Document dated November 1996 for the Long-Term Surveillance Plan for the Falls City Disposal Site in Falls City, Texas. The site is part of the U.S. DOE`s Uranium Mill Tailings Remedial Action Project (UMTRA). Several comments regarding the hydrology and surface erosion described in the Long-Term Surveillance Plan are addressed in this document.

NONE

1996-11-01

214

Monitoring the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site  

Microsoft Academic Search

The U.S. Department of Energy Office of Legacy Management (DOE) and the U.S. Environmental Protection Agency (EPA) collaborated on the design and monitoring of an alternative cover for the Monticello uranium mill tailings disposal cell, a Superfund site in southeastern Utah. Ground-water recharge is naturally limited at sites like Monticello where thick, fine-textured soils store precipitation until evaporation and plant

W. J. Waugh; M. K. Kastens; L. R. L. Sheader; C. H. Benson; W. H. Albright; P. S. Mushovic

2008-01-01

215

Low-level liquid waste disposal at the Savannah River Site: A large scale demonstration of saltstone  

SciTech Connect

Lysimeters are large-scale, field experiments used at the Savannah River Site (SRS) to measure the effect of percolating rainfall on the release of contaminants from wasteforms. The saltstone lysimeters described are demonstrations of a disposal concept for a low-level radioactive waste resulting from the processing of high-level defense waste for vitrification. Results from the lysimeters confirm the efficacy of the slag formulation in retaining chromium and technetium. Lysimeter results were also useful in validating mathematical models used in predicting environmental effects of saltstone disposal in engineered vaults. 7 refs., 3 figs., 4 tabs.

Clark, S.B.; Wilhite, E.L.

1990-01-01

216

Low-level liquid waste disposal at the Savannah River Site: A large scale demonstration of saltstone  

SciTech Connect

Lysimeters are large-scale, field experiments used at the Savannah River Site (SRS) to measure the effect of percolating rainfall on the release of contaminants from wasteforms. The saltstone lysimeters described are demonstrations of a disposal concept for a low-level radioactive waste resulting from the processing of high-level defense waste for vitrification. Results from the lysimeters confirm the efficacy of the slag formulation in retaining chromium and technetium. Lysimeter results were also useful in validating mathematical models used in predicting environmental effects of saltstone disposal in engineered vaults. 7 refs., 3 figs., 4 tabs.

Clark, S.B.; Wilhite, E.L.

1990-12-31

217

Corrective Action Decision Document/Closure Report for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, in Areas 2, 3, 9, and 20 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended February 2008). Corrective Action Unit 545 is comprised of the following eight Corrective Action Sites (CASs): 02-09-01, Mud Disposal Area 03-08-03, Mud Disposal Site 03-17-01, Waste Consolidation Site 3B 03-23-02, Waste Disposal Site 03-23-05, Europium Disposal Site 03-99-14, Radioactive Material Disposal Area 09-23-02, U-9y Drilling Mud Disposal Crater 20-19-01, Waste Disposal Site While all eight CASs are addressed in this CADD/CR, sufficient information was available for the following three CASs; therefore, a field investigation was not conducted at these sites: For CAS 03-08-03, though the potential for subsidence of the craters was judged to be extremely unlikely, the data quality objective (DQO) meeting participants agreed that sufficient information existed about disposal and releases at the site and that a corrective action of close in place with a use restriction is recommended. Sampling in the craters was not considered necessary. For CAS 03-23-02, there were no potential releases of hazardous or radioactive contaminants identified. Therefore, the Corrective Action Investigation Plan for CAU 545 concluded that: Sufficient information exists to conclude that this CAS does not exist as originally identified. Therefore, there is no environmental concern associated with CAS 03-23-02. This CAS is closed with no further action. For CAS 03-23-05, existing information about the two buried sources and lead pig was considered to be sufficient, and safety concerns existed about the stability of the crater component. Therefore, a corrective action of close in place with a use restriction is recommended, and sampling at the site was not considered necessary. The purpose of this CADD/CR is to provide justification and documentation to support the recommendation for closure of CAU 545 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from August 20 through November 02, 2007, as set forth in the CAU 545 Corrective Action Investigation Plan. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent. Provide sufficient information and data to complete appropriate corrective actions. The CAU 545 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels established in this CADD/CR. The results of the CAI identified no COCs at the five CASs investigated in CAU 545. As a best management practice, repair of the fence enclosing CAS 03-08-03 has been completed. Therefore, the DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: Close in place COCs at CASs 03-08-03 and 03-23-05 with use restrictions. No further corrective action for CAU 545. No Corrective Action Plan. Corrective Action Unit 545 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order. A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office is requested from the Nevada Division of Environmental Protection for closure of CAU 545.

Alfred Wickline

2008-04-01

218

Closure Report for Corrective Action Unit 356: Mud Pits and Disposal Sites, Nevada Test Site, Nevada with Errata Sheet  

SciTech Connect

This Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 356, Mud Pits and Disposal Sites, in accordance with the Federal Facility Agreement and Consent Order. This CAU is located in Areas 3 and 20 of the Nevada Test Site (NTS) approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 356 consists of seven Corrective Action Sites (CASs): 03-04-01, Area 3 Change House Septic System; 03-09-01, Mud Pit Spill Over; 03-09-03, Mud Pit; 03-09-04, Mud Pit; 03-09-05, Mud Pit; 20-16-01, Landfill; and 20-22-21, Drums. This CR identifies and rationalizes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office's (NNSA/NV's) recommendation that no further corrective action and closure in place is deemed necessary for CAU 356. This recommendation is based on the results of field investigation/closure activities conducted November 20, 2001, through January 3, 2002, and March 11 to 14, 2002. These activities were conducted in accordance with the Streamlined Approach for Environmental Restoration Plan (SAFER) for CAU 356. For CASs 03-09-01, 03-09-03, 20-16-01, and 22-20-21, analytes detected in soil during the corrective action investigation were evaluated against Preliminary Action Levels (PALs) and it was determined that no Contaminants of Concern (COCs) were present. Therefore, no further action is necessary for the soil at these CASs. For CASs 03-04-01, 03-09-04, and 03-09-05, analytes detected in soil during the corrective action investigation were evaluated against PALs and identifies total petroleum hydrocarbons (TPHs) and radionuclides (i.e., americium-241 and/or plutonium 239/240) as COCs. The nature, extent, and concentration of the TPH and radionuclide COCs were bounded by sampling and shown to be relatively immobile. Therefore, closure in place is recommended for these CASs in CAU 356. Further, use restrictions are not required at this CAU beyond the NTS use restrictions identified in the SAFER Plan. In addition, the septic tank associated with CAU 356 will be closed in accordance with applicable regulations.

NNSA /NV

2002-11-12

219

SOIL DISPOSAL OF RADIOACTIVE WASTES AT ORNL: CRITERIA AND TECHNIQUES OF SITE SELECTION AND MONITORING  

Microsoft Academic Search

The ability of soil to remove and retain the but of the fission product ; cations from aqueous solution is used as the basis for disposal of large ; volumes of intermediate level wastes. An experimental system consisting of three ; 1 million gal disposal pits has been developed at ORNL and through December 1858, ; received a total of

K. E. Cowser; F. L. Parker

1958-01-01

220

Census and Statistical Characterization of Soil and Water Quality at Abandoned and Other Centralized and Commercial Drilling-Fluid Disposal Sites in Louisiana, New Mexico, Oklahoma, and Texas.  

National Technical Information Service (NTIS)

Commercial and centralized drilling-fluid disposal (CCDD) sites receive a portion of spent drilling fluids for disposal from oil and gas exploration and production (E&P) operations. Many older and some abandoned sites may have operated under less stringen...

A. R. Dutton H. S. Nance

2003-01-01

221

Use of geophysical monitoring systems and data to identify and designate ocean sites for disposal of low-level radioactive wastes. Final report  

SciTech Connect

The report provides information applicable to using geophysical instruments and survey methods, and the data collected, in the process of designating sites for ocean disposal of low level radioactive wastes. The geophysical ocean survey methods described in the report are envisioned as preceding any sediment sampling required to characterize disposal sites.

Neiheisel, J.

1988-07-01

222

1990 State-by-State assessment of low-level radioactive wastes received at commercial disposal sites  

SciTech Connect

Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This annual report provides both national and state-specific disposal data on low-level radioactive wastes. Data in this report are categorized according to disposal site, generator category, waste class, volume, and activity. Included in this report are tables showing a distribution of wastes by state for 1990 and a comparison of waste volumes by state for 1986 through 1990; also included is a list of all commercial nuclear power reactors in the United States as of December 31, 1990. In this year's report, a distinction has been made between low-level radioactive waste shipped directly by generators for disposal and that which was handled by an intermediary. 5 refs., 4 tabs.

Fuchs, R.L.; Culbertson-Arendts, K.

1991-09-01

223

Development of a prototype plan for the effective closure of a waste disposal site in Los Alamos, New Mexico  

SciTech Connect

The purpose of this study was to develop a prototype plan for the effective closure and stabilization of a semiarid low-level waste disposal site. This prototype plan will provide demonstrated closure techniques for a trench in a disposal site at Los Alamos based on previous shallow land burial (SLB) field research both at the Los Alamos Experimental Engineered Test Facility (EETF), and at a waste disposal area at Los Alamos. The accuracy of modeling soil water storage by two hydrologic models was tested by comparing simulation results with field measurements of soil moisture in eight experimental landfill cover systems at Waste Disposal Area B having a range of well-defined soil profiles and vegetative covers. Regression analysis showed that one of the two models tested represented soil moisture more accurately than the second model. The accuracy of modeling all of the parameters of the water balance equation was then evaluated using field data from the Integrated Systems Demonstration plots at the EETF. Optimized parameters were developed for one model to describe observed values of deep percolation, evapotranspiration, and runoff from the field plots containing an SLB trench cap configuration.

Nyhan, J.; Barnes, F.

1989-02-01

224

Arsenic concentration in porewater of an alkaline coal ash disposal site: Roles of siderite precipitation/dissolution and soil cover.  

PubMed

The geochemical behavior of As in porewaters of an alkaline coal ash disposal site was investigated using multilevel samplers. The disposal site was in operation from 1983 until 1994 and was covered with 0.3-0.5m thick soils in 2001 when this study was initiated. Sequential extraction analyses and batch leaching experiments were also performed using the coal ash samples collected from the disposal site. The results suggest the important roles of siderite (FeCO(3)) precipitation/dissolution and soil cover, which have been ignored previously. Arsenic levels in the porewater were very low (average of 10microgL(-1)) when the site was covered with soil due to coprecipitation with siderite. The soil cover enabled the creation of anoxic conditions, which raised the Fe concentration by the reductive dissolution of Fe-(hydr)oxides. Because of the high alkalinity generated from the alkaline coal ash, even a small increase in the Fe concentration (0.66mgL(-1) on average) could cause siderite precipitation. When the soil cover was removed, however, an oxidizing condition was created and triggered the precipitation of dissolved Fe as (hydr)oxides. As a result, the dissolution of previously precipitated As-rich siderite caused higher As concentration in the porewater (average of 345microgL(-1)). PMID:19682722

Kim, Kangjoo; Park, Sung-Min; Kim, Jinsam; Kim, Seok-Hwi; Kim, Yeongkyoo; Moon, Jeong-Tae; Hwang, Gab-Soo; Cha, Wang-Seog

2009-09-01

225

Bulk Transport of Waste Slurries to Inland and Ocean Disposal Sites.  

National Technical Information Service (NTIS)

This is the summary report of a three volume study principally concerned with the development of regional land and ocean pipeline disposal systems for digested sewage sludge and maintenance dredgings.

E. J. Wasp T. L. Thompson P. E. Snoek J. P. Kenny J. C. Carney

1969-01-01

226

Application of organic tracers in characterizing the greater confinement disposal test at the Nevada Test Site  

SciTech Connect

The Greater Confinement Disposal Test (GCDT) is a research project investigating the feasibility of augered-shaft disposal of low-level radioactive waste considered unsuitable for shallow land burial. Gaseous diffusion of radionuclides through alluvial sediments is considered the primary contaminant migration process. Volatile halocarbon tracers are released in the subsurface and their migration is monitored to determine media effective diffusion coefficients, tortuosity values, and sorption terms. Design and instrumentation of the emplacement and monitoring shafts of the disposal facility are detailed. Instrumentation includes a three-dimensional array of soil-air sample stations encircling the disposal waste. Recirculation flow lines minimize induced advection in the alluvial matrix due to tracer sample collection. 6 references, 5 figures, 2 tables.

Olson, M.C.

1985-01-01

227

Radionuclide distributions around a low-level radioactive waste disposal pond and ditch system at the Hanford Site  

Microsoft Academic Search

Chemical reprocessing of spent nuclear fuels at the US Department of Energy (DOE) Hanford Site has generated large volumes of low-level radioactive liquid effluents. The majority of these effluents have been used strictly for cooling or other support functions and have been discharged to ditches and ponds. The 216-U-10 (U) Pond and 216-Z-19 (Z-19) Ditch are two such disposal facilities

1983-01-01

228

Addendum to Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site  

SciTech Connect

This report summarizes efforts to complete an addendum analysis to the first iteration of the Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site (Composite Analysis). This document describes the background and performance objectives of the Composite Analysis and this addendum analysis. The methods used, results, and conclusions for this Addendum analysis are summarized, and recommendations are made for work to be undertaken in anticipation of a second analysis.

Bergeron, Marcel P.; Freeman, Eugene J.; Wurstner, Signe K.; Kincaid, Charles T.; Coony, Mike M.; Strenge, Dennis L.; Aaberg, Rosanne L.; Eslinger, Paul W.

2001-09-28

229

Composite analysis for low-level waste disposal in the 200 area plateau of the Hanford Site  

SciTech Connect

This report presents the first iteration of the Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site (Composite Analysis) prepared in response to the U.S. Department of Energy Implementation Plan for the Defense Nuclear Facility Safety Board Recommendation 94-2. The Composite Analysis is a companion document to published analyses of four active or planned low-level waste disposal actions: the solid waste burial grounds in the 200 West Area, the solid waste burial grounds in the 200 East Area, the Environmental Restoration Disposal Facility, and the disposal facilities for immobilized low-activity waste. A single Composite Analysis was prepared for the Hanford Site considering only sources on the 200 Area Plateau. The performance objectives prescribed in U.S. Department of Energy guidance for the Composite Analysis were 100 mrem in a year and examination of a lower dose (30 mrem in a year) to ensure the {open_quotes}as low as reasonably achievable{close_quotes} concept is followed. The 100 mrem in a year limit was the maximum allowable all-pathways dose for 1000 years following Hanford Site closure, which is assumed to occur in 2050. These performance objectives apply to an accessible environment defined as the area between a buffer zone surrounding an exclusive waste management area on the 200 Area Plateau, and the Columbia River. Estimating doses to hypothetical future members of the public for the Composite Analysis was a multistep process involving the estimation or simulation of inventories; waste release to the environment; migration through the vadose zone, groundwater, and atmospheric pathways; and exposure and dose. Doses were estimated for scenarios based on agriculture, residential, industrial, and recreational land use. The radionuclides included in the vadose zone and groundwater pathway analyses of future releases were carbon-14, chlorine-36, selenium-79, technetium-99, iodine-129, and uranium isotopes.

Kincaid, C.T.; Bergeron, M.P.; Cole, C.R. [and others

1998-03-01

230

Sampling and analyses of colloids at the Drigg low level radioactive waste disposal site.  

PubMed

Water samples have been extracted from inside (from standpipes) and from outside (from boreholes) of the trenches at the low level radioactive waste disposal site at Drigg in Cumbria, UK. The samples were taken anaerobically from between 8.5 and 10.0 m below the surface using a submersible pump at low flow rates to ensure that the waters in the standpipes and boreholes were maintained at constant levels. To ensure representative samples, the Eh, pH. conductivity, temperature, iron and dissolved oxygen concentrations of the waters were taken during initial purging and during sampling. The gross tritium, gross non-tritium beta, gross alpha and gamma activities of each sample were determined using suitable sample preparation and counting techniques. Samples were then anaerobically, sequentially filtered through 12 microm, 1 microm, 30 kDa and 500 Da filter membranes. The filtrates were analysed for gross alpha, gross non-tritium beta and gamma activities. SEM and STEM analyses were used to determine the colloid population. An energy dispersive analyser on the SEM was used to determine the major elements present in the colloids. UV-visible spectrophotometry, fluorescence spectrophotometry and high performance size exclusion liquid chromatography were used to analyse the waters before and after treatment with ion exchange materials to determine whether natural organic matter was present in the waters. Results showed that two major types of colloids (iron containing colloids and silicon containing colloids) were present in the waters. There were also a small number of other colloids that contain, as major elements, aluminium, calcium and chromium. Organic colloids were also present. The majority of the radioactivity in the waters was due to tritium. Waters taken from outside the trenches contained low levels of non-tritium beta activities and alpha activities which were lower than the minimum detectable amount. Waters taken from the trenches contained non-tritium beta activities and low levels of alpha emitters. Filtration of the trench waters showed that some of the alpha activity was retained by the 30 kDa and 500 Da membranes suggesting that this activity was associated with small colloids. Radioactivity was not found to be associated with colloids present in the waters taken from outside the trenches. Possible reasons for this observation could be that radionuclide bearing colloids have not yet reached the far-field or that the radionuclide concentration is diluted to below the minimum detectable amount. After concentrating two of the samples by factors of x20 and x 16 respectively, 2.4+/-0.1 and 0.6+/-0.1 Bq dm(-3) of 137Cs were measured. PMID:11993761

Warwick, P; Allinson, S; Beckett, K; Eilbeck, A; Fairhurst, A; Russel-Flint, K; Verrall, K

2002-04-01

231

Site Selection and Geological Research Connected with High Level Waste Disposal Programme in the Czech Republic.  

National Technical Information Service (NTIS)

Attempts to solve the problem of high-level waste disposal including the spent fuel from nuclear power plants have been made in the Czech Republic for over the 10 years. Already in 1991 the Ministry of Environment entitled The Czech Geological Survey to d...

J. Tomas

2003-01-01

232

Groundwater monitoring plan for the Hanford Site 200 Area Treated Effluent Disposal Facility  

Microsoft Academic Search

Seven years of groundwater monitoring at the 200 Area Treated Effluent Disposal Facility (TEDF) have shown that the uppermost aquifer beneath the facility is unaffected by TEDF effluent. Effluent discharges have been well below permitted and expected volumes. Groundwater mounding from TEDF operations predicted by various models has not been observed, and waterlevels in TEDF wells have continued declining with

DB Barnett

2000-01-01

233

Automated System for Monitoring Groundwater Levels at an Experimental Low-Level Waste Disposal Site.  

National Technical Information Service (NTIS)

One of the major problems with disposing of low-level solid wastes in the eastern United States is the potential for water-waste interactions and leachate migration. To monitor groundwater fluctuations and the frequency with which groundwater comes into c...

J. D. Newbold M. A. Bogle

1984-01-01

234

1999 Report on Hanford Site land disposal restriction for mixed waste  

SciTech Connect

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-011. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility.

BLACK, D.G.

1999-03-25

235

Gas production, composition and emission at a modern disposal site receiving waste with a low-organic content.  

PubMed

AV Milj is a modern waste disposal site receiving non-combustible waste with a low-organic content. The objective of the current project was to determine the gas generation, composition, emission, and oxidation in top covers on selected waste cells as well as the total methane (CH(4)) emission from the disposal site. The investigations focused particularly on three waste disposal cells containing shredder waste (cell 1.5.1), mixed industrial waste (cell 2.2.2), and mixed combustible waste (cell 1.3). Laboratory waste incubation experiments as well as gas modeling showed that significant gas generation was occurring in all three cells. Field analysis showed that the gas generated in the cell with mixed combustible waste consisted of mainly CH(4) (70%) and carbon dioxide (CO(2)) (29%) whereas the gas generated within the shredder waste, primarily consisted of CH(4) (27%) and nitrogen (N(2)) (71%), containing no CO(2). The results indicated that the gas composition in the shredder waste was governed by chemical reactions as well as microbial reactions. CH(4) mass balances from three individual waste cells showed that a significant part (between 15% and 67%) of the CH(4) generated in cell 1.3 and 2.2.2 was emitted through leachate collection wells, as a result of the relatively impermeable covers in place at these two cells preventing vertical migration of the gas. At cell 1.5.1, which is un-covered, the CH(4) emission through the leachate system was low due to the high gas permeability of the shredder waste. Instead the gas was emitted through the waste resulting in some hotspot observations on the shredder surface with higher emission rates. The remaining gas that was not emitted through surfaces or the leachate collection system could potentially be oxidized as the measured oxidation capacity exceeded the potential emission rate. The whole CH(4) emission from the disposal site was found to be 820 202 kg CH(4)d(-1). The total emission rate through the leachate collection system at AV Milj was found to be 211 kg CH(4)d(-1). This showed that approximately of the emitted gas was emitted through the leachate collections system making the leachate collection system an important source controlling the overall gas migration from the site. The emission pathway for the remaining part of the gas was more uncertain, but emission from open cells where waste is being disposed of or being excavated for incineration, or from horizontal leachate drainage pipes placed in permeable gravel layers in the bottom of empty cells was likely. PMID:21186118

Scheutz, Charlotte; Fredenslund, Anders M; Nedenskov, Jonas; Samuelsson, Jerker; Kjeldsen, Peter

2011-05-01

236

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

SciTech Connect

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.

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

1996-01-01

237

Postconstruction report of the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Environmental Restoration Program.  

National Technical Information Service (NTIS)

Remedial actions conducted under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) were completed at the Y-12 United Nuclear Corporation (UNC) Disposal Site in August 1992. The purpose of this Postconstruct...

L. B. Oakley J. K. Siberell T. L. Voskuil

1993-01-01

238

State Data Related to Abandoned Centralized and Commercial Drilling-Fluid Disposal Sites in Louisiana, New Mexico, Oklahoma, and Texas. Executive Summary.  

National Technical Information Service (NTIS)

This 2003 Spring Semi-Annual Report contains a summary of the Final Technical Report being prepared for the Soil Remediation Requirements at Commercial and Centralized Drilling-Fluid Disposal (CCDD) Sites project funded by the United States Department of ...

H. S. Nance A. R. Dutton

2003-01-01

239

Health assessment for Douglassville Disposal Site, Douglassville, Berks County, Union Township, Pennsylvania, Region 3. CERCLIS No. PAD002384865. Preliminary report  

SciTech Connect

The Douglassville Disposal site is on the National Priorities List. Between the years 1941 and 1986, a waste oil recycling (1941-1986) and waste oil refining (1979-1986) operation was conducted on the site. Contamination on-site consists of lead, arsenic, barium, cadmium, chromium, benzene, toluene, xylenes, antimony, cobalt, manganese, nickel, 1,1-dichloroethane, 1-2-dichloroethane, tetrachloroethene, trichloroethene, vinyl chloride, trans-1,2-dichloroethene, non-carcinogenic polycyclic aromatic hydrocarbons (PAHs), carcinogenic PAHs, and polychlorinated biphenyls (PCBs). Contamination off-site consists of lead in water from several domestic drinking water wells, copper, and nickel. The site is of public health concern because of the risk to human health resulting from probable exposure to hazardous substances at concentrations that may result in adverse human health effects and the physical hazards associated with the site. Human exposure to lead, PCBs, PAHs, and other site contaminants may occur by contact with on-site soils and sediments, by ingestion of contaminated groundwater, or by the consumption of contaminated biota.

Not Available

1989-04-17

240

Screen printed electrodes provide micro-domain sites for fabricating disposable electro-catalytic ensembles  

Microsoft Academic Search

We demonstrate that bespoke screen printed electrodes which are basal plane-like in nature can be used as a template to produce randomly dispersed electro-catalytic micro-domains for analytical sensing purposes. Proof-of-concept is shown for the case of copper ensembles for nitrate detection and palladium ensembles for hydrazine sensing. The advantageous disposable nature of the ensemble precludes the need of pre-treatment between

Nadeem A. Choudhry; Rashid O. Kadara; Norman Jenkinson; Craig E. Banks

2010-01-01

241

Mapping subsurface pathways for contaminant migration at a proposed low level waste disposal site using electromagnetic methods  

SciTech Connect

Electromagnetic methods have been used to measure apparent terrain conductivity in the downstream portion of a watershed in which a waste disposal site is proposed. At that site, the pathways for waste migration in ground water are controlled by subsurface channels. The channels are identified using isocurves of measured apparent conductivity. Two upstream channel branches are found to merge into a single downstream channel which constitutes the main drainage path out of the watershed. The identification and mapping of the ground water pathways is an important contribution to the site characterization study and the pathways analysis. The direct applications of terrain conductivity mapping to the planning of the monitoring program, the hydrogeological testing, and the modeling study are demonstrated. 7 references, 4 figures.

Pin, F.G.; Ketelle, R.H.

1984-01-01

242

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH03, Shiprock, NM, July-November 1982  

SciTech Connect

A comprehensive survey of the vicinity property designated as SH03 was conducted on an intermittent basis from July 26 to November 11, 1982. At the time of the survey, three structures were located on the property - a residential trailer, the main structure, and an old gas pump housing. The lands surrounding the structures were either sparsely covered with arid vegetation or paved. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air, soil, and other material samples. No evidence of radioactive contamination was found inside the trailer. However, the results of the radiological assessment did indicate the occurrence of elevated levels of gamma, surface alpha, and radon daughter radioactivity within the main structure. The short-term radon daughter measurements exceeded the limit of 0.02 Working Level for average annual concentration including background. The assessment also indicated elevated levels of radioactivity in the outdoor environs, encompassing about 32,000 ft/sup 2/ of the grounds adjacent to and surrounding the main structure on the east, south, and west sides. The contamination appeared to be due to the presence of unprocessed uranium ore. Analysis of surface soil samples collected from the environs indicated radium concentrations in excess of the limit of 5 pCi/g above background specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Since the surface soil contamination levels exceeded the limits specified in the EPA Standard, remedial action for this vicinity site should be considered.

Flynn, K F; Justus, A L; Sholeen, C M; Smith, W H; Wynveen, R A

1984-04-01

243

Monitoring the remediation of a near shore waste disposal site in Antarctica using the amphipod Paramoera walkeri and diffusive gradients in thin films (DGTs)  

Microsoft Academic Search

The water quality of a marine embayment (Brown Bay) was monitored during the remediation of an abandoned waste disposal site at Casey Station, East Antarctica, using a combination of biomonitoring and chemical methods. The Antarctic amphipod Paramoera walkeri, in field mesocosms suspended in the water column, was deployed adjacent to the site and at two reference sites for periods of

Jonathan S. Stark; Glenn J. Johnstone; Anne S. Palmer; Ian Snape; Bronwyn L. Larner; Martin J. Riddle

2006-01-01

244

Monitoring the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site  

SciTech Connect

The U.S. Department of Energy Office of Legacy Management (DOE) and the U.S. Environmental Protection Agency (EPA) collaborated on the design and monitoring of an alternative cover for the Monticello uranium mill tailings disposal cell, a Superfund site in southeastern Utah. Ground-water recharge is naturally limited at sites like Monticello where thick, fine-textured soils store precipitation until evaporation and plant transpiration seasonally return it to the atmosphere. The cover at Monticello uses local soils and a native plant community to mimic the natural soil water balance. The cover is fundamentally an evapotranspiration (ET) design with a capillary barrier. A 3-hectare drainage lysimeter was embedded in the cover during construction of the disposal cell in 2000. The lysimeter consists of a geo-membrane liner below the capillary barrier that directs percolation water to a monitoring system. Soil water storage is determined by integration of point water content measurements. Meteorological parameters are measured nearby. Plant cover, shrub density, and leaf area index (LAI) are monitored annually. The cover performed well over the 7-year monitoring period (2000-2007). The cumulative percolation was 4.2 mm (0.6 mm yr{sup -1}), satisfying an EPA goal of an average percolation of <3.0 mm yr{sup -1}. Almost all percolation can be attributed to the exceptionally wet winter and spring of 2004-2005 when soil water content slightly exceeded the water storage capacity of the cover. The diversity, percent cover, and LAI of vegetation increased over the monitoring period, although the density of native shrubs that extract water from deeper in the cover has remained less than revegetation targets. DOE and EPA are applying the monitoring results to plan for long-term surveillance and maintenance and to evaluate alternative cover designs for other waste disposal sites. (authors)

Waugh, W.J.; Kastens, M.K.; Sheader, L.R.L. [Environmental Sciences Laboratory, Grand Junction, CO (United States); Benson, C.H. [University of Wisconsin, Madison, WI (United States); Albright, W.H. [Desert Research Institute, Reno, NV (United States); Mushovic, P.S. [U.S. Environmental Protection Agency, Denver, CO (United States)

2008-07-01

245

Guidance on the application of quality assurance for characterizing a low-level radioactive waste disposal site  

SciTech Connect

This document provides the Nuclear Regulatory Commission's staff guidance to an applicant on meeting the quality control (QC) requirements of Title 10 of the Code of Federal Regulations, Part 61, Section 61.12 (10 CFR 61.12), for a low-level waste disposal facility. The QC requirements combined with the requirements for managerial controls and audits are the basis for developing a quality assurance (QA) program and for the guidance provided herein. QA guidance is specified for site characterization activities necessary to meet the performance objectives of 10 CFR Part 61 and to limit exposure to or the release of radioactivity. 1 tab.

Pittiglio, C.L. Jr.; Starmer, R.J.; Hedges, D.

1990-10-01

246

Chromium(VI)-reducing Chlorella spp. isolated from disposal sites of paper-pulp and electroplating industry  

Microsoft Academic Search

We isolated four cultures of chromate resistant, unicellular, non-motile green algae from disposal sites of the paper-pulp\\u000a and electroplating industries. These algae were maintained in Tris-acetate-glycerophosphate medium containing 30?M K2Cr2O7. The morphological features as well as analysis of the 500-bp fragment of 18S rDNA (NS 12 region) showed that these isolates\\u000a belong to Chlorella spp. These isolates showed EC50 values

Swati N. Yewalkar; Kondiram. N. Dhumal; Jayashree K. Sainis

2007-01-01

247

Technology assessment guide for application of engineered sorbent barriers to low-level radioactive waste disposal sites  

SciTech Connect

An engineered sorbent barrier (ESB) uses sorbent materials (such as activated carbon or natural zeolites) to restrict migration of radionuclides from low-level waste sites. The permeability of the ESB allows moisture to pass while the sorbent material traps or absorbs contaminants. In contrast, waste sites with impermeable barriers could fill with water, especially those waste sites in humid climates. A sorbent barrier can be a simple, effective, and inexpensive method for restricting radionuclide migration. This report provides information and references to be used in assessing the sorbent barrier technology for low-level waste disposal. The ESB assessment is based on sorbent material and soil properties, site conditions, and waste properties and inventories. These data are used to estimate the thickness of the barrier needed to meet all performance requirements for the waste site. This document addresses the following areas: (1) site information required to assess the need and overall performance of a sorbent barrier; (2) selection and testing of sorbent materials and underlying soils; (3) use of radionuclide transport models to estimate the required barrier thickness and long-term performance under a variety of site conditions; (4) general considerations for construction and quality assurance; and (5) cost estimates for applying the barrier. 37 refs., 6 figs., 2 tabs.

Freeman, H.D.; Jones, E.O.; Depner, J.P.

1989-06-01

248

Corrective Action Investigation Plan for Corrective Action Unit 542: Disposal Holes, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect

Corrective Action Unit (CAU) 542 is located in Areas 3, 8, 9, and 20 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 542 is comprised of eight corrective action sites (CASs): (1) 03-20-07, ''UD-3a Disposal Hole''; (2) 03-20-09, ''UD-3b Disposal Hole''; (3) 03-20-10, ''UD-3c Disposal Hole''; (4) 03-20-11, ''UD-3d Disposal Hole''; (5) 06-20-03, ''UD-6 and UD-6s Disposal Holes''; (6) 08-20-01, ''U-8d PS No.1A Injection Well Surface Release''; (7) 09-20-03, ''U-9itsy30 PS No.1A Injection Well Surface Release''; and (8) 20-20-02, ''U-20av PS No.1A Injection Well Surface Release''. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 30, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 542. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 542 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Conduct geophysical surveys to locate previously unidentified features at CASs 03-20-07, 03-20-09, 03-20-10, 03-20-11, and 06-20-03. (4) Perform field screening. (5) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present. (6) Collect quality control samples for laboratory analyses to evaluate the performance of measurement systems and controls based on the requirements of the data quality indicators. (7) If COCs are present at the surface/near surface (< 15 feet below ground surface), collect additional step-out samples to define the extent of the contamination. (8) If COCs are present in the subsurface (i.e., base of disposal hole), collect additional samples to define the vertical extent of contamination. A conservative use restriction will be used to encompass the lateral extent of subsurface contamination. (9) Stake or flag sample locations in the field, and record coordinates through global positioning systems surveying. (10) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes. This Corrective Action Investigation Plan has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan.

Laura Pastor

2006-05-01

249

Superfund Record of Decision (EPA Region 2): C and J disposal site, Town of Eaton, Madison County, NY. (First remedial action), March 1991. Final report  

SciTech Connect

The C and J Disposal site is a former industrial waste disposal area in the Town of Eaton, Madison County, New York. Located 3,000 feet to the south of the site, Woodman Pond serves as a backup drinking water source for the nearby Village of Hamilton. The primary contaminants of concern affecting the soil and debris are VOCs including benzene, toluene, TCE, and xylenes; other organics including PAHs and phenols; and metals including lead. The selected remedial action for the site includes dewatering the trench and treating the water before recharge, if necessary; excavating approximately 1,250 cubic yards of contaminated soil and debris from the disposal trench, followed by offsite treatment or disposal.

Not Available

1991-03-29

250

ALTERNATIVE ONSITE WASTEWATER TREATMENT AND DISPOSAL SYSTEMS ON SEVERELY LIMITED SITES  

EPA Science Inventory

Several research and evaluation studies were performed on alternative onsite systems on sites with severe limitations for conventional systems. The major limitations included slow permeability, a seasonally high water table, and limiting soil horizons. Several typical site evalua...

251

Assessment of Potential Flood Events and Impacts at INL's Proposed Remote-Handled Low-Level Waste Disposal Facility Sites  

SciTech Connect

Rates, depths, erosion potential, increased subsurface transport rates, and annual exceedance probability for potential flooding scenarios have been evaluated for the on-site alternatives of Idaho National Laboratorys proposed remote handled low-level waste disposal facility. The on-site disposal facility is being evaluated in anticipation of the closure of the Radioactive Waste Management Complex at the INL. An assessment of flood impacts are required to meet the Department of Energys Low-Level Waste requirements (DOE-O 435.1), its natural phenomena hazards assessment criteria (DOE-STD-1023-95), and the Radioactive Waste Management Manual (DOE M 435.1-1) guidance in addition to being required by the National Environmental Policy Act (NEPA) environmental assessment (EA). Potential sources of water evaluated include those arising from (1) local precipitation events, (2) precipitation events occurring off of the INL (off-site precipitation), and (3) increased flows in the Big Lost River in the event of a Mackay Dam failure. On-site precipitation events include potential snow-melt and rainfall. Extreme rainfall events were evaluated for the potential to create local erosion, particularly of the barrier placed over the disposal facility. Off-site precipitation carried onto the INL by the Big Lost River channel was evaluated for overland migration of water away from the river channel. Off-site precipitation sources evaluated were those occurring in the drainage basin above Mackay Reservoir. In the worst-case scenarios, precipitation occurring above Mackay Dam could exceed the dams capacity, leading to overtopping, and eventually complete dam failure. Mackay Dam could also fail during a seismic event or as a result of mechanical piping. Some of the water released during dam failure, and contributing precipitation, has the potential of being carried onto the INL in the Big Lost River channel. Resulting overland flows from these flood sources were evaluated for their erosion potential, ability to overflow the proposed disposal facility, and for their ability to increase migration of contaminants from the facility. The assessment of available literature suggests that the likelihood of detrimental flood water impacting the proposed RH-LLW facility is extremely low. The annual exceedance probability associated with uncontrolled flows in the Big Lost River impacting either of the proposed sites is 1x10-5, with return interval (RI) of 10,000yrs. The most probable dam failure scenario has an annual exceedance probability of 6.3x10-6 (1.6x105 yr RI). In any of the scenarios generating possible on-site water, the duration is expected to be quite short, water depths are not expected to exceed 0.5 m, and the erosion potential can easily be mitigated by emplacement of a berm (operational period), and an engineered cover (post closure period). Subsurface mobilization of radionuclides was evaluated for a very conservative flooding scenario resulting in 50 cm deep, 30.5 day on-site water. The annual exceedance probability for which is much smaller than 3.6x10-7 (2.8x106 yr RI). For the purposes of illustration, the facility was assumed to flood every 500 years. The periodically recurring flood waters were predicted to marginally increase peak radionuclide fluxes into the aquifer by at most by a factor of three for non-sorbing radionuclides, and to have limited impact on peak radionuclide fluxes into the aquifer for contaminants that do sorb.

A. Jeff Sondrup; Annette L. Schafter

2010-09-01

252

Assessment of Exergy for Renewable Energy Disposable in the Site of Building  

NASA Astrophysics Data System (ADS)

Future energy challenges to construct near zero energy buildings and to have a centralized network together with integrated distributed generation from local disposable renewable energy (LdRe) raises new goals of a complex approach to energy supply. In the context of the current scientific sector, a single comprehensive approach to the general LdRe is missing. Following the typical way, all buildings are planned or designed in light of the energy needs of the intended activities in the buildings and only after the determination of these activities are the points and forms of energy supply planned. This article presents another approach in the planning process - a building and its energy needs planning taking into account the LdRe. It also provides the universal system describing the quantity and quality of LdRe. This research includes LdRe flows' assessment, with the building, as LdRe energy user flows linking to the user only as a potential user of this energy. The exergy analysis method is used to determine the LdRe indicator. Actually determined main renewable energy (RE) flow' (solar, wind, soil and air) values are used for the calculations. Standard 1 ha land plot area and set volumes above the land surface and beneath it are analyzed. After determination of disposable RE flows exergy quantity of the exergy change in the period of half year, one typical month and day is depicted.

Zekas, Vygantas; Martinaitis, Vytautas

2011-01-01

253

COMPOSITE ANALYSIS OF LLW DISPOSAL FACILITIES AT THE U.S. DEPARTMENT OF ENERGY'S SAVANNAH RIVER SITE  

SciTech Connect

Composite Analyses (CA's) are required per DOE Order 435.1 [1], in order to provide a reasonable expectation that DOE low-level waste (LLW) disposal, high-level waste tank closure, and transuranic (TRU) waste disposal in combination with Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), Resource Conservation and Recovery Act (RCRA), and deactivation and decommissioning (D&D) actions, will not result in the need for future remedial actions in order to ensure radiological protection of the public and environment. This Order requires that an accounting of all sources of DOE man-made radionuclides and DOE enhanced natural radionuclides that are projected to remain on the site after all DOE site operations have ceased. This CA updates the previous CA that was developed in 1997. As part of this CA, an inventory of expected radionuclide residuals was conducted, exposure pathways were screened and a model was developed such that a dose to the MOP at the selected points of exposure might be evaluated.

Hiergesell, R; Mark Phifer, M; Frank02 Smith, F

2009-01-08

254

West Hackberry Strategic Petroleum Reserve site brine-disposal monitoring, year 1 report. Volume 1. Executive summary. Final report  

SciTech Connect

The physical, chemical and biological attributes are described for: (1) a coastal marine environment centered about a Department of Energy Strategic Petroleum Reserve (SPR) brine disposal site located 11.4 km off the southwest coast of Louisiana; and (2) the lower Calcasieu and Sabine estuarine systems that provide leach waters for the SPR project. During the study period, the daily discharge averaged 529,000 barrels of 216 0/00 brine, representing a loading of 18,000 metric tons of salt per day. The objective of this study are: (1) characterize the environment in terms of physical, chemical and biological attributes; (2) determine if significant adverse changes in ecosystem productivity and stability of the biological community are occurring as a result of brine discharge; and (3) determine the magnitude of any change observed. This report describes the methodology and significant results of the first year's monitoring effort of the West Hackberry brine disposal site. The investigative tasks, presented as separate sections, are: Physical Oceanography, Estuarine Hydrology and Hydrography, Analysis of Discharge Plume, Water and Sediment Quality, Special Pollutant Surveys, Benthos, Nekton, Phytoplankton, Zooplankton and Data Management.

DeRouen, L.R.; Hann, R.W.; Casserly, D.M.; Giammona, C.; Lascara, V.J. (eds.)

1983-02-01

255

Recommended Method To Account For Daughter Ingrowth For The Portsmouth On-Site Waste Disposal Facility Performance Assessment Modeling  

SciTech Connect

A 3-D STOMP model has been developed for the Portsmouth On-Site Waste Disposal Facility (OSWDF) at Site D as outlined in Appendix K of FBP 2013. This model projects the flow and transport of the following radionuclides to various points of assessments: Tc-99, U-234, U-235, U-236, U-238, Am-241, Np-237, Pu-238, Pu-239, Pu-240, Th-228, and Th-230. The model includes the radioactive decay of these parents, but does not include the associated daughter ingrowth because the STOMP model does not have the capability to model daughter ingrowth. The Savannah River National Laboratory (SRNL) provides herein a recommended method to account for daughter ingrowth in association with the Portsmouth OSWDF Performance Assessment (PA) modeling.

Phifer, Mark A.; Smith, Frank G. III

2013-06-21

256

Hydrogeology, ground-water flow, and tritium movement at low-level radioactive-waste disposal site near Sheffield, Illinois  

USGS Publications Warehouse

Groundwater flow and tritium movement are described at and near a low-level radioactive waste disposal site near Sheffield, Illinois. Flow in the shallow aquifer is confined to three basins that ultimately drain into a stripmine lake. Most of the flow from the site is through a buried, pebbly sandfilled channel. Remaining flow is toward alluvium of an existing stream. Conceptual flow models for the two largest basins are used to improve definition of flow velocity and direction. Flow velocities range from about 25 to 2,500 ft/yr. Tritium was found in all three basins. The most extensive migration of tritium is coincident with buried channel. Tritium concentrations ranged from detection level to more than 300 nanocuries/L. (USGS)

Garklavs, George; Healy, R. W.

1986-01-01

257

Field Verification Program (Upland Disposal): Prediction of Surface Runoff Water Quality from Black Rock Harbor Dredged Material Placed in an Upland Disposal Site.  

National Technical Information Service (NTIS)

Some of the sediment dredged from waterways is contaminated and must be tested to predict problems that might occur after disposal. Laboratory tests showed that as dredged material dried and oxidized, physicochemical changes occurred which changed the con...

J. G. Skogerboe C. R. Lee R. A. Price D. Brandon G. Hollins

1987-01-01

258

76 FR 19003 - Land Disposal Restrictions: Nevada and California; Site Specific Treatment Variances for...  

Federal Register 2010, 2011, 2012, 2013

...site-specific treatment variance to U.S. Ecology Nevada (USEN) located in Beatty, Nevada...site-specific treatment variance to U.S. Ecology Nevada (USEN) located in Beatty, Nevada...This proposal applies only to U. S. Ecology Nevada located in Beatty, Nevada...

2011-04-06

259

Gas production, composition and emission at a modern disposal site receiving waste with a low-organic content  

SciTech Connect

AV Miljo is a modern waste disposal site receiving non-combustible waste with a low-organic content. The objective of the current project was to determine the gas generation, composition, emission, and oxidation in top covers on selected waste cells as well as the total methane (CH{sub 4}) emission from the disposal site. The investigations focused particularly on three waste disposal cells containing shredder waste (cell 1.5.1), mixed industrial waste (cell 2.2.2), and mixed combustible waste (cell 1.3). Laboratory waste incubation experiments as well as gas modeling showed that significant gas generation was occurring in all three cells. Field analysis showed that the gas generated in the cell with mixed combustible waste consisted of mainly CH{sub 4} (70%) and carbon dioxide (CO{sub 2}) (29%) whereas the gas generated within the shredder waste, primarily consisted of CH{sub 4} (27%) and nitrogen (N{sub 2}) (71%), containing no CO{sub 2}. The results indicated that the gas composition in the shredder waste was governed by chemical reactions as well as microbial reactions. CH{sub 4} mass balances from three individual waste cells showed that a significant part (between 15% and 67%) of the CH{sub 4} generated in cell 1.3 and 2.2.2 was emitted through leachate collection wells, as a result of the relatively impermeable covers in place at these two cells preventing vertical migration of the gas. At cell 1.5.1, which is un-covered, the CH{sub 4} emission through the leachate system was low due to the high gas permeability of the shredder waste. Instead the gas was emitted through the waste resulting in some hotspot observations on the shredder surface with higher emission rates. The remaining gas that was not emitted through surfaces or the leachate collection system could potentially be oxidized as the measured oxidation capacity exceeded the potential emission rate. The whole CH{sub 4} emission from the disposal site was found to be 820 {+-} 202 kg CH{sub 4} d{sup -1}. The total emission rate through the leachate collection system at AV Miljo was found to be 211 kg CH{sub 4} d{sup -1}. This showed that approximately 1/4 of the emitted gas was emitted through the leachate collections system making the leachate collection system an important source controlling the overall gas migration from the site. The emission pathway for the remaining part of the gas was more uncertain, but emission from open cells where waste is being disposed of or being excavated for incineration, or from horizontal leachate drainage pipes placed in permeable gravel layers in the bottom of empty cells was likely.

Scheutz, Charlotte, E-mail: chs@env.dtu.dk [Department of Environmental Engineering, Technical University of Denmark, Miljovej - Building 113, 2800 Kongens Lyngby (Denmark); Fredenslund, Anders M., E-mail: amf@env.dtu.dk [Department of Environmental Engineering, Technical University of Denmark, Miljovej - Building 113, 2800 Kongens Lyngby (Denmark); Nedenskov, Jonas, E-mail: jne@amfor.dk [AV Miljo, DK-2650 Hvidovre (Denmark); Samuelsson, Jerker, E-mail: jerker.samuelsson@fluxsense.se [Chalmers University of Technology/FluxSense AB, SE-412 96 Goeteborg (Sweden); Kjeldsen, Peter, E-mail: pk@env.dtu.dk [Department of Environmental Engineering, Technical University of Denmark, Miljovej - Building 113, 2800 Kongens Lyngby (Denmark)

2011-05-15

260

Savannah River Site's macro encapsulation processing of Less Than 3700 BQ/GM1 tru isotopic mixed waste for disposal at the Nevada Test Site  

SciTech Connect

During the Fiscal Year of 2006 (FY2006) the Savannah River Site (SRS) made a commitment with the South Carolina Department of Health and Environmental Control (SC-DHEC) to remove 1000 cubic meters of Transuranic (TRU) waste from its TRU inventory. As SRS has been generating TRU waste for many years, there was a multi-thousand drum inventory of waste designated as TRU waste. After characterization, a large inventory of TRU designated waste was determined to have a TRU radiological content of less than 3700 Becquerels per gram. This created an inventory of containers that could not be shipped to the Waste Isolation Pilot Plant (WIPP) due to being below the TRU waste threshold. A substantial portion of this debris waste was also known to contain RCRA constituents, making the waste Mixed Low Level Waste (MLLW). In order to safely and economically dispose of this waste inventory the SRS developed a process to characterize, inspect, and repackage this MLLW for disposal at the Nevada Test Site (NTS). (authors)

Siry, G.W.; Reid, L.T. [Washington Savannah River Company (United States)

2007-07-01

261

Finding of no significant impact shipment of stabilized mixed waste from the K-25 Site to an off-site commercial disposal facility, Oak Ridge K-25 Site, Oak Ridge, Tennessee  

SciTech Connect

The Department of Energy (DOE) has prepared an Environmental Assessment (EA) for the shipment of stabilized mixed waste, removed from K-1407-B and -C ponds, to an off-site commercial disposal facility (Envirocare) for permanent land disposal. Based on the analysis in the EA, DOE has determined that the proposed action is not a major federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement (EIS) is not required, and DOE is issuing this Finding of No Significant Impact (FONSI).

NONE

1994-12-31

262

Alternative Evaluation Study: Methods to Mitigate/Accommodate Subsidence for the Radioactive Waste Management Sites at the Nevada Test Site, Nye County Nevada, with Special Focus on Disposal Cell U-3ax/bl  

SciTech Connect

An Alternative Evaluation Study is a type of systematic approach to problem identification and solution. An Alternative Evaluation Study was convened August 12-15, 1997, for the purpose of making recommendations concerning closure of Disposal Cell U-3ax/bl and other disposal cells and mitigation/accommodation of waste subsidence at the Radioactive Waste Management Sites at the Nevada Test Site. This report includes results of the Alternative Evaluation Study and specific recommendations.

Barker, L.

1997-09-01

263

Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units Nevada Test Site, Nevada, Rev. No.: 0 with ROTC 1 and 2  

Microsoft Academic Search

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the

David A. Strand

2004-01-01

264

ENVIRONMENTAL IMPACTS ASSOCIATED WITH STORAGE, TREATMENT, AND DISPOSAL OF SOLID RADIOACTIVE AND CHEMICALLY HAZARDOUS WASTE AT THE HANFORD SITE, RICHLAND, WASHINGTON  

Microsoft Academic Search

The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) provides environmental and technical information concerning U.S. Department of Energy (DOE) proposed waste management practices for certain solid radioactive wastes at the Hanford Site through the year 2046. The HSW EIS covers four primary aspects of waste management at Hanford storage, treatment, transportation, and disposal. It

Wayne L. Johnson; Iral C. Nelson; David R. Payson; Kathleen Rhoads

2004-01-01

265

Alternative Onsite Wastewater Treatment and Disposal Systems on Severely Limited Sites.  

National Technical Information Service (NTIS)

Several research and evaluation studies were performed on alternative onsite systems on sites with severe limitations for conventional systems. The major limitations included slow permeability, a seasonally high water table, and limiting soil horizons. Se...

D. D. Effert J. M. Morand M. M. Cashell

1986-01-01

266

Post-Closure Inspection Report for Corrective Action Unit 333: U-3auS Disposal Site Annual Report, Nevada Test Site, Nevada  

SciTech Connect

The U-3auS Disposal Site Corrective Action Unit (CAU) 333 is a closed construction landfill located in Area 3 of the Nevada Test Site. The closure of this site was approved by the Nevada Division of Environmental Protection (NDEP) in a letter to the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office (NNSA/NV) dated June 27, 2001. Post-closure monitoring requirements are described in a letter from NNSA/NV to NDEP dated October 9, 2001, and were approved by the NDEP in a letter from NDEP to NNSA/NV dated November 5, 2001. Post-closure care consists of the following: Semiannual inspections of the unit using an inspection checklist; Photographic documentation of site conditions; Field note documentation; Performing minor site maintenance as necessary; and Preparation and submittal of an annual report. The annual report consists of copies of the inspection checklist, repair records (if any), photographs, and recommendations and conclusions. The Post-Closure Inspection Checklists are provided in Attachment A, a copy of the field notes is found in Attachment B, and copies of the inspection photographs are provided in Attachment C. Field note documentation is not formally required for this CAU, however in order to be consistent with other reports, it has been added to this report.

K. K. Knapp

2003-09-01

267

The Site Investigation Of Low-Level Radioactive Waste For Sub-Surface Disposal Facility In Japan  

NASA Astrophysics Data System (ADS)

[1.Concept of the sub-surface disposal facility] In Japan, the facilities of Low-Level Radioactive West (LLW) for near-surface disposal have already been in operation. Japan Nuclear Fuel Limited (JNFL) has a plan of a new facility of LLW for sub-surface disposal with engineered barrier, for short "the sub-surface disposal facility".This facility can accept the relatively higher low-level waste from unclear power plant operation and in core materials from the decommissioning, estimated about 20 thousands cubic meter in total.In addition, this will accept transuranim (TRU) slightly contaminated waste from reprocessing plant operation and decommissioning. It shall be located at a sufficient depth enough to avoid normal human activities in future. [2.Site investigation] From 2001 to 2006,the site investigation on geology and hydrogeology has been performed in order to acquire the basic data for the design and the safety assessment for the sub-surface disposal facility.The candidate area is located at the site of JNFL, where Rokkasho-mura, Aomori Prefecture in the northern area of the Mainland of Japan.To confirm geology hydraulic conditions and geo-chemistry, 22 boring survey including 6 holes in swamp and marsh have been performed. The 1km long access tunnel (the entrance level EL 8.0m, incline of 1/10) to the altitude of EL -86m underground, around 100m depth from surface, has excavated. During excavating the tunnel, observation of geology, permeability tests, pore water pressure measurements and so on has been performed in situ.And the large size test cavern of 18m diameters was constructed at the end of the tunnel to demonstrate stability of the tunnel. Prior to the excavation, 3 measuring tunnels were excavated surrounding the test cavern to examine the excavation. [3.Geological features] The sedimentary rock called Takahoko formation at the Neogene period is distributed upper than EL-500m in the candidate area.The quaternary stratum about 10m in thickness is distributed on the plateau and covers Takahoko formation.The stratum which consists of sandstone and tuff can be roughly subdivided into two stratums above EL-100m of the candidate area.The upper stratum is a little sandy, and is called pumice mixed sandstone. The lower stratum is called pumice tuff.Several faults have been observed in it.It is inferred that these faults had moved under unconsolidation condition in the early phase of sedimentation.The faults are considered not to become 'water conducting feature' because the interface of fault adheres completely and there is no fracture according to the observation of the drilling core and tunnel through the fault plane. [4. Groundwater] According to the logarithmic mean of hydraulic conductivity estimated by the injection test method with interval of 5-10m, hydraulic conductivity of pumice mixed sandstone and pumice tuff are 9.9E-8m/s, 1.9E-8m/s respectively.The direction of groundwater flow is to the central swamp or to the marsh which connected to the ocean.It is found that the groundwater flow is enough slow and movement of the nuclides will be limited.Groundwater velocity is around 10cm/y.There is no harmful constituent in the groundwater that affect to engineered barrier significantly.Reduction environment observed around the test cavern. [5. Mechanical stability] Its uniaxial compressive strength is around 4MPa, which is sufficient to excavate tunnels.Displacement of the test cavern of 18m diameters is less than 1cm during tunnel excavation.It is strong enough to excavate large tunnels.

Hosoya, S.; Sasaki, T.

2006-12-01

268

Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada: Revision 0  

SciTech Connect

The general purpose of this Corrective Action Investigation Plan is to ensure that adequate data are collected to provide sufficient and reliable information to identify, evaluate, and select technically viable corrective action alternatives (CAAs) for Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. Located in Areas 6 and 15 on the NTS, CAU 543 is comprised of a total of seven corrective action sites (CASs), one in Area 6 and six in Area 15. The CAS in Area 6 consists of a Decontamination Facility and its components which are associated with decontamination of equipment, vehicles, and materials related to nuclear testing. The six CASs in Area 15 are located at the U.S. Environmental Protection Agency Farm and are related to waste disposal activities at the farm. Sources of possible contamination at Area 6 include potentially contaminated process waste effluent discharged through a process waste system, a sanitary waste stream generated within buildings of the Decon Facility, and radiologically contaminated materials stored within a portion of the facility yard. At Area 15, sources of potential contamination are associated with the dairy operations and the animal tests and experiments involving radionuclide uptake. Identified contaminants of potential concern include volatile organic compounds, semivolatile organic compounds, petroleum hydrocarbons, pesticides, herbicides, polychlorinated biphenyls, metals, and radionuclides. Three corrective action closure alternatives - No Further Action, Close in Place, or Clean Closure - will be recommended for CAU 543 based on an evaluation of all the data quality objective-related data. Field work will be conducted following approval of the plan. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2004-05-03

269

Mineral precipitation and dissolution at two slag-disposal sites in northwestern Indiana, USA  

USGS Publications Warehouse

Slag is a ubiquitous byproduct of the iron- and steel-refining industries. In northwestern Indiana and northeastern Illinois, slag has been deposited over more than 52 km2 of land surface. Despite the widespread use of slag for fill and construction purposes, little is known about its chemical effects on the environment. Two slagdisposal sites were examined in northwestern Indiana where slag was deposited over the native glacial deposits. At a third site, where slag was not present, background conditions were defined. Samples were collected from cores and drill cuttings and described with scanning electron microscopy and electron microprobe analysis. Ground-water samples were collected and used to assess thermodynamic equilibria between authigenic minerals and existing conditions. Differences in the mineralogy at background and slag-affected sites were apparent. Calcite, dolomite, gypsum, iron oxides, and clay minerals were abundant in native sediments immediately beneath the slag. Mineral features indicated that these minerals precipitated rapidly from slag drainage and co-precipitated minor amounts of non-calcium metals and trace elements. Quartz fragments immediately beneath the slag showed extensive pitting that was not apparent in sediments from the background site, indicating chemical weathering by the hyperalkaline slag drainage. The environmental impacts of slag-related mineral precipitation include disruption of natural ground-water flow patterns and bed-sediment armoring in adjacent surface-water systems. Dissolution of native quartz by the hyperalkaline drainage may cause instability in structures situated over slag fill or in roadways comprised of slag aggregates.

Bayless, E. R.; Schulz, M. S.

2003-01-01

270

Hydrologic factors and /sup 90/Sr transport at a low-level waste disposal site  

SciTech Connect

A case study of a solid waste storage area at Oak Ridge National Laboratory is presented. The purpose of the study is to devise effective remedial actions based upon understanding of the underlying processes governing radionuclide migration. Discussion is presented under the following headings: site history; radionuclide transport studies; analysis of field results; and recommended remedial action.

Huff, D.D.

1982-01-01

271

ASSESSMENT OF SYNTHETIC MEMBRANE SUCCESSES AND FAILURES AT WASTE STORAGE AND DISPOSAL SITES  

EPA Science Inventory

Data from 27 lined facilities provided by five vendors was analyzed to determine the factors which contributed to success or failure of the liner at those facilities. The sites studied included a wide variety of wastes handled, liner types, geographic locations, facility ages, fa...

272

Evaluation of Liners for a Uranium-Mill Tailings Disposal Site: A Status Report.  

National Technical Information Service (NTIS)

The United States Department of Energy is conducting a program designed to reclaim or stabilize inactive uranium-mill tailings sites. This report presents the status of the Liner Evaluation Program. The purpose of the study was to identify eight prospecti...

J. L. Buelt V. Q. Hale S. M. Barnes D. J. Silviera

1981-01-01

273

Siting a municipal solid waste disposal facility, part II: the effects of external criteria on the final decision.  

PubMed

The procedure of a multi-criteria decision analysis supported by the geographic information systems was applied to the site selection process of a planning municipal solid waste management practice based on twelve different scenarios. The scenarios included two different decision tree modes and two different weighting models for three different area requirements. The suitability rankings of the suitable sites obtained from the application of the decision procedure for the scenarios were assessed by a factorial experimental design concerning the effect of some external criteria on the final decision of the site selection process. The external criteria used in the factorial experimental design were defined as "Risk perception and approval of stakeholders" and "Visibility". The effects of the presence of these criteria in the decision trees were evaluated in detail. For a quantitative expression of the differentiations observed in the suitability rankings, the ranking data were subjected to ANOVA test after a normalization process. Then the results of these tests were evaluated by Tukey test to measure the effects of external criteria on the final decision. The results of Tukey tests indicated that the involvement of the external criteria into the decision trees produced statistically meaningful differentiations in the suitability rankings. Since the external criteria could cause considerable external costs during the operation of the disposal facilities, the presence of these criteria in the decision tree in addition to the other criteria related to environmental and legislative requisites could prevent subsequent external costs in the first place. PMID:24654382

Korucu, M Kemal; Karademir, Aykan

2014-02-01

274

Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) plans to close the waste and classified material storage cells in the southeast quadrant of the Area 5 Radioactive Waste Management Site (RWMS), informally known as the '92-Acre Area', by 2011. The 25 shallow trenches and pits and the 13 Greater Confinement Disposal (GCD) borings contain various waste streams including low-level waste (LLW), low level mixed waste (LLMW), transuranic (TRU), mixed transuranic (MTRU), and high specific activity LLW. The cells are managed under several regulatory and permit programs by the U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP). Although the specific closure requirements for each cell vary, 37 closely spaced cells will be closed under a single integrated monolayer evapotranspirative (ET) final cover. One cell will be closed under a separate cover concurrently. The site setting and climate constrain transport pathways and are factors in the technical approach to closure and performance assessment. Successful implementation of the integrated closure plan requires excellent communication and coordination between NNSA/NSO and the regulators. (authors)

Wrapp, J.; Yucel, V.; Desotell, L.; Shott, G. [National Security Technologies, LLC, Sponsored by: J. Carilli, U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office (United States)

2008-07-01

275

The Site Investigation Of Low-Level Radioactive Waste For SubSurface Disposal Facility In Japan  

Microsoft Academic Search

[1.Concept of the sub-surface disposal facility] In Japan, the facilities of Low-Level Radioactive West (LLW) for near-surface disposal have already been in operation. Japan Nuclear Fuel Limited (JNFL) has a plan of a new facility of LLW for sub-surface disposal with engineered barrier, for short \\

S. Hosoya; T. Sasaki

2006-01-01

276

Evaluation of geologic materials to limit biological intrusion into low-level radioactive waste disposal sites  

SciTech Connect

This report describes the results of a three-year research program to evaluate the performance of selected soil and rock trench cap designs in limiting biological intrusion into simulated waste. The report is divided into three sections including a discussion of background material on biological interactions with waste site trench caps, a presentation of experimental data from field studies conducted at several scales, and a final section on the interpretation and limitations of the data including implications for the user.

Hakonson, T.E.

1986-02-01

277

Screening Evaluation of the Ecological Risks to Terrestrial Wildlife Associated with a Coal Ash Disposal Site  

Microsoft Academic Search

Between 1955 and 1989, coal ash was deposited within an impounded watershed on the U.S. Department of Energy's Oak Ridge Reservation in Tennessee, creating the 3.6?ha Filled Coal Ash Pond (FCAP). The site has subsequently become vegetated wildlife habitat. To evaluate risks that metals in ash may pose to wildlife; ash, surface water, small mammal, and vegetation samples were collected

Bradley E. Sample; Glenn W. Suter II

2002-01-01

278

Rooting depths of plants on low-level waste disposal sites  

SciTech Connect

In 1981-1982 an extensive bibliographic study was done to reference rooting depths of native plants in the United States. The data base presently contains 1034 different rooting citations with approximately 12,000 data elements. For this report, data were analyzed for rooting depths related to species found on low-level waste (LLW) sites at Los Alamos National Laboratory. Average rooting depth and rooting frequencies were determined and related to present LLW maintenance. The data base was searched for information on rooting depths of 53 species found on LLW sites at Los Alamos National Laboratory. The study indicates 12 out of 13 grasses found on LLW sites root below 91 cm. June grass (Koeleria cristata (L.) Pers.) (76 cm) was the shallowest rooting grass and side-oats grama (Bouteloua curtipendula (Michx.) Torr.) was the deepest rooting grass (396 cm). Forbs were more variable in rooting depths. Indian paintbrush (Castelleja spp.) (30 cm) was the shallowest rooting forb and alfalfa (Medicago sativa L.) was the deepest (>3900 cm). Trees and shrubs commonly rooted below 457 cm. The shallowest rooting tree was elm (Ulmus pumila L.) (127 cm) and the deepest was one-seed juniper (Juniperus monosperma (Engelm) Sarg.) (>6000 cm). Apache plume (Fallugia paradoxa (D. Don) Endl.) rooted to 140 cm, whereas fourwing saltbush (Atriplex canecens (Pursh) Nutt.) rooted to 762 cm.

Foxx, T.S.; Tierney, G.D.; Williams, J.M.

1984-11-01

279

Geochemical survey of an illegal waste disposal site under a waste emergency scenario (Northwest Naples, Italy).  

PubMed

Since the mid 1980s, Naples and the Campania region have suffered from the dumping of wastes into overfilled landfills. The aim was to characterise a former cave located in Roccarainola (Naples, Italy) for its eventual destination to a controlled landfill site. A detailed hydro-geochemical survey of the area was carried out through drilling of 14 boreholes and four monitoring wells. Samples of water, sediment and soil were analysed for heavy metals and organic contaminants from a dew pond placed in the middle of the cave. The underneath aquifer was also surveyed. The nature of gases emitted from the site was investigated. Results of the geognostic survey revealed the presence of huge volumes of composite wastes, approximately half a million of cubic metre, which accumulated up to a thickness of 25.6m. In some points, wastes lie below the free surface level of the aquifer. The sampled material from the boreholes revealed levels of As, Cd, Cr, Cu, Hg, Pb, Sn, Tl and Zn exceeding the intervention legal limits. Outstanding loads of Cd, Pb and Zn were found, with levels exceeding of about 50, 100 and 1,870 times the limit. In several points, polycyclic aromatic hydrocarbon load was extremely high, 35 vs 1mgkg(-1) of the threshold. The aquifer was also very heavily polluted by Cd, Cr-tot, Cu, Fe, Mn, Ni, Pb and Zn, with impressive high load of Cr and Mn, up to 250-370 times the limits. Hot gases up to 62C with presence of xylene and ethylbenzene were found. Results indicated that the site needs an urgent intervention of recovery to avoid compromising the surrounding areas and aquifers of the Campania plain. PMID:22766923

Ferrara, L; Iannace, M; Patelli, A M; Arienzo, M

2013-03-01

280

Use of Transient Electromagnetic Soundings (tem) to Locate Urban Solid Wastes Disposal Sites, in Coatzacoalcos, Veracruz, Mexico.  

NASA Astrophysics Data System (ADS)

Anthropogenic activities and their impact cause complex alterations in the natural quality of superficial and groundwater. Urban solid waste disposal represented an important source of contamination of groundwater. One of the main problems of the Coatzacoalcos, Veracruz area is the urgent necessity to close some dumps, actually in operation. At present, the municipal government has the project of selecting an urban waste disposal site that fulfills the official ecological norms, with appropriate geologic conditions and a useful life of 15 years. Study area, El Rebozo 1, is covered for sandy - clays from Filisola Formation. Also has outcrops of shales belonging to the Nanchital Formation. This Formation presents low porosity and permeability. It could serve as container in the construction of the landfill. We carried out 6 transient electromagnetic soundings (TEM), to determine the thickness and distribution of this formation in depth and to establish the existence of aquifers. The geophysical studies were carried out along a line of 680 m, with variable separation among stations between 150 m to 250 m, crossing the study area in SW direction. Results of TEM survey, geological, hydrological information and drilling survey confirmed the wide distribution in the studied area of the shale layer from the Nanchital Formation. The average thickness of the shale layer is 70 m and it presents low possibilities of storing an important aquifer. It could be considered as an impermeable layer that can be used as base for the construction of the landfill. Underlying the shale layer there are sandy-clays that could reduce the possible lixiviation from the landfill. Use of TEM provides larger advantages than the conventional electric methods (SEV's) and also more detailed information on the geologic and hydro-geologic conditions from the underground. The integration of geophysical methods with other disciplines allows more integrated systematic research in hydrogeology and contamination processes.

Gonzalez-Moran, T.; Hurtado, M.

2003-12-01

281

Transport and fate of organic wastes in groundwater at the Stringfellow hazardous waste disposal site, southern California  

USGS Publications Warehouse

In January 1999, wastewater influent and effluent from the pretreatment plant at the Stringfellow hazardous waste disposal site were sampled along with groundwater at six locations along the groundwater contaminant plume. The objectives of this sampling and study were to identify at the compound class level the unidentified 40-60% of wastewater organic contaminants, and to determine what organic compound classes were being removed by the wastewater pretreatment plant, and what organic compound classes persisted during subsurface waste migration. The unidentified organic wastes are primarily chlorinated aromatic sulfonic acids derived from wastes from DDT manufacture. Trace amounts of EDTA and NTA organic complexing agents were discovered along with carboxylate metabolites of the common alkylphenolpolyethoxylate plasticizers and nonionic surfactants. The wastewater pretreatment plant removed most of the aromatic chlorinated sulfonic acids that have hydrophobic neutral properties, but the p-chlorobenzenesulfonic acid which is the primary waste constituent passed through the pretreatment plant and was discharged in the treated wastewaters transported to an industrial sewer. During migration in groundwater, p-chlorobenzenesulfonic acid is removed by natural remediation processes. Wastewater organic contaminants have decreased 3- to 45-fold in the groundwater from 1985 to 1999 as a result of site remediation and natural remediation processes. The chlorinated aromatic sulfonic acids with hydrophobic neutral properties persist and have migrated into groundwater that underlies the adjacent residential community. Copyright ?? 2001 .

Leenheer, J. A.; Hsu, J.; Barber, L. B.

2001-01-01

282

Transport of elemental mercury in the unsaturated zone from a waste disposal site in an arid region  

USGS Publications Warehouse

Mercury contained in buried landfill waste may be released via upward emission to the atmosphere or downward leaching to groundwater. Data from the US Geological Survey's Amargosa Desert Research Site (ADRS) in arid southwestern Nevada reveal another potential pathway of Hg release: long-distance (102 m) lateral migration of elemental Hg (Hg0) through the unsaturated zone. Gas collected from multiple depths from two instrumented boreholes that sample the entire 110-m unsaturated zone thickness and are located 100 and 160 m away from the closest waste burial trench exhibit gaseous Hg concentrations of up to 33 and 11 ng m-3, respectively. The vertical distribution of gaseous Hg in the borehole closest to the disposal site shows distinct subsurface peaks in concentration at depths of 1.5 and 24 m that cannot be explained by radial diffusive transport through a heterogeneous layered unsaturated zone. The inability of current models to explain gaseous Hg distribution at the ADRS highlights the need to advance the understanding of gas-phase contaminant transport in unsaturated zones to attain a comprehensive model of landfill Hg release.

Walvoord, M. A.; Andraski, B. J.; Krabbenhoft, D. P.; Striegl, R. G.

2008-01-01

283

Preliminary report on the hydrogeology of a low-level radioactive waste disposal site near Sheffield, Illinois  

USGS Publications Warehouse

The Sheffield low-level radioactive-waste disposal site is located on 20 acres of rolling terrain about 3 miles southwest of Sheffield, Illinois. Twenty-one trenches were constructed and filled with radioactive waste from August 1967 through April 1978. Forty-three test wells were installed by the U.S. Geological Survey on and adjacent to the site. Continuous cores were collected from 36 wells to help in defining the subsurface geology. The wells have been used for water sample collection and to monitor water-level changes. A tunnel, 6.5 feet in diameter by 290 feet in length, was constructed beneath four burial trenches to provide access for collection of hydrologic and geologic data. Pennsylvanian shale and mudstone deposits are overlain by Pleistocene glacial deposits consisting of the Teneriffe Silt, Glasford Formation, Roxana Silt, Peoria Loess, Parkland Sand, Cahokia Alluvium, and Henry Formation. Three till units of the Glasford Formation, the Hulick Till Member, the Radnor Till Member, and Till A have been identified on the site. Stratigraphic position indicates that the Hulick Till Member and Till A are probably variations of the same till. A continuous pebbly sand deposit, classified as part of the Toulon Member, extends across the middle of the site and continues off site on the northeast and southwest corners. Because of its relatively high hydraulic conductivity, this deposit will be a controlling factor in shallow groundwater movement and in any radionuclide migration. Ground water at the site is derived through infiltration of precipitation and as underflow from adjacent highlands. Precipitation averages 35 inches per year, 1 or 2 inches of which probably recharge the ground water. Runoff is estimated to be 12 to 15 inches per year and evapotranspiration about 20 inches. The fluctuation of water levels has been about 2.5 feet in hilltop wells, 3.6 feet in sidehill wells, and 5.9 feet in valley wells. Hydraulic conductivity of the materials comprising the hydrogeologic system vary widely from about 2.8 to 2.8 x 10^-6 feet/day. Tritium in ground water near the southeast corner of the site has moved about 25 feet per year since June 1975.

Foster, J. B.; Erickson, J. R.

1980-01-01

284

Water movement and water chemistry in the unsaturated zone at a low-level radioactive-waste disposal site near Sheffield, Illinois, 1986-87  

SciTech Connect

Hydrologic research was conducted at the low-level radioactive-waste disposal site near Sheffield, Ill., during 1986-87. The purpose of the research was to address questions generated by earlier studies at the disposal site from 1981 to 1985 (PB95-186631). The specific goals of the research were (1) to characterize temporal trends in water movement and water chemistry over several (5-11) years, (2) to evaluate preferential movement of water and leachate (soluble trend-waste constituents) in an unsaturated glacial sand deposit underlying several disposal trenches, and (3) to determine the extent to which a tunnel, used in the study to access geologic deposits below four trenches, affected the natural movement of water in the unsaturated deposits.

Mills, P.C.

1993-12-31

285

Evaluation of liners for a uranium-mill tailings disposal site: a status report  

SciTech Connect

The United States Department of Energy is conducting a program designed to reclaim or stabilize inactive uranium-mill tailings sites. This report presents the status of the Liner Evaluation Program. The purpose of the study was to identify eight prospective lining materials or composites for laboratory testing. The evaluation was performed by 1) reviewing proposed regulatory requirements to define the material performance criteria; 2) reviewing published literature and communicating with industrial and government experts experienced with lining materials and techniques; and 3) characterizing the tailings at three of the sites for calcium concentration, a selection of anions, radionuclides, organic solvents, and acidity levels. The eight materials selected for laboratory testing are: natural soil amended with sodium-saturated montmorillonite (Volclay); locally available clay in conjunction with an asphalt emulsion radon suppression cover; locally available clay in conjunction with a multibarrier radon suppression cover; rubberized asphalt membrane; hydraulic asphalt concrete; chlorosulfonated polyethylene (hypalon) or high-density polyethylene; bentonite, sand and gravel mixture; and catalytic airblown asphalt membrane. The materials will be exposed in test units now being constructed to conditions such as wet/dry cycles, temperature cycles, oxidative environments, ion-exchange elements, etc. The results of the tests will identify the best material for field study. The status report also presents the information gathered during the field studies at Grand Junction, Colorado. Two liners, a bentonite, sand and gravel mixture, and a catalytic airblown asphalt membrane, were installed in a prepared trench and covered with tailings. The liners were instrumented and are being monitored for migration of moisture, radionuclides, and hazardous chemicals. The two liner materials will also be subjected to accelerated laboratory tests for a comparative assessment.

Buelt, J.L.; Hale, V.Q.; Barnes, S.M.; Silviera, D.J.

1981-05-01

286

Addendum to the Closure Report for Corrective Action Unit 356: Mud Pits and Disposal Sites Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This document constitutes an addendum to the November 2002, Closure Report for Corrective Action Unit 356: Mud Pits and Disposal Sites as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: This cover page that refers the reader to the UR Modification document for additional information The cover and signature pages of the UR Modification document The NDEP approval letter The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the URs for: CAS 03-04-01, Area 3 Change House Septic System CAS 03-09-04, Mud Pit These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004f). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

Lynn Kidman

2008-10-01

287

Mobilization of colloids in groundwater due to infiltration of water at a coal ash disposal site  

NASA Astrophysics Data System (ADS)

We investigated groundwaters in the vicinity of a coal ash site near an electric generating station in the western U.S.A. The purpose of the study was to ascertain why fine particles or colloids appear in some subsurface water samples there. If such fine particles are merely introduced during bailing or pumping operations which suspend otherwise immobile soil colloids, we should exclude these particulate materials from the water samples before analysis intended to quantify what is moving through the aquifer. However, if the colloids were truly suspended and moving with the groundwater flow in situ, then we should includes their contribution to our assessment of the mobile loads. Application of very careful sampling techniques (slow pumping rates, no atmospheric exposure) did not cause the large quantities of colloids observed previously to disappear from well water in which they occured. Additionally, the same sampling procedures did not cause similar abundances of colloids to appear in waters collected from neighboring wells installed and developed in the same manner and in the same geologic strata. Thus we believe sampling artifacts do not explain the colloids' presence in the groundwater samples. On the other hand, the groundwater chemistry and the nature of the suspended colloids (size, composition) strongly suggest these fine particles were suspended and therefore moving with the groundwater flow. At wells exhibiting large amounts of suspended colloids (?10-100 mg L -1), the water was enriched in CO 2 and depleted in O 2 relative to nearby locations. The colloids were typically between 0.1 and 2 ?m in size and were primarily silicates. These results suggest to us that, where infiltrating water is percolating through a site that has been mixed with coal ash, the secondary carbonate mineral in the soils are being dissolved; removal of this cementing carbonate phase may consequently release soil silicate colloids to be carried in the flowing water. Such processes may enhance contaminant transport in groundwater by augmenting the pollutant load moving in the groundwater, and increasing the permeability of the porous medium to pollutant infiltration with water water and/or rainwater.

Gschwend, Philip M.; Backhus, Debera A.; MacFarlane, John K.; Page, A. L.

1990-12-01

288

A method for the processing and analysis of digital terrain elevation data. [Shiprock and Gallup Quadrangles, Arizona and New Mexico  

NASA Technical Reports Server (NTRS)

A method is presented for the processing and analysis of digital topography data that can subsequently be entered in an interactive data base in the form of slope, slope length, elevation, and aspect angle. A discussion of the data source and specific descriptions of the data processing software programs are included. In addition, the mathematical considerations involved in the registration of raw digitized coordinate points to the UTM coordinate system are presented. Scale factor considerations are also included. Results of the processing and analysis are illustrated using the Shiprock and Gallup Quadrangle test data.

Junkin, B. G. (principal investigator)

1979-01-01

289

Enhanced detection of groundwater contamination from a leaking waste disposal site by microbial community profiles  

NASA Astrophysics Data System (ADS)

Groundwater biogeochemistry is adversely impacted when municipal solid waste leachate, rich in nutrients and anthropogenic compounds, percolates into the subsurface from leaking landfills. Detecting leachate contamination using statistical techniques is challenging because well strategies or analytical techniques may be insufficient for detecting low levels of groundwater contamination. We sampled profiles of the microbial community from monitoring wells surrounding a leaking landfill using terminal restriction fragment length polymorphism (T-RFLP) targeting the 16S rRNA gene. Results show in situ monitoring of bacteria, archaea, and the family Geobacteraceae improves characterization of groundwater quality. Bacterial T-RFLP profiles showed shifts correlated to known gradients of leachate and effectively detected changes along plume fringes that were not detected using hydrochemical data. Experimental sediment microcosms exposed to leachate-contaminated groundwater revealed a shift from a ?-Proteobacteria and Actinobacteria dominated community to one dominated by Firmicutes and ?-Proteobacteria. This shift is consistent with the transition from oxic conditions to an anoxic, iron-reducing environment as a result of landfill leachate-derived contaminants and associated redox conditions. We suggest microbial communities are more sensitive than hydrochemistry data for characterizing low levels of groundwater contamination and thus provide a novel source of information for optimizing detection and long-term monitoring strategies at landfill sites.

Mouser, Paula J.; Rizzo, Donna M.; Druschel, Gregory K.; Morales, Sergio E.; Hayden, Nancy; O'Grady, Patrick; Stevens, Lori

2010-12-01

290

Probabilistic Assessment of Radon Transport at the Monticello, Utah Uranium Mill Tailings Disposal Site  

NASA Astrophysics Data System (ADS)

One objective of the cover design at the Monticello site is attenuation of the radon emanation from the mill tailings to the atmosphere. The landfill cover acts as a diffusion barrier, allowing time for the decay of the relatively short-lived Rn-222 gas during migration through the pore spaces of the cover soil. The conceptual model of radon migration through the landfill cover is one-dimensional upward transport driven by the difference in concentration in the tailings and the atmosphere. The processes affecting transport are molecular diffusion and radioactive decay. Uncertainty in the radon emanation rate from the tailings, as well as uncertainties in the effective diffusion coefficient and moisture content for individual layers in the landfill cover are assessed for both present and future conditions. Transport of radon gas by diffusion is enhanced at higher moisture content because of the reduced air phase volume in the soil under these conditions. In a competing manner, higher moisture content results in a lower effective diffusion coefficient for radon gas. Multiple realizations of the system and simulations of radon transport were performed using the RAECOM and FRAMES computer programs. Results indicate a very low probability of exceeding the regulatory limit of 20 pCi/m2/s under present conditions and a low probability of exceedence for future conditions. Sandia National Laboratories is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under Contract DE-AC04-94AL85000.

Arnold, B. W.; Ho, C. K.; Cochran, J. R.; Taira, R. Y.

2001-12-01

291

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 1: Executive summary.  

National Technical Information Service (NTIS)

A team of analysts designed and conducted a performance evaluation (PE) to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and ...

1996-01-01

292

Long-Term Site Management Plan for the LLRW (Low-Level Radioactive Waste) Disposal Area at West Valley, New York: Task 3: Final Report.  

National Technical Information Service (NTIS)

The New York State Energy Research and Development Authority has sponsored a project to develop an integrated set of site management plans for the West Valley low-level radioactive waste (LLRW) disposal area. The plans were directed to upgrade the disposa...

1987-01-01

293

Spherical Diffusion of Tritium from a Point of Release in a Uniform Unsaturated Soil: A Deterministic Model for Tritium Mibration in an Arid Disposal Site.  

National Technical Information Service (NTIS)

The report presents a three-dimensional model for tritium migration in an arid waste disposal site. When tritiated water is released at a point in a uniform and relatively dry soil it redistributes in both the liquid and vapor phases. The flux density of ...

D. E. Smiles W. R. Gardner R. K. Schulz

1993-01-01

294

Total gaseous mercury and volatile organic compounds measurements at five municipal solid waste disposal sites surrounding the Mexico City Metropolitan Area  

Microsoft Academic Search

The daily municipal solid waste (MSW) generation in the Mexico City Metropolitan Area (MCMA) is the highest nationwide (?26000tonday?1); this amount is discarded in sanitary landfills and controlled dumps. Information about the type and concentration of potential pollutants contained in landfill gas (LFG) from these MSW disposal sites is limited. This study intends to generate information about the composition of

D. A. de la Rosa; A. Velasco; A. Rosas; T. Volke-Seplveda

2006-01-01

295

Deployment of an Alternative Closure Cover and Monitoring System at the Mixed Waste Disposal Unit U-3ax\\/bl at the Nevada Test Site  

Microsoft Academic Search

In October 2000, final closure was initiated of U-3ax\\/bl, a mixed waste disposal unit at the Nevada Test Site (NTS). The application of approximately 30 cm of topsoil, composed of compacted native alluvium onto an operational cover, seeding of the topsoil, installation of soil water content sensors within the cover, and deployment of a drainage lysimeter facility immediately adjacent to

Daniel G. Levitt; Thomas M. Fitzmaurice

2001-01-01

296

Origin of increased sulfate in groundwater at the ETF disposal site  

SciTech Connect

Treated effluent being discharged to the vadose zone from the C-018H Effluent Treatment Facility (ETF) at the Hanford Site has infiltrated vertically to the unconfined aquifer, as indicated by increasing tritium activity levels in the groundwater. Well 699-48-77A, in particular, exhibits increased levels of tritium and also sulfate in the groundwater. The origin of increased sulfate levels in the groundwater is attributed to the dissolution of gypsum as the effluent flows through the vadose zone. This is supported by the observation that sulfate was found to be present in soils collected from the vadose zone at an average value of about 10.6 ppm. The maximum observed sulfate concentration of 190 mg/L from well 699-48-77A was observed on August 6, 1996, and is less than the maximum value of 879 mg/L that potentially could be achieved if water in the vadose zone was to attain saturation with respect to gypsum and calcite. It is suggested that infiltration rates were high enough that the effluent did not completely equilibrate with gypsum in the vadose zone, and thus, sulfate levels remained below gypsum saturation levels. Sulfate levels appear to be dropping, which may be attributed to the completion of the dissolution of the bulk of gypsum present along the vadose zone flow path traversed by the effluent. Geochemical modeling was undertaken to evaluate the influence of effluent chemistry on sulfate concentration levels in the presence of excess calcite and gypsum. In general, the effect is fairly minor for dilute solutions, but becomes more significant for concentrated solutions.

Thornton, E.C.

1997-09-01

297

A composite modeling approach for subsurface transport of degrading contaminants from land-disposal sites  

NASA Astrophysics Data System (ADS)

A composite modeling approach is presented for simulating the three-dimensional (3-D) subsurface transport of dissolved contaminants with transformation products. The approach is based on vertical infiltration and contaminant transport in the unsaturated zone and 3-D groundwater flow and contaminant migration in the saturated zone. Moisture movement and groundwater flow are considered to be steady, but contaminant transport is treated as transient. The model allows for advection, dispersion, linear or nonlinear equilibrium sorption, and first-order biochemical transformation of either a single contaminant species, or a multi-species, straight or branched, decay chain. The model is designed for regulatory decision making using Monte Carlo analysis. For such applications considerable emphasis is placed on computational efficiency and robustness of the model. An efficient and robust semi-analytical method is used to perform the steady-state solution for infiltration through the unsaturated zone. A variety of transport solutions, corresponding to transient or steady state, and linear or nonlinear sorption conditions, are incorporated in the model. For transient linear transport, the Laplace transform technique is used. The transformed unsaturated-zone transport equation is solved analytically; the transformed saturated-zone transport is solved numerically using the Laplace transform-Galerkin (LTG) technique which permits a nonuniform groundwater flow field, reflecting the influence of locally higher infiltration from the waste source. The model contains fully 3-D solutions for flow and transport in the saturated zone, as well as two-dimensional solutions for vertical cross-sectional and areal scenarios. Model formulations and solution schemes are verified by comparison against a fully 3-D, variably saturated flow and transport code for a hypothetical problem which represents a typical landfill. The model is applied also to simulate a controlled release field experiment and the model predictions compare well with groundwater monitoring data for the site.

Kool, J. B.; Huyakorn, P. S.; Sudicky, E. A.; Saleem, Z. A.

1994-11-01

298

Seismic Characterization of Basalt Topography at Two Candidate Sites for the INL Remote-Handled Low-Level Waste Disposal Project  

Microsoft Academic Search

This report presents the seismic refraction results from the depth to bed rock surveys for two areas being considered for the Remote-Handled Low-Level Waste (RH-LLW) disposal facility at the Idaho National Laboratory. The first area (Site 5) surveyed is located southwest of the Advanced Test Reactor Complex and the second (Site 34) is located west of Lincoln Boulevard near the

Jeff Sondrup; Gail Heath; Trent Armstrong; Annette Shafer; Jesse Bennett; Clark Scott

2011-01-01

299

Trench water chemistry at commercially operated low-level radioactive waste disposal sites. [Trench waters from Maxey Flats, Kentucky and West Valley, New York  

SciTech Connect

Water samples from the disposal trenches of two low-level radioactive-waste-disposal sites were analyzed for their inorganic, organic, and radionuclide contents. Since oxidation of the trench waters can occur during their movement along the groundwater flow path, experiments were performed to measure the chemical and physical changes that occur in these waters upon oxidation. Low concentrations of chelating agents, shown to exist in trench waters, may be responsible for keeping radionuclides, particularly /sup 60/Co, in solution. 4 figures, 5 tables.

Pietrzak, R.F.; Dayal, R.; Kinsley, M.T.; Clinton, J.; Czyscinski, K.S.; Weiss, A.J.

1982-01-01

300

PBC triggers in water reservoirs, coal mining areas and waste disposal sites: from Newcastle to New York.  

PubMed

Various environmental factors have been proposed as triggers of primary biliary cirrhosis (PBC), a progressive autoimmune cholestatic liver disease which is characterised by the destruction of the small intrahepatic bile ducts. Support for their pathogenic role in PBC is provided by epidemiological studies reporting familial clustering and clusters of the disease within a given geographical area. The seminal study by Triger reporting that the great majority of PBC cases in the English city of Sheffield drank water from a specific water reservoir, has been followed by studies reporting disease 'hot spots' within a restricted geographic region of the former coal mining area of Newcastle. The New York study reporting an increased risk and significant clustering of PBC cases near toxic federal waste disposal sites has added strength to the notion that environmental factors, possibly in the form of infectious agents or toxic/chemical environmental factors in areas of contaminated land, water or polluted air may play a key role in the development of the disease. This review discusses the findings of reports investigating environmental factors which may contribute to the cause of primary biliary cirrhosis. PMID:21297253

Smyk, Daniel; Mytilinaiou, Maria G; Rigopoulou, Eirini I; Bogdanos, Dimitrios P

2010-01-01

301

10 CFR 40.27 - General license for custody and long-term care of residual radioactive material disposal sites.  

...General license for custody and long-term care of residual radioactive material disposal...General license for custody and long-term care of residual radioactive material disposal...issued for the custody of and long-term care, including monitoring,...

2014-01-01

302

Selection of a site for the ground disposal of radioactive wastes. 4. Migration of multiple nuclides under the ground  

Microsoft Academic Search

The migration of single radionuclides disposed of underground has been ; studied extensively, and many results have been reported. The migration of ; multiple radionuclides under similar conditions, has, on the other hand, scarcely ; been studied, and yet it is very important for evaluating the safety of the ; ground disposal of radioactive wastes. A discussion is presented on

Morisawa

1973-01-01

303

Superfund Record of Decision (EPA Region 5): Hunts Disposal Landfill site, Town of Caledonia, WI. (First remedial action), September 1990. Final report  

SciTech Connect

The 84-acre Hunts Disposal site is an inactive landfill in Caledonia Township, Racine County, Wisconsin. Onsite features include a 35-acre landfill surrounded by woodlands, wetlands, agricultural areas, and a lake. Part of the site that includes the landfill is within the 100-year floodplain of the Root River. The site overlies a contaminated surficial sand and gravel aquifer. By 1961, municipal and industrial wastes were dumped and burned in an onsite open pit. Specific wastes disposed of onsite included waste newspaper ink, spent solvents, tannery wastes, chromic acids, arsenic acid, and beryllium. The Record of Decision (ROD) addresses both source control and management of contaminant migration. The primary contaminants of concern affecting the soil, sediment, debris, and ground water are VOCs including benzene, TCE, and xylenes; acids; and metals including arsenic and chromium.

Not Available

1990-09-29

304

Public health assessment for C and J Disposal Site, Hamilton, Madison County, New York, Region 2. Cerclis No. NYD981561954. Final report  

SciTech Connect

The C J Disposal National Priority List (NPL) site is in the Town of Eaton in Madison County, New York. The site consists of a trench that was dug and filled with paint sludges and solid and liquid industrial wastes, including 75-100 barrels, in the mid-1970s. The primary waste-related contaminants are phthalates, which were found in on-site soils and groundwater. A preliminary health assessment for the site was completed in February 1991 and concluded that the site posed a potential human health concern to users of private wells downgradient of the site. Additionally, contamination of Woodman Pond which is about 3,000 feet downgradient of the site, was also identified as a potential concern as it is a supplemental potable water supply source for the Village of Hamilton.

Not Available

1994-01-12

305

Performance Assessment of a Low-Level Radioactive Waste Disposal Site using GoldSim Integrated Systems Model  

NASA Astrophysics Data System (ADS)

Texas Commission on Environmental Quality has approved licenses for four landfills at the Waste Control Specialists (WCS) site located in Andrews County, West Texas. The site includes a hazardous waste landfill and three landfills for radioactive waste. An updated performance assessment is necessary prior to acceptance of waste at the landfills. The updated performance assessment a) provides for more realistic and flexible dose modeling capabilities, b) addresses all plausible release and accident scenarios as they relate to the performance objectives, c) includes impact of climate and hydrologic scenarios that may impact long-term performance of the landfill, d) addresses impact of cover naturalization and degradation on the landfill, and e) incorporates uncertainty and sensitivity analysis for critical parameters. For the updated performance assessment, WCS has developed an integrated systems level performance assessment model using the GoldSim platform. GoldSim serves as a model for integrating all of the major components of a performance assessment, which include the radionuclide source term, facility design, environmental transport pathways, exposure scenarios, and radiological doses. Unlike many computer models that are based on first principles, GoldSim is a systems level model that can be used to integrate and abstract more complex sub-models into one system. This can then be used to assess the results into a unified model of the disposal system and environment. In this particular application, the GoldSim model consists of a) hydrogeologic model that simulates flow and transport through the Dockum geologic unit that underlies all of the waste facilities, b) waste cells that represent the containment unit and simulate degradation of waste forms, radionuclide leaching, and partitioning into the liquid and vapor phase within the waste unit, c) a cover system model that simulates upward diffusive transport from the underground repository to the atmosphere. In addition modules are included for human intrusion scenarios. Inputs and parameters for the hydrogeologic model are developed from a more detailed, numerical, vadose zone model (implemented in HYDRUS 2D). The Vadose zone model calculates fluxes through the waste under various climatic and cover-degradation scenarios. Uncertainty related to model parameters and boundary/initial conditions is also incorporated in the flux distribution through sensitivity analyses in the vadose zone model. Doses are calculated for onsite and offsite receptors through ingestion, inhalation, and external exposure, for comparison with regulatory dose standards. This modeling is part of an ongoing licensing effort to demonstrate compliance with low-level waste site performance objectives.

Merrell, G.; Singh, A.; Tauxe, J.; Perona, R.; Dornsife, W.; grisak, G. E.; Holt, R. M.

2011-12-01

306

CHARACTERIZATION OF DEFENSE NUCLEAR WASTE USING HAZARDOUS WASTE GUIDANCE. APPLICATIONS TO HANFORD SITE ACCELERATED HIGH-LEVEL WASTE TREATMENT AND DISPOSAL MISSION0  

SciTech Connect

Federal hazardous waste regulations were developed for management of industrial waste. These same regulations are also applicable for much of the nation's defense nuclear wastes. At the U.S. Department of Energy's (DOE) Hanford Site in southeast Washington State, one of the nation's largest inventories of nuclear waste remains in storage in large underground tanks. The waste's regulatory designation and its composition and form constrain acceptable treatment and disposal options. Obtaining detailed knowledge of the tank waste composition presents a significant portion of the many challenges in meeting the regulatory-driven treatment and disposal requirements for this waste. Key in applying the hazardous waste regulations to defense nuclear wastes is defining the appropriate and achievable quality for waste feed characterization data and the supporting evidence demonstrating that applicable requirements have been met at the time of disposal. Application of a performance-based approach to demonstrating achievable quality standards will be discussed in the context of the accelerated high-level waste treatment and disposal mission at the Hanford Site.

Hamel, William; Huffman, Lori; Lerchen, Megan; Wiemers, Karyn

2003-02-27

307

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results  

SciTech Connect

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site.

Waters, R.D.; Gruebel, M.M.; Hospelhorn, M.B. [and others

1996-03-01

308

Savannah River Site Public and regulatory involvement in the transuranic (TRU) program and their effect on decisions to dispose of Pu-238 heat source tru waste onsite  

SciTech Connect

The key to successful public involvement at the Savannah River Site (SRS) has been and continues to be vigorous, up-front involvement of the public and state regulators with technical experts. The SRS Waste Management Program includes all forms of radioactive waste. All of the decisions associated with the management of these wastes are of interest to the public and successful program implementation would be impossible without including the public up-front in the program formulation. Serious problems can result if program decisions are made without public involvement, and if the public is informed after key decisions are made. This paper will describe the regulatory and public involvement program and their effects on the decisions concerning the disposal at the Savannah River Site (SRS) of heat source Pu-238 TRU waste. As can be imagined, a decision to dispose of TRU waste onsite versus shipment to the Waste Isolation Pilot Plan (WIPP) in New Mexico for disposal is of considerable interest to the stakeholders in South Carolina. The interaction between the stakeholders not only include the general public, but also the South Carolina Department of Health and Environmental Control (SCDHEC) and Region IV of the Environmental Protection Agency (EPA). The discussions, educational sessions, and negotiations include resolution of equity issues as well and moved forward to an understanding of the difficulties including risk management faced by the Ship-to- WIPP program. Once the program was better understood, the real negotiations concerning equity, safety, and risk to workers from handling Pu-238 waste could begin. This paper will also discuss the technical, regulatory, and public involvement aspects of disposal onsite that must be properly communicated if the program is to be successful. The Risk Based End State Vision Report for the Savannah River Site includes a variance that proposes on-site near surface disposal of waste from the program to produce Pu-238 heat sources for deep space probes. On-site disposal would greatly reduce the risk to workers by eliminating the need to repackage the waste in order to characterize it and ship it to the Waste Isolation Pilot Plant. Significant cost savings can also be realized. A performance assessment was completed to demonstrate that on-site disposal of this waste can be done while meeting the Department of Energy and EPA performance objectives for disposal of TRU waste in a non-WIPP location such as the SRS. This analysis provides a means of demonstrating the technical basis for this alternative to management, stakeholders and regulators. The technical analysis is required to demonstrate that the performance objectives contained in 40 CFR 191, Environmental Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes will be met over a 10,000 year period. This paper will describe the successful results of this technical, regulatory, and public involvement program, explore why and how the accomplishments occurred, and describe the future challenges along with the road map for the future. In doing this, the TRU Ship-to-WIPP program must be described to give the readers an understanding of the technical complexities that must be communicated successfully to achieve constructive stakeholder participation and regulatory approval. (authors)

Bert Crapse, H.M. [U. S. Department of Energy, Washington (United States); Sonny, W.T. [Goldston Washington Savannah River Company (United States)

2007-07-01

309

Estimation of ground-water recharge from precipitation, runoff into drywells, and on-site waste-disposal systems in the Portland Basin, Oregon and Washington  

USGS Publications Warehouse

The average recharge rate in the Portland Basin, in northwestern Oregon and southwestern Washington, is estimated to be about 22.0 inches per year. Of that amount, precipitation accounts for about 20.8 inches per year, runoff into drywells 0.9 inches per year, and on-site waste disposal about 0.4 inches per year. Recharge is highest, about 49 inches per year, in the Cascade Range. Recharge is lowest, near zero, along and between the Columbia and Willamette Rivers. Recharge is higher locally in discrete areas owing to recharge from runoff into drywells and on-site, waste-disposal systems in urbanized parts of the study area. In these urbanized areas, recharge ranges from 0 to 49 inches per year.

Snyder, D. T.; Morgan, D. S.; McGrath, T. S.

1994-01-01

310

MODELING OF THE SUB-SUFACE REDUCING ENVIRONMENT OF THE Z-AREA SALTSTONE DISPOSAL FACILITY AT THE SAVANNAH RIVER SITE  

Microsoft Academic Search

Low-level radioactive liquid wastes at the U.S. Department of Energy Savannah River Site are treated by mixing the wastes with Saltstone grout to generate the Saltstone waste form that is poured into the concrete vaults for long-term disposal. The formula for Saltstone includes 25 wt% slag to create a reducing environment for mitigating the sub-surface transport of several radionuclides, including

T Hang; D Daniel Kaplan

2006-01-01

311

Modeling of the sub-surface reducing environment of the Z-Area Saltstone disposal facility at the Savannah River Site  

Microsoft Academic Search

Low-level radioactive liquid wastes at the U.S. Department of Energy Savannah River Site are treated by mixing the wastes with Saltstone grout to generate the Saltstone waste form that is poured into the concrete vaults for long-term disposal. The formula for Saltstone includes ~25 wt% slag to create a reducing environment for mitigating the sub-surface transport of several radionuclides, including

Thong Hang; Daniel I. Kaplan

2007-01-01

312

Remedial Action Plan and site conceptual design for stabilization of the inactive uranium mill tailings site at Shiprock, New Mexico.  

National Technical Information Service (NTIS)

This Remedial Action Plan (RAP) has been developed to serve a twofold purpose. It presents the series of activities which are proposed by the Department of Energy (DOE) to effect long-term control of radioactive materials at the inactive uranium processin...

T. V. Hill J. A. Morley E. T. Began

1985-01-01

313

Water and tritium movement through the unsaturated zone at a low-level radioactive-waste disposal site near Sheffield, Illinois, 1981-85  

SciTech Connect

The report characterizes water and tritium movement through the unsaturated zone in an area within the Sheffield disposal site. The report describes (1) the physical setting of the study area; (2) the physical and hydraulic properties of unconsolidated geologic materials; (3) the timing, paths, quantity, and rate of water movement through the unsaturated zone; (4) the factors that influence unsaturated-zone water movement; (5) the spatial and temporal patterns of tritium concentrations within the unsaturated zone; and (6) the application of study-area results to the site as a whole.

Mills, P.C.; Healy, R.W.

1993-12-31

314

Closure Report for Corrective Action Unit 110: Areas 3 RWMS U-3ax/bl Disposal Unit, Nevada Test Site, Nevada  

SciTech Connect

This Closure Report (CR) has been prepared for the Area 3 Radioactive Waste Management Site (RWMS) U-3ax/bl Disposal Unit Corrective Action Unit (CAU) 110 in accordance with the reissued (November 2000) Resource Conservation and Recovery Act (RCRA) Part B operational permit NEV HW009 (Nevada Division of Environmental Protection [NDEP], 2000) and the Federal Facility and Consent Order (FFACO) (NDEP et al., 1996). CAU 110 consists of one Corrective Action Site 03-23-04, described as the U-3ax/bl Subsidence Crater. Certifications of closure are located in Appendix A. The U-3ax/bl is a historic disposal unit within the Area 3 RWMS located on the Nevada Test Site (NTS). The unit, which was formed by excavating the area between two subsidence craters (U-3ax and U-3bl), was operationally closed in 1987. The U-3ax/bl disposal unit was closed under the RCRA, as a hazardous waste landfill. Existing records indicate that, from July 1968 to December 1987, U-3ax/bl received 2.3 x 10{sup 5} cubic meters (m{sup 3}) (8.12 x 10{sup 6} cubic feet [ft{sup 3}]) of waste. NTS atmospheric nuclear device testing generated approximately 95% of the total waste volume disposed of in U-3ax/bl; 80% of the total volume was generated from the Waste Consolidation Project. Area 3 is located in Yucca Flat, within the northeast quadrant of the NTS. The Yucca Flat watershed is a structurally closed basin encompassing an area of approximately 780 square kilometers (300 square miles). The structural geomorphology of Yucca Flat is typical of the Basin and Range Physiographic Province. Yucca Flat lies in one of the most arid regions of the country. Water balance calculations for Area 3 indicate that it is normally in a state of moisture deficit.

J. L. Smith

2001-08-01

315

Proposed Department of Energy design and operations criteria for low-level radioactive-waste-disposal sites  

Microsoft Academic Search

Shallow land burial activities were divided into site selection, site design, site operation, waste acceptance, site closure\\/postclosure and corrective actions. Criteria for each of the six areas were developed by a committee process, in order to meet site performance objectives (10 CFR 61). This document discusses the site design and operating criteria. (DLC)

H. D. Williams; K. L. Falconer; A. E. Grey

1982-01-01

316

Total gaseous mercury and volatile organic compounds measurements at five municipal solid waste disposal sites surrounding the Mexico City Metropolitan Area  

NASA Astrophysics Data System (ADS)

The daily municipal solid waste (MSW) generation in the Mexico City Metropolitan Area (MCMA) is the highest nationwide (26000 ton day -1); this amount is discarded in sanitary landfills and controlled dumps. Information about the type and concentration of potential pollutants contained in landfill gas (LFG) from these MSW disposal sites is limited. This study intends to generate information about the composition of LFG from five MSW disposal sites with different operational characteristics and stages, in order to identify their contribution as potential pollutant sources of total gaseous mercury (TGM) and volatile organic compounds (VOCs). Important methane (CH 4) contents (>55%) in LFG were registered at three of the five sites, while two sites were found in semi-aerobic conditions (CH 4<32%). Only at one site (a closed site), potentially polluting emissions from the LFG were detected, including toluene (90 ppm) and other VOCs, and especially high TGM concentrations (1100-1500 ng m -3). At the remaining sites, TGM levels in LFG were between 12.5 and 52.4 ng m -3. The impact of TGM contained in LFG emissions in ambient air was assessed by means of the TGM air/LFG ratio. This quotient indicated that values below 0.2, such as those found at two closed sites with final synthetic covers, could imply better closure practices than places with higher ratios, such as sites with only periodical clay cover. High values of the TGM air/LFG ratio were also related to external TGM sources of influence, as a landfill in operation stage located at a highly industrialized area.

de la Rosa, D. A.; Velasco, A.; Rosas, A.; Volke-Seplveda, T.

317

Demonstration of In-Situ Stabilization of Buried Waste at Pit G-11 at the Brookhaven National laboratory Glass Pits Disposal Site  

SciTech Connect

In 1989 BNL was added to the EPAs National Priorities List. The site is divided into seven operable units (OU). OU-I includes the former landfill area. The field task site is noted as the AOC 2C Glass Holes location. Beginning in the 1960s and continuing into the 1980s, BNL disposed of laboratory waste (glassware, chemicals and animal carcasses) in numerous shallow pits. The drivers for remediating the pits are; historical records that indicate hazardous materials may have been disposed of in the pits; ground water contamination down gradient of the pits; a test excavation of one of the glass holes that unearthed laboratory glass bottles with unidentified liquids still contained; and the fact that BNL rests atop an EPA designated sole-source aquifer. The specific site chosen for this demonstration was pit G-11. The requirements that lead to choosing this pit were; a well characterized pit and a relatively isolated pit where our construction operations would not impact on adjacent pits. The glass holes area, including pit G-11, was comprehensively surveyed using a suite of geophysical techniques (e.g., EM-31, EM-61, GPR). Prior to stabilizing the waste form a subsurface barrier was constructed to contain the entire waste pit. The pit contents were then stabilized using a cement grout applied via jet grouting. The stabilization was performed to make removal of the waste from the pit easier and safer in terms of worker exposure. The grouting process would mix and masticate the waste and grout and form a single monolithic waste form. This large monolith would then be subdivided into smaller 4 foot by 4 foot by 10-12 foot block using a demolition grout. The smaller blocks would then be easily removed from the site and disposed of in a CERCLA waste site.

Dwyer, B.P.; Gilbert, J.; Heiser, J.

1999-01-01

318

Savannah River Site Public and Regulatory Involvement in the Inadvertent Disposal of TRU Waste in the E-Area Low-Level Waste (LLW) Trenches  

SciTech Connect

The key to successful public involvement at the Savannah River Site (SRS) has been and continues to be vigorous, up-front involvement of the public, federal and state regulators with technical experts. The SRS Waste Management Program includes all forms of radioactive waste. All of the decisions associated with the management of these wastes are of interest to the public and successful program implementation would be impossible without including the public up-front in the program formulation. Serious problems can result if program decisions are made without public involvement, and if the public is informed after key decisions are made. This paper will describe the regulatory and public involvement program and their effects on the decisions concerning the inadvertent disposal at the Savannah River Site (SRS) of TRU waste in the E-area LLW Facility Trenches. SRS engineers discovered that a small amount of TRU waste was disposed in the E-area LLW trenches in 2003. This discovery was obviously of considerable interest to the State and Federal Regulators, and to the public. In addition to notifications to all interested parties, the first order of business was to ensure that operations continued to be protective of the public and the environment. This paper will describe the interactions with the Department of Energy (DOE), the South Carolina Department of Health and Environmental Control (SCDHEC), the Environmental Protection Agency (EPA), and the public. In addition the technical details of the inadvertent disposal will be discussed along with the analysis of long term performance of the waste form in the E-Area LLW Trenches and how this information was communicated with all parties. As can be imagined, a decision to dispose of TRU waste onsite versus shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico for disposal is of considerable interest to the stakeholders in South Carolina. The events that lead to the inadvertent disposal will be reviewed as well as the new systems put into place to ensure that this event will not happen again in the future. In order to determine alternatives to properly deposition this TRU waste, an evaluation of retrieval of the waste from the trench disposal was performed as well as an options risk analysis to determine the regulatory path forward should the decision be made to dispose of the TRU waste in place. An evaluation of the risks to the workers associated with retrieval was then compared to the risks of continued disposal in the E-Area Trenches. Cost and schedule for each alternative was also compared. This paper will describe the successful results of this technical, regulatory, and public involvement program, explore the challenges, how the accomplishments occurred, and describe the future challenges along with the road map for the future. A comparison with other similar events at other DOE sites will be discussed as well. In doing this, the SRS TRU and LLW programs must be described to give the readers an understanding of the technical complexities that must be communicated successfully to achieve constructive stakeholder participation and regulatory approval. (authors)

Pope, H. [U. S. Department of Energy, W. T. (Sonny) Goldston, Washington Savannah River Company (United States)

2008-07-01

319

Proposed Plan for an amendment to the Environmental Restoration Disposal Facility Record of Decision, Hanford Site, Richland, Washington.  

National Technical Information Service (NTIS)

The U.S. Environmental Protection Agency, the Washington State Department of Ecology, and the U.S. Department of Energy (Tri- Parties) are proposing an amendment to the Environmental Restoration Disposal Facility Record of Decision (ERDF ROD). EPA is the ...

1997-01-01

320

77 FR 50622 - Land Disposal Restrictions: Site-Specific Treatment Variance for Hazardous Selenium-Bearing Waste...  

Federal Register 2010, 2011, 2012, 2013

...Selenium-Bearing Waste Treated by U.S. Ecology Nevada in Beatty, NV AGENCY: Environmental...Disposal Restrictions program, to U.S. Ecology Nevada in Beatty, Nevada for the treatment...This action applies only to U.S. Ecology Nevada located in Beatty, Nevada....

2012-08-22

321

Trees as indicators of subterranean migration of tritium at a commercial shallow land radioactive waste disposal site. [Maxey Flats, KY  

Microsoft Academic Search

Leaf water and tree sap collected from deciduous trees in a natural forest growing outside the fenced exclusion area of the Maxey Flats Waste Disposal Facility in eastern Kentucky, USA were radiochemically analyzed to detect movement of tritium via subterranean flows of water at depths of three meters. These data indicate that trees can be used to detect the subterranean

W. H. Rickard; L. J. Kirby

1984-01-01

322

Long-term site management plan for the LLRW (low-level radioactive waste) disposal area at West Valley, New York: Task 3: Final report  

SciTech Connect

The New York State Energy Research and Development Authority has sponsored a project to develop an integrated set of site management plans for the West Valley low-level radioactive waste (LLRW) disposal area. The plans were directed to upgrade the disposal area so that passive custodial care and monitoring activities would be sufficient to protect public health and safety and the environment. Task 3 Long-Term Site Management Plan, is the subject of this report. The goal of Task 3 was to select a long-term site management plan that would result in a stabilized site which would require only passive maintenance activities. The objectives of Task 3 were to formulate and evaluate alternative long-term strategies. The following seven system plans were conceptualized for a comparative assessment: Precast Concrete Vault, Structural Glacial Fill cover, Structural Clay Cover, Dynamic Compaction with a Semi-Structural Clay Cap, Displacement piles with a Semi-Structural Clay Cap, Grouting with a Semi-Structural Clay Cap, and Active Maintenance/Final Closure with a Semi-Structural Clay Cap. The Energy Authority's basis for selecting its preferred alternative is described. Based upon this chosen alternative, a scale model demonstration project is presented to test some of the engineered remediation techniques. 53 refs., 20 figs., 18 tabs.

Not Available

1987-02-01

323

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

SciTech Connect

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.

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

1995-03-01

324

Closure Plan for Corrective Action Unit 110: Area 3 RWMS U-3ax/bl Disposal Unit, Nevada Test Site, Nevada  

SciTech Connect

This Closure Plan has been prepared for the Area 3 RWMS U-3ax/bl Disposal Unit Corrective Action Unit 110 in accordance with the Federal Facility and Consent Order (Nevada Division of Environmental Protection [NDEP] et al., 1996). The U-3ax/bl is a historic disposal unit within the Area 3 Radioactive Waste Management Site located on the Nevada Test Site (NTS). The unit, which was formed by excavating the area between two subsidence craters (U-3ax and U-3bl), was operationally closed in 1987. The U-3ax/bl disposal unit is scheduled for permanent closure under the Resource Conservation and Recovery Act as a hazardous waste landfill. Existing records indicate that, from July 1968 to December 1987, U-3ax/bl received 2.3 x 10{sup 5} cubic meters (8.12 x 10{sup 6} cubic feet) of waste. NTS nuclear device testing generated approximately 95 percent of the total volume disposed of in U-3ax/bl, the majority of which came from the Waste Consolidation Project (80 percent of the total volume) (Elletson and Johnejack, 1995). Area 3 is located in Yucca Flat, within the northeast quadrant of the NTS. The Yucca Flat watershed is a structurally closed basin encompassing an area of approximately 780 square kilometers (300 square miles). The structural geomorphology of Yucca Flat is typical of the Basin and Range Physiographic Province. Yucca Flat lies in one of the most arid regions of the country. Water balance calculations for Area 3 indicate that it is continuously in a state of moisture deficit. The U-3ax/bl Disposal Unit will be closed in place by installing a Resource Conservation and Recovery Act equivalent cover. Following cover construction a fence will be installed around the cover to prevent accidental damage to the cover. Post-closure monitoring will consist of site inspections to determine the condition of the engineered cover and cover performance monitoring using Time-Domain Reflectometry arrays to monitor moisture migration in the cover. Any identified maintenance and repair requirements will be remedied within 60 working days of discovery and documented in writing at the time of repair. Results of all inspections/repairs for a given year will be addressed in a single report submitted annually to the NDEP. Soil moisture will be monitored within the cover for a period of at least two years prior to establishing performance criteria for NDEP regulatory purposes.

T. M. Fitzmaurice

2000-08-01

325

Effect of On-Site Wastewater Disposal on Quality of Ground Water and Base Flow - A Pilot Study in Chester County, Southeastern Pennsylvania, 2005  

USGS Publications Warehouse

On-site wastewater disposal has the potential to introduce contaminants into ground water and subsequently, by ground-water discharge, to streams. A pilot study was conducted during 2005 by the U.S. Geological Survey in cooperation with the Chester County Health Department and the Chester County Water Resources Authority to determine if wastewater components, including inorganic constituents and selected organic wastewater compounds, such as detergents, considered to be emerging contaminants, were present in ground water and stream base flow in areas with on-site wastewater disposal. The study area was a small watershed (about 7.1 square miles) of mixed land use drained by Broad Run in central Chester County, Pa. The area is underlain by fractured metamorphic rocks that form aquifers recharged by precipitation. Surface- and ground-water sampling was done in areas with and without on-site wastewater disposal for comparison, including a relatively densely populated village with cesspools and septic systems, a residential area with septic systems, a residential area served by sewers, and agricultural land. Samples were collected in May-June and September 2005 from eight headwater stream sites under base-flow conditions and in June 2005 from eight wells and two springs. Samples were analyzed for major ions, nutrients, boron, bacteria, and a suite of organic wastewater compounds. Several emerging contaminant wastewater compounds, including detergent components, insect repellents, and flame retardants, were detected in base-flow and ground-water samples. Stream base-flow samples generally contained more compounds and higher concentrations of those compounds than did ground-water samples, and of the ground-water samples, samples from springs contained more compounds and higher concentrations than samples from wells. Concentrations of nitrate, chloride, and boron (inorganic constituents associated with wastewater) generally were all elevated in base-flow and ground-water samples in areas with relatively high densities of on-site wastewater disposal (septic systems or cesspools) compared to other areas sampled. Results of this pilot study should be considered preliminary because of limited data.

Senior, Lisa A.; Cinotto, Peter J.

2007-01-01

326

Carbon Isotopes in Unsaturated-Zone Gases and Ground Water Near a Radioactive-Waste Disposal Area, Amargosa Desert Research Site, Nye County, Nevada  

NASA Astrophysics Data System (ADS)

To test hypotheses about radionuclide distribution and transport, vertical profiles of 14C in carbon dioxide were determined on gas samples from a 110-m deep unsaturated zone 32, 100, and 3,000 m from a low-level radioactive-waste disposal area. A direct-scintillation-counting method for radiocarbon was developed that minimized sample handling and compared favorably with the more labor-intensive benzene-synthesis method. Values of ? 13C in pore gas were determined by isotope ratio mass spectrometry. Gross gas compositions were determined by chromatography. Gross gas compositions 100 m from the disposal area were similar to those at the 3,000-m site, i.e., relatively unperturbed, except that O2 levels at the 100-m site were slightly depleted in the 34-48 m depth interval ( ~19.5% versus ~20.8% O2 by volume). Radiocarbon levels at the 100-m site peaked at ~2,000 percent modern carbon (PMC) near land surface and decreased monotonically to <100 PMC at depths below 58 m. Gross gas composition 32 m from the disposal area displayed a well-defined CO2 peak that reached 2.0-2.5% by volume at a depth of 24 m. 14C levels showed a roughly coincident peak that reached 6x105 PMC at the 24 m depth. Elevated levels of tritium and volatile organic-carbon compounds accompanied the CO2 and 14C peaks. Corresponding ? 13CO2 values were shifted -7 to -10 permil from unperturbed values. This shift to lighter values is suggestive of fractionation during microbial production of 14CO2 from disposed waste. Core samples from the affected depths were dry and virtually devoid of microbes, with <4x103 colony forming units per gram of sediment, suggesting that the hypothesized microbial activity occurs closer to the emplacement trenches. Ground water at the 32-m site had a 14C level in dissolved inorganic carbon of 845 PMC in March 2000. Ground water from an adjacent well had a 14C level of 26 PMC in 1989 and 323 PMC in 1999. The low levels of 14C in ground water relative to those in unsaturated-zone gases suggest that radiocarbon transport is primarily by lateral gas diffusion through the unsaturated zone at this site.

Stonestrom, D. A.; Michel, R. L.; Evans, W. C.; Smith, T. R.; Smith, T. R.; Prudic, D. E.; Striegl, R. G.; Haas, H.; Brockman, F. J.; Andraski, B. J.

2001-12-01

327

Geophysical and chemical investigations of ground water at five industrial or waste-disposal sites in Logan Township, Gloucester County, New Jersey, 1983-87. Water Resources Investigation  

SciTech Connect

The report describes the use of electromagnetic-conductivity (EM) and ground-water-quality data at available wells to determine the presence of contaminant plumes at the five industrial or waste-disposal sites, to delineate the lateral and vertical extent of any plumes in the aquifer system, and to document the inorganic and organic constituents present in the plumes. EM surveys were used to locate probable shallow ground-water-contamination plumes (less than 30 ft (feet) below land surface). Ground-water samples were collected to identify the inorganic and organic constituents present in plumes delineated by geophysical methods and in ground water elsewhere at each site, and to test the reliability of the geophysical methods in detecting plumes of contaminated ground water. EM data were collected at 850 stations from September 1983 through January 1984 at the Air Products and Chemicals, Inc., waste-disposal site; BROS; Chemical Leaman; Monsanto; and property north of Rollins. The Rollins property was not accessible for conducting EM surveys. Ambient ground-water quality was determined by analyzing samples from 20 wells in Logan Township that are not in areas of ground-water contamination; results of these analyses are summarized in the report.

Kozinski, J.; Lacombe, P.J.; Hochreiter, J.J.; Lewis, J.C.

1990-01-01

328

Study of deep ocean currents near the 3800-M low-level radioactive waste disposal site. May 1984-May 1986. Final report  

SciTech Connect

The report presents the results of a two-year study of a U.S. 3800-m low-level radioactive waste-disposal site near the mouth of the Hudson Canyon. The program objectives were to describe the currents, including their source and variability, and deduce from the data the potential for, and direction of, transport of contaminants from the disposal area. The results show that the currents in the disposal area range in strength from a few to 62 cm/sec and are principally due to the presence of low-frequency topographic Rossby waves having periods of approximately two to four weeks. The currents generally flow towards the southwest, in line with the general topography of the mid-Atlantic region. The canyon acts to distort the southwest flow, resulting in currents below the canyon rim which are aligned with the canyon onshore-offshore axis. The direction of currents along the canyon axis appears to be determined by the proximity of both the Gulf Stream and the Western Boundary Undercurrent.

Casagrande, C.; Hamilton, P.

1988-06-01

329

Regulatory Requirements and Technical Analysis for Department of Energy Regulated Performance Assessments of Shallow-Trench Disposal of Low-Level Radioactive Waste at the Nevada Test Site  

NASA Astrophysics Data System (ADS)

The National Nuclear Security Administration, Nevada Operations Office (NNSA/NV) operates and maintains two active facilities on the Nevada Test Site (NTS) that dispose Department of Energy (DOE) defense-generated low-level radioactive (LLW), mixed radioactive, and classified waste in shallow trenches, pits and large-diameter boreholes. The operation and maintenance of the LLW disposal sites are self-regulated under DOE Order 435.1, which requires review of a Performance Assessment for four performance objectives: 1) all pathways 25 mrem/yr limit; 2) atmospheric pathways 10 mrem/yr limit; 3) radon flux density of 20 pCi/m2/s; and 4) groundwater resource protection (Safe Drinking Water Act; 4 mrem/yr limit). The inadvertent human intruder is protected under a dual 500- and 100-mrem limit (acute and chronic exposure). In response to the Defense Nuclear Facilities Safety Board Recommendation 92 2, a composite analysis is required that must examine all interacting sources for compliance against both 30 and 100 mrem/yr limits. A small component of classified transuranic waste is buried at intermediate depths in 3-meter diameter boreholes at the Area 5 LLW disposal facility and is assessed through DOE-agreement against the requirements of the Environmental Protection Agency (EPA)'s 40 CFR 191. The hazardous components of mixed LLW are assessed against RCRA requirements. The NTS LLW sites fall directly under three sets of federal regulations and the regulatory differences result not only in organizational challenges, but also in different decision objectives and technical paths to completion. The DOE regulations require deterministic analysis for a 1,000-year compliance assessment supplemented by probabilistic analysis under a long-term maintenance program. The EPA regulations for TRU waste are probabilistically based for a compliance interval of 10,000 years. Multiple steps in the assessments are strongly dependent on assumptions for long-term land use policies. Integrating the different requirements into coherent and consistent sets of conceptual models of the disposal setting, alternative scenarios, and system models of fate, transport and dose-based assessments is technically challenging. Environmental assessments for these sites must be broad-based and flexible to accommodate the multiple objectives.

Crowe, B.; Black, P.; Tauxe, J.; Yucel, V.; Rawlinson, S.; Colarusso, A.; DiSanza, F.

2001-12-01

330

Seismic Characterization of Basalt Topography at Two Candidate Sites for the INL Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect

This report presents the seismic refraction results from the depth to bed rock surveys for two areas being considered for the Remote-Handled Low-Level Waste (RH-LLW) disposal facility at the Idaho National Laboratory. The first area (Site 5) surveyed is located southwest of the Advanced Test Reactor Complex and the second (Site 34) is located west of Lincoln Boulevard near the southwest corner of the Idaho Nuclear Technology and Engineering Center (INTEC). At Site 5, large area and smaller-scale detailed surveys were performed. At Site 34, a large area survey was performed. The purpose of the surveys was to define the topography of the interface between the surficial alluvium and underlying basalt. Seismic data were first collected and processed using seismic refraction tomographic inversion. Three-dimensional images for both sites were rendered from the data to image the depth and velocities of the subsurface layers. Based on the interpreted top of basalt data at Site 5, a more detailed survey was conducted to refine depth to basalt. This report briefly covers relevant issues in the collection, processing and inversion of the seismic refraction data and in the imaging process. Included are the parameters for inversion and result rendering and visualization such as the inclusion of physical features. Results from the processing effort presented in this report include fence diagrams of the earth model, for the large area surveys and iso-velocity surfaces and cross sections from the detailed survey.

Jeff Sondrup; Gail Heath; Trent Armstrong; Annette Shafer; Jesse Bennett; Clark Scott

2011-04-01

331

Climax Granite, Nevada Test Site, as a host for a rock mechanics test facility related to the geologic disposal of high level nuclear wastes  

SciTech Connect

This document discusses the potential of the Climax pluton, at the Nevada Test Site, as the host for a granite mechanics test facility related to the geologic disposal of high-level nuclear waste. The Climax granitic pluton has been the site of three nuclear weapons effects tests: Hard Hat, Tiny Tot, and Piledriver. Geologic exploration and mapping of the granite body were performed at the occasion of these tests. Currently, it is the site Spent Fuel Test (SFT-C) conducted in the vicinity of and at the same depth as that of the Piledriver drifts. Significant exploration, mapping, and rock mechanics work have been performed and continue at this Piledriver level - the 1400 (ft) level - in the context of SFT-C. Based on our technical discussions, and on the review of the significant geological and rock mechanics work already achieved in the Climax pluton, based also on the ongoing work and the existing access and support, it is concluded that the Climax site offers great opportunities for a rock mechanics test facility. It is not claimed, however, that Climax is the only possible site or the best possible site, since no case has been made for another granite test facility in the United States. 12 figures, 3 tables.

Heuze, F.E.

1981-02-01

332

Evaluation of Heavy Metals in Solid Waste Disposal Sites in Campinas City, Brazil Using Synchrotron Radiation Total Reflection X-Ray Fluorescence  

NASA Astrophysics Data System (ADS)

The problem of solid waste in most countries is on the rise as a result of rapid population growth, urbanization, industrial development and changes in consumption habits. Amongst the various forms of waste disposals, landfills are today the most viable for the Brazilian reality, both technically and economically. Proper landfill construction practices allow minimizing the effects of the two main sources of pollution from solid waste: landfill gas and slurry. However, minimizing is not synonymous with eliminating; consequently, the landfill alone cannot resolve all the problems with solid waste disposal. The main goal of this work is to evaluate the content of trace elements in samples of groundwater, surface water and slurry arising from local solid waste disposals in the city of Campinas, SP, Brazil. Samples were collected at the Delta, Santa Barbara and Pirelli landfills. At the Delta and Santa Barbara sites, values above the maximum permitted level established by CETESB for Cr, Mn, Fe, Ni and Pb were observed in samples of groundwater, while at the Pirelli site, elements with concentrations above the permitted levels were Mn, Fe, Ba and Pb. At Delta, values above levels permitted by the CONAMA 357 legislation were still observed in surface water samples for Cr, Mn, Fe and Cu, whereas in slurry samples, values above the permitted levels were observed for Cr, Mn, Fe, Ni, Cu, Zn and Pb. Slurry samples were prepared in accordance with two extraction methodologies, EPA 3050B and EPA 200.8. Concentrations of Cr, Ni, Cu and Pb were higher than the limit established by CONAMA 357 for most samples collected at different periods (dry and rainy) and also for the two extraction methodologies employed.

de Faria, Bruna Fernanda; Moreira, Silvana

2011-12-01

333

Chemical Stockpile Disposal Program  

SciTech Connect

As part of the Chemical Stockpile Disposal Program mandated by Public Law 99--145 (Department of Defense Authorization Act), an independent review is presented of the US Army Phase I environmental report for the disposal program at the Umatilla Depot Activity (UMDA) in Hermiston, Oregon. The Phase I report addressed new and additional concerns not incorporated in the final programmatic environmental impact statement (FPEIS). Those concerns were addressed by examining site-specific data for the Umatilla Depot Activity and by recommending the scope and content of a more detailed site-specific study. This independent review evaluates whether the new site-specific data presented in the Phase I report would alter the decision in favor of on-site disposal that was reached in the FPEIS, and whether the recommendations for the scope and content of the site-specific study are adequate. Based on the methods and assumptions presented in the FPEIS, the inclusion of more detailed site-specific data in the Phase I report does not change the decision reached in the FPEIS (which favored on-site disposal at UMDA). It is recommended that alternative assumptions about meteorological conditions be considered and that site-specific data on water, ecological, socioeconomic, and cultural resources; seismicity; and emergency planning and preparedness be considered explicitly in the site-specific EIS decision-making process. 7 refs., 1 fig.

Krummel, J.R.; Policastro, A.J.; Olshansky, S.J.; McGinnis, L.D.

1990-10-01

334

Chemical Stockpile Disposal Program  

SciTech Connect

As part of the Chemical Stockpile Disposal Program mandated by Public Law 99--145 (Department of Defense Authorization Act), an independent review is presented of the US Army Phase I environmental report for the disposal program at the Pine Bluff Arsenal (PBA) in Arkansas. The Phase I report addressed new and additional concerns not incorporated in the final programmatic environmental impact statement (FPEIS). Those concerns were addressed by examining site-specific data for the PBA and by recommending the scope and content of a more detailed site- specific study. This dependent review evaluates whether the new site-specific data presented in the Phase I report would alter the decision in favor of on-site disposal that was reached in the FPEIS, and whether the recommendations for the scope and content of the site-specific study are adequate. Based on the methods and assumptions presented in the FPEIS, the inclusion of more detailed site-specific data in the Phase I report does not change the decision reached in the FPEIS (which favored on-site disposal at PBA). It is recommended that alternative assumptions about meteorological conditions be considered and that site-specific data on water, ecological, socioeconomic, and cultural resources, and emergency planning and preparedness be considered explicitly in the site-specific EIS decision-making process. 13 refs., 1 fig.

Krummel, J.R.; Policastro, A.J.; Olshansky, S.J.; McGinnis, L.D.

1990-10-01

335

Use of strategic environmental assessment in the site selection process for a radioactive waste disposal facility in Slovenia.  

PubMed

The benefits of strategic environmental considerations in the process of siting a repository for low- and intermediate-level radioactive waste (LILW) are presented. The benefits have been explored by analyzing differences between the two site selection processes. One is a so-called official site selection process, which is implemented by the Agency for radwaste management (ARAO); the other is an optimization process suggested by experts working in the area of environmental impact assessment (EIA) and land-use (spatial) planning. The criteria on which the comparison of the results of the two site selection processes has been based are spatial organization, environmental impact, safety in terms of potential exposure of the population to radioactivity released from the repository, and feasibility of the repository from the technical, financial/economic and social point of view (the latter relates to consent by the local community for siting the repository). The site selection processes have been compared with the support of the decision expert system named DEX. The results of the comparison indicate that the sites selected by ARAO meet fewer suitability criteria than those identified by applying strategic environmental considerations in the framework of the optimization process. This result stands when taking into account spatial, environmental, safety and technical feasibility points of view. Acceptability of a site by a local community could not have been tested, since the formal site selection process has not yet been concluded; this remains as an uncertain and open point of the comparison. PMID:20846780

Dermol, Urka; Konti?, Branko

2011-01-01

336

The Evolution of Low-Level Radioactive Waste (LLW) Disposal Practices at the Savannah River Site Coupled with Vigorous Stakeholder Interaction  

SciTech Connect

Low-level radioactive waste (LLW) disposal practices at SRS evolved from trench disposal with little long-term performance basis to disposal in robust concrete vaults, again without modeling long-term performance. Now, based on an assessment of long-term performance of various waste forms and methods of disposal, the LLW disposal program allows for a ''smorgasbord'' of various disposal techniques and waste forms, all modeled to ensure long-term performance is understood. New disposal techniques include components-in-grout, compaction/volume reduction prior to disposal, and trench disposal of extremely low activity waste. Additionally, factoring partition coefficient (Kd) measurements based on waste forms has been factored into performance models. This paper will trace the development of the different disposal methods, and the extensive public communications effort that resulted in endorsement of the changes by the SRS Citizens Advisory Board.

Goldston, W. T.; Wilhite, E. L.; Cook, J. R.; Sauls, V. W.

2002-02-25

337

Bibliography of reports by US Geological Survey personnel pertaining to underground nuclear testing and radioactive waste disposal at the Nevada Test Site, and radioactive waste disposal at the WIPP Site, New Mexico, January 1, 1979-December 31, 1979  

SciTech Connect

This bibliography presents reports released to the public between January 1, 1979, and December 31, 1979, by personnel of the US Geological Survey. Reports include information on underground nuclear testing and waste management projects at the NTS (Nevada Test Site) and radioactive waste projects at the WIPP (Waste Isolation Pilot Plant) site, New Mexico. Reports on Project Dribble, Tatum Dome, Mississippi, previously prepared as administrative reports and released to the public as 474-series reports during 1979 are also included in this bibliography.

Glanzman, V.M.

1980-01-01

338

Health Assessment for Doepke Disposal Holliday Site, Holliday, Johnson County, Kansas, Region 7. CERCLIS No. KSD980632301.  

National Technical Information Service (NTIS)

The Doepke-Holliday site is an 80.3-acre inactive landfill area owned by Deffenbaugh Industries, Inc. The site, which was placed on the National Priorities List (NPL) in 1982, is located on the south bank of the Kansas River 0.75 miles east of Holliday, K...

1991-01-01

339

76 FR 30027 - Land Disposal Restrictions: Site-Specific Treatment Variance for Hazardous Selenium-Bearing Waste...  

Federal Register 2010, 2011, 2012, 2013

...Selenium-Bearing Waste Treated by U.S. Ecology Nevada in Beatty, NV and Withdrawal of...site-specific treatment variance to U.S. Ecology Nevada in Beatty, Nevada and withdrew...site-specific treatment variance to U.S. Ecology Nevada in Beatty, Nevada and...

2011-05-24

340

Special Analysis for the Disposal of the Consolidated Edison Uranium Solidification Project Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada  

SciTech Connect

The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLB disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, Radioactive Waste Management, for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of compliance with all performance objectives. Tier II results indicate that the long-term performance of the OR CEUSP 233U waste stream is protective of human health and the environment. The Area 5 RWMS is located in one of the least populated and most arid regions of the U.S. Site characterization data indicate that infiltration of precipitation below the plant root zone at 2.5 meters (8.2 feet) ceased 10,000 to 15,000 y ago. The site is not expected to have a groundwater pathway as long as the current arid climate persists. The national security mission of the NNSS and the location of the Area 5 RWMS within the Frenchman Flat Corrective Action Unit require that access controls and land use restrictions be maintained indefinitely. PA modeling results for 10,000 to 60,000 y also indicate that the OR CEUSP 233U waste stream is acceptable for near-surface disposal. The mean resident air pathway annual total effective dose (TED), the resident all-pathways annual TED, and the acute drilling TED are less than their performance objectives for 10,000 y after closure. The mean radon-222 (222Rn) flux density exceeds the performance objective at 4,200 y, but this is due to waste already disposed at the Area 5 RWMS and is only slightly affected by disposal of the CEUSP 233U. The peak resident all-pathways annual TED from CEUSP key radionuclides occurs at 48,000 y and is less than the 0.25 millisievert performance objective. Disposal of the OR CEUSP 233U waste stream in a typical SLB trench slightly increases PA results. Increasing the depth was found to eliminate any impacts of the OR CEUSP 233U waste stream. Containers could not be shown to have any significant impact on performance due to the long half-life of the waste stream and a lack of data for pitting corrosion rates of stainless steel in soil. The results of the SA indicate that all performance objectives can be met with disposal of the OR CEUSP 233U waste stream in the SLB units at the Area 5 RWMS. The long-term performance of the OR CEUSP 233U waste stream disposed in the near surface is protective of human health

NSTec Environmental Management

2013-01-31

341

Demonstration of performance modeling of a low-level waste shallow-land burial site: A comparison of predictive radionuclide transport modeling versus field observations at the ''A''disposal area, Chalk River Nuclear Laboratories  

Microsoft Academic Search

Before a license can be obtained to construct a facility for the shallow-land burial of low-level wastes, the US Nuclear Regulatory Commission must be assured that the facility will meet both performance objectives and prescriptive requirements set forth in 10CFR61, ''Licensing Requirements for Land Disposal of Radioactive Waste.'' Subpart D, Section 61.50(a) (2) of 10CRF61 states that a ''disposal site

D. E. Robertson; M. P. Bergeron; D. Holford; K. H. Abel; C. W. Thomas; D. A. Myers; D. R. Champ; R. W. D. Killey; G. L. Moltyaner; J. L. Young; T. Ohnuki

1989-01-01

342

Tritium waste disposal technology in the US  

Microsoft Academic Search

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

E. L. Albenesius; O. A. Towler

1983-01-01

343

Disposable polymer \\  

Microsoft Academic Search

The recent development of an innovative disposable polymer smart lab-on-a-chip, which includes smart passive microfluidics, embedded on-chip power sources, and integrated biosensor array, has opened a new era for the point-of-care testing in clinical diagnostics. Several challenging issues in the development of the disposable polymer smart lab-on-a-chip have been explored and addressed in this work. A new disposable polymer \\

Chong H. Ahn

2005-01-01

344

Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units Nevada Test Site, Nevada, Rev. No.: 0 with ROTC 1 and 2  

SciTech Connect

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S Department of Defense (DoD). Corrective Action Unit 543 is located in Area 6 and Area 15 of the NTS, which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Seven corrective action sites (CASs) comprise CAU 543 and are listed below: (1) 06-07-01, Decon Pad; (2) 15-01-03, Aboveground Storage Tank; (3) 15-04-01, Septic Tank; (4) 15-05-01, Leachfield; (5) 15-08-01, Liquid Manure Tank; (6) 15-23-01, Underground Radioactive Material Area; and (7) 15-23-03, Contaminated Sump, Piping. Corrective Action Site 06-07-01, Decon Pad, is located in Area 6 and consists of the Area 6 Decontamination Facility and its components that are associated with decontamination of equipment, vehicles, and materials related to nuclear testing. The six CASs in Area 15 are located at the U.S. Environmental Protection Agency (EPA) Farm and are related to waste disposal activities at the EPA Farm. The EPA Farm was a fully-functional dairy associated with animal experiments conducted at the on-site laboratory. The corrective action investigation (CAI) will include field inspections, video-mole surveys, and sampling of media, where appropriate. Data will also be obtained to support waste management decisions. The CASs within CAU 543 are being investigated because hazardous and/or radioactive constituents may be present at concentrations that could potentially pose a threat to human health and the environment. The seven CASs in CAU 543 primarily consist of sanitary and process waste collection, storage, and distribution systems (e.g., storage tanks, sumps, and piping). Existing information on the nature and extent of potential contamination at these sites is insufficient to evaluate and recommend corrective action alternatives for the CASs. Therefore, additional information will be obtained by conducting a CAI prior to evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS.

David A. Strand

2004-05-01

345

Corrective Action Investigation Plan for Corrective Action Unit 561: Waste Disposal Areas, Nevada Test Site, Nevada with ROTC 1, Revision 0  

SciTech Connect

Corrective Action Unit (CAU) 561 is located in Areas 1, 2, 3, 5, 12, 22, 23, and 25 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 561 is comprised of the 10 corrective action sites (CASs) listed below: 01-19-01, Waste Dump 02-08-02, Waste Dump and Burn Area 03-19-02, Debris Pile 05-62-01, Radioactive Gravel Pile 12-23-09, Radioactive Waste Dump 22-19-06, Buried Waste Disposal Site 23-21-04, Waste Disposal Trenches 25-08-02, Waste Dump 25-23-21, Radioactive Waste Dump 25-25-19, Hydrocarbon Stains and Trench These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2008, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 561. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the Corrective Action Investigation for CAU 561 includes the following activities: Move surface debris and/or materials, as needed, to facilitate sampling. Conduct radiological surveys. Perform exploratory excavations. Perform field screening. Collect and submit environmental samples for laboratory analysis to determine the nature and extent of any contamination released by each CAS. Collect samples of source material to determine the potential for a release. Collect samples of potential remediation wastes. Collect quality control samples.

Grant Evenson

2008-07-01

346

Decommissioning of a RCRA Treatment, Storage, and Disposal Facility: A case study of the 216-A-29 ditch at the Hanford Site  

SciTech Connect

The 216-A-29 ditch is located in the central portion of the Hanford Site with Operable Unit 200-PO-5. The ditch is classified under the Resource Conservation and Recovery Act of 1976 as a Treatment, Storage, and Disposal (TSD) Facility and as such, is to be removed from service in support of the Hanford Federal Facility Agreement and Consent Order Tri-Party Agreement (Ecology et al. 1989) Milestone M-17-10, which states cease all liquid discharges to hazardous land disposal units unless such units have been clean closed in accordance with the Resource Conservation and Recovery Act of 1976''. The 216-A-29 ditch is one stream feeding the 216-B-3 Pond system, and its removal from service was necessary to support the closure strategy for the 216-B-3 Pond system. Interim stabilization of the 216-A-29 ditch is the first step required to comply with the Tri-Party Agreement (Ecology et al. 1989) and the eventual decommissioning of the entire B Pond system. Interim stabilization was required to maintain the 216-A-29 ditch in a stable configuration until closure actions have been determined and initiated. 4 refs., 3 figs.

Smith, D.L.; Hayward, W.M.

1991-09-01

347

Evaluation of brine disposal from the Bryan Mound Site of the Strategic Petroleum Reserve Program. Final report of predisposal studies. Chapter 4. Appendix 7  

SciTech Connect

This report describes nekton communities off Freeport, Texas prior to brine disposal based on trawl studies in the period October 1977 to February 1980. Trawling was conducted aboard chartered commercial shrimp trawlers along a transect in depths of 3 to 25 fathoms to describe the general background of nekton communities off Freeport. An array of stations were occupied at the diffuser site in 12 fathoms of water to describe in detail nekton communities near the diffuser. Collections at each station, in general, were made once a month during the day and once a month at night, cruises being about two weeks apart in time. Projected diffuser locations, stations occupied, etc., changed during the course of the project, and the Materials and Methods (Section 4.2) should be consulted for details.

Hann, Jr, Roy W.; Randall, Robert E. [eds.] [eds.

1981-02-01

348

MODELING OF THE SUB-SUFACE REDUCING ENVIRONMENT OF THE Z-AREA SALTSTONE DISPOSAL FACILITY AT THE SAVANNAH RIVER SITE  

SciTech Connect

Low-level radioactive liquid wastes at the U.S. Department of Energy Savannah River Site are treated by mixing the wastes with Saltstone grout to generate the Saltstone waste form that is poured into the concrete vaults for long-term disposal. The formula for Saltstone includes {approx}25 wt% slag to create a reducing environment for mitigating the sub-surface transport of several radionuclides, including Tc-99. A two-dimensional reactive transport model was developed to estimate how long the Z-Area Saltstone will maintain a reducing environment, and therefore its ability to request Tc-99. The model predicted that {approx}16% of the Saltstone reduction capacity would be consumed after 213,000 years. Independent calculations published by other researchers yielded nearly identical results. The general modeling approach and the study results are presented in this paper.

Hang, T; Daniel Kaplan, D

2006-12-18

349

Biological intrusion barriers for large-volume waste-disposal sites. [Rocks and chemical barriers, trifluralin beads  

SciTech Connect

intrusion of plants and animals into shallow land burial sites with subsequent mobilization of toxic and radiotoxic materials has occured. Based on recent pathway modeling studies, such intrusions can contribute to the dose received by man. This paper describes past work on developing biological intrusion barrier systems for application to large volume waste site stabilization. State-of-the-art concepts employing rock and chemical barriers are discussed relative to long term serviceability and cost of application. The interaction of bio-intrusion barrier systems with other processes affecting trench cover stability are discussed to ensure that trench cover designs minimize the potential dose to man. 3 figures, 6 tables.

Hakonson, T.E.; Cline, J.F.; Rickard, W.H.

1982-01-01

350

Recent ORNL (Oak Ridge National Laboratory) Experience in Site Performance Prediction: The Gas Centrifuge Enrichment Plant and the Oak Ridge Central Waste Disposal Facility.  

National Technical Information Service (NTIS)

The suitability of the Portsmouth Gas Centrifuge Enrichment Plant Landfill and the Oak Ridge, Tennessee, Central Waste Disposal Facility for disposal of low-level radioactive waste was evaluated using pathways analyses. For these evaluations, a conservati...

F. G. Pin

1985-01-01

351

Analyses of Soils from an Area Adjacent to the Low-Level Radioactive Waste Disposal Site at Sheffield, Illinois.  

National Technical Information Service (NTIS)

Soil samples and field resistivity data were collected from an area adjacent to the Sheffield site. Specimens of Peoria Loess, Roxana Silt, Radnor Till, sand from the Toulon member, Hulick Till, and shale from the Pennsylvanian system were collected and a...

P. L. Piciulo C. E. Shea R. E. Barletta

1985-01-01

352

Chemical gradients in sediment cores from an EPA reference site off the Farallon Islands - Assessing chemical indicators of dredged material disposal in the deep sea  

USGS Publications Warehouse

Heavy metal and organic contaminants have been determined in undisturbed sediment cores from the US Environmental Protection Agency reference site for dredged material on the continental slope off San Francisco. As expected, the concentrations are significantly lower than toxic effects guidelines, but concentrations of PCBs, PAHs, Hg, Pb, and Clostridium perfringens (a bacterium spore found in sewage) were nearly two or more times greater in the surface sediments than in intervals deeper in the cores. These observations indicate the usefulness of measuring concentration gradients in sediments at the San Francisco deep ocean disposal site (SF-DODS) where a thin (0.5 cm thick) layer of dredged material has been observed beyond the boundary. This thin layer has not been chemically characterized by the common practice of homogenizing over the top 10 cm. An estimated 300 million cubic yards of dredged material from San Francisco Bay are expected to be discharged at the SF-DODS site during the next 50 years. Detailed depth analysis of sediment cores would add significant new information about the fate and effects of dredged material in the deep sea.

Bothner, M. H.; Gill, P. W.; Boothman, W. S.; Taylor, B. B.; Karl, H. A.

1998-01-01

353

Processes controlling the variations of pH, alkalinity, and CO2 partial pressure in the porewater of coal ash disposal site.  

PubMed

Alkalinity, pH, and pCO2 are generally regarded as the most important parameters affecting trace element leaching from coal ashes. However, little is known about how those parameters are actually regulated in the field condition. This study investigated the processes controlling those parameters by observing undisturbed porewater chemistry in a closed ash disposal site. The site is now covered with 30-50 cm thick soils according to the management scheme suggested by the Waste Management Law of Korea and our results show the important role of soil cover regulating those parameters in the shallow porewater. Without the soil cover, the shallow porewater shows low pCO2 and alkalinity, and highly alkaline pH. In contrast, the porewater shows much higher alkalinity and near neutral pH range when the site was covered with the low permeability soils. This difference was caused by the CO2 supply condition changes associated with the changes in infiltration rate. The geochemical modeling shows that the calcite precipitations induced by porewater aging, dolomitization, and weathering of solid phases are the main processes controlling alkalinity, pH, and pCO2 in the deep saline porewaters. The weathering of coal ash plays the most important role decreasing the alkalinity in the deep porewater. PMID:20627567

Kim, Kangjoo; Kim, Seok-Hwi; Park, Sung-Min; Kim, Jinsam; Choi, Mansik

2010-09-15

354

Operational technology for greater confinement disposal  

Microsoft Academic Search

Procedures and methods for the design and operation of a greater confinement disposal facility using large-diameter boreholes are discussed. It is assumed that the facility would be located at an operating low-level waste disposal site and that only a small portion of the wastes received at the site would require greater confinement disposal. The document is organized into sections addressing:

P. T. Dickman; A. T. Vollmer; P. H. Hunter

1984-01-01

355

ESTIMATED DURATION OF THE SUBSURFACE REDUCTION ENVIRONMENT PRODUCED BY THE SALTSTONE DISPOSAL FACILITY ON THE SAVANNAH RIVER SITE  

Microsoft Academic Search

The formula for Savannah River Site (SRS) saltstone includes 25 wt% slag to create a reducing environment for mitigating the subsurface transport of several radionuclides, including Tc-99. Based on laboratory measurements and two-dimensional reactive transport calculations, it was estimated that the SRS saltstone waste form will maintain a reducing environment, and therefore its ability to sequester Tc-99, for well over

D Kaplan; T Thong Hang

2007-01-01

356

The cleanup of releases of radioactive materials from commercial low-level radioactive waste disposal sites: Whose jurisdiction?  

Microsoft Academic Search

There exists an overlap between the Comprehensive Environmental Response, Compensation and Recovery Act ({open_quotes}CERCLA{close_quotes}) and the Atomic Energy Act ({open_quotes}AEA{close_quotes}) regarding the cleanup of releases of radioactive materials from commercial low-level radioactive waste sites. The Nuclear Regulatory Commission ({open_quotes}NRC{close_quotes}) and Agreement States have jurisdiction under the AEA, and the Environmental Protection Agency ({open_quotes}EPA{close_quotes}) has jurisdiction pursuant to CERCLA. This overlapping

Hartnett

1994-01-01

357

Slingram survey on the Nevada Test Site: part of an integrated geologic-geophysical study of site evaluation for nuclear waste disposal  

Microsoft Academic Search

A slingram geophysical survey was made in early 1978 as part of the integrated geological-geophysical study aimed at evaluating the Eleana Formation as a possible repository for nuclear waste. The slingram data were taken over an alluvial fan and pediments along the eastern flank of Syncline Ridge about 45 km north of Mercury, Nevada, on the Nevada Test Site. The

Flanigan

1979-01-01

358

Initial field trials of the site characterization and analysis penetrometer system (SCAPS). Reconnaissance of Jacksonville Naval Air Station waste oil and solvents disposal site. Final report  

SciTech Connect

At the request of the Naval Facilities Engineering Command (NAVFAC), Southern Division, Charleston, SC, the U.S. Army Engineer Waterways Experiment Station (WES) conducted the initial field trial of the Site Characterization and Analysis Penetrometer System (SCAPS) at Jacksonville Naval Air Station (NAS), Jacksonville FL. This work was carried out by a field crew consisting of personnel from WES and the Naval Ocean Systems Center during the period of 16 July 1990 to 14 August 1990. The SCAPS investigation at the Jacksonville NAS has two primary objectives: (a) to provide data that could be useful in formulating remediation plans for the facility and (b) to provide for the initial field trial of the SCAPS currently under development by WES for the U.S. Army Toxic and Hazardous Materials Agency (USATHAMA), now the U.S. Army Environmental Center. The original concepts for the SCAPS was to develop an integrated site screening characterization system whose capabilities would include (a) surface mapping, (b) geophysical surveys using magnetic, induced electromagnetic, and radar instruments, (c) measurements of soil strength, soil electrical resistivity, and laser-induced soil fluorometry Cone penetrometer, Site Characterization and Analysis Laser Induced Fluorescence(LIF), Penetrometer System(SCAPS) POL Contamination, using screening instrumentation mounted in a soil penetrometer, (d) soil and fluid samplers, and (e) computerized data acquisition, interpretation, and visualization. The goal of the SCAPS program is to provide detailed, rapid, and cost-effective surface and subsurface data for input to site assessment/remediation efforts.

Cooper, S.S.; Douglas, D.H.; Sharp, M.K.; Olsen, R.A.; Comes, G.D.

1993-12-01

359

Experimental and modeling study of adsorption desorption processes with application to a deep-well injection radioactive waste disposal site  

NASA Astrophysics Data System (ADS)

Radionuclide (Sr-90 and Cs-137) behavior in the subsurface environment was evaluated with respect to natural attenuation, sorption and desorption kinetics, and equilibrium. Batch experiments were conducted with synthesized groundwater or acid (NaNO 3; pH ?3) solutions under different temperature ( T=20 and 70 C) and pressure ( P= Patm and P=3 MPa) conditions. Samples of sedimentary rock were selected as the solid phase from a radioactively contaminated site associated with deep-well injection of the radioactive waste. Groundwater and a NaNO 3 waste-brine solution were used as the liquid phase. All experiments revealed hysteresis in radionuclide adsorption. Moreover, some of the experiments indicated that the adsorption process may be irreversible. A simultaneous temperature and pressure increase leads to anomalous behavior of the adsorption kinetics: a period of a rapid concentration drop of the radionuclides in solution, which is caused by their sorption uptake, is changed by a stage of a gradual increase in the corresponding concentrations. To explain the observed phenomena, several hypotheses were examined. Thus, an analytical model describing the mutual interference of adsorption kinetics and dissolution of carbonate minerals was developed resulting in a nonmonotonic behavior of the concentration curves obtained at the adsorption stage. For the description of the batch experiments with radionuclides at room temperature and atmospheric pressure, a dual-site adsorption model has been used.

Rumynin, V. G.; Konosavsky, P. K.; Hoehn, E.

2005-01-01

360

Peculiarities of the High-Level Concrete-Encased Radwaste Repository Disposition at the Radwaste Disposal Site of the Russian Research Center 'Kurchatov Institute'  

SciTech Connect

The paper presents peculiarities of organization and performance of activities on disposition of the old repository that contained high-level waste and located at the radwaste disposal site of the Russian Research Center 'Kurchatov Institute' in Moscow. The repository was constructed in the late 1950's. A large number of cases with high-level waste were placed in the repository along with low- and intermediate-level waste. When the repository was filled in 1973, the entire radwaste mass was encased in concrete matrix which caused difficulties with the radwaste extraction and made the work on the repository disposition highly hazardous in terms of radiation conditions. Based on results of the preliminary radiation survey of the repository, technologies and equipment to be used in disposition works were selected, and a decision on construction of external radiation shielding around the repository to maintain normal radiation conditions during these works was made. Specific features of the selected radiation shielding design constructed around the repository and of a technology used for the radwaste extraction from the repository are provided. According to the technology, conventional construction machines equipped with a hydraulic hammer or a clamshell were used for destruction of the concrete-encased radwaste mass and extraction of low-level waste. Intermediate- and high-level waste was extracted by remotely controlled robots operating inside the radiation shielding structure. Video cameras and a gamma imager were used for detection of high-level waste or fragments of such radwaste in the mass concrete being destroyed and for guiding remotely controlled robots. Peculiarities of rapid control of changes in radiation conditions in the working areas are presented. This control was performed using a gamma locator with on-line transmission of its data to a PC for their processing. With disposition of this not easily accessible repository, the stage of remediation of old repositories at the Kurchatov Institute radwaste disposal site approached completion. At present the work on soil decontamination is being continued at the site, and residual contamination of the soil and groundwater is being examined. (authors)

Volkov, V.G.; Ponomarev-Stepnoi, N.N.; Gorodetsky, G.G.; Zverkov, Yu.A.; Ivanov, O.P.; Lemus, A.V.; Semenov, S.G.; Stepanov, V.E.; Chesnokov, A.V.; Shisha, A.D. [Russian Research Center 'Kurchatov Institute', 1 Kurchatov Square, Moscow 123182 (Russian Federation)

2006-07-01

361

Disposal Rabbit.  

National Technical Information Service (NTIS)

A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation ...

L. C. Lewis D. R. Trammell

1983-01-01

362

Chromium speciation and fractionation in ground and surface waters in the vicinity of chromite ore processing residue disposal sites.  

PubMed

Chromium concentrations of up to 91 mg l(-1) were found by ICP-OES for ground water from nine boreholes at four landfill sites in an area of S.E. Glasgow/S. Lanarkshire where high-lime chromite ore processing residue (COPR) from a local chemical works had been deposited from 1830 to 1968. Surface water concentrations of up to 6.7 mg l(-1) in a local tributary stream fell to 0.11 mg l(-1) in the River Clyde. Two independent techniques of complexation/colorimetry and speciated isotope dilution mass spectrometry (SIDMS) showed that Cr was predominantly (>90%) in hexavalent form (CrVI) as CrO4(2-), as anticipated at the high pH (7.5-12.5) of the sites. Some differences between the implied and directly determined concentrations of dissolved CrIII, however, appeared related to the total organic carbon (TOC) content. This was most significant for the ground water from one borehole that had the highest TOC concentration of 300 mg l(-1) and at which < 3% of Cr was in the form of CrVI. Subsequent ultrafiltration produced significant decreases in Cr concentration with decreasing size fractions, e.g. <0.45 microm, < 100 kDa, <30 kDa and < 1 kDa by the tangential-flow method. As this appeared related more to concentrations of humic substances than of TOC per se, horizontal bed gel electrophoresis of freeze-dried ultrafilter retentates was carried out to further characterise the CrIII-organic complex. This showed for the main Cr-containing fraction, 100 kDa-0.45 microm, that the Cr was associated with a dark brown band characteristic of organic (humic) matter. Comparison of gel electrophoresis and FTIR results for ultrafilter retentates of ground water from this borehole with those for a borehole at another site where CrVI predominated suggested the influence of carboxylate groups, both in reducing CrVI and in forming soluble CrIII-humic complexes. The implications of this for remediation strategies (especially those based on the addition of organic matter) designed to reduce highly mobile and carcinogenic Cr(VI)O4(2-) to the much less harmful CrIII as insoluble Cr(OH)3 are discussed. PMID:11993762

Farmer, John G; Thomas, Rhodri P; Graham, Margaret C; Geelhoed, Jeanine S; Lumsdon, David G; Paterson, Edward

2002-04-01

363

Savannah River Site's macro encapsulation processing of Less Than 3700 BQ\\/GM1 tru isotopic mixed waste for disposal at the Nevada Test Site  

Microsoft Academic Search

During the Fiscal Year of 2006 (FY2006) the Savannah River Site (SRS) made a commitment with the South Carolina Department of Health and Environmental Control (SC-DHEC) to remove 1000 cubic meters of Transuranic (TRU) waste from its TRU inventory. As SRS has been generating TRU waste for many years, there was a multi-thousand drum inventory of waste designated as TRU

G. W. Siry; L. T. Reid

2007-01-01

364

40 CFR 228.10 - Evaluating disposal impact.  

Code of Federal Regulations, 2010 CFR

...disposal site of pollution-sensitive biota characteristic of the general area; ...numbers of pelagic, demersal, or benthic biota at or near the disposal site, when these...limitation, human pathogens) in marine biota at or near the site. (c)...

2009-07-01

365

40 CFR 228.10 - Evaluating disposal impact.  

Code of Federal Regulations, 2010 CFR

...disposal site of pollution-sensitive biota characteristic of the general area; ...numbers of pelagic, demersal, or benthic biota at or near the disposal site, when these...limitation, human pathogens) in marine biota at or near the site. (c)...

2010-07-01

366

ESTIMATED DURATION OF THE SUBSURFACE REDUCTION ENVIRONMENT PRODUCED BY THE SALTSTONE DISPOSAL FACILITY ON THE SAVANNAH RIVER SITE.  

SciTech Connect

The formula for Savannah River Site (SRS) saltstone includes {approx}25 wt% slag to create a reducing environment for mitigating the subsurface transport of several radionuclides, including Tc-99. Based on laboratory measurements and two-dimensional reactive transport calculations, it was estimated that the SRS saltstone waste form will maintain a reducing environment, and therefore its ability to sequester Tc-99, for well over 10,000 years. For example, it was calculated that {approx}16% of the saltstone reduction capacity would be consumed after 213,000 years. For purposes of comparison, a second calculation was presented that was based on entirely different assumptions (direct spectroscopic measurements and diffusion calculations). The results from this latter calculation were near identical to those from this study. Obtaining similar conclusions by two extremely different calculations and sets of assumptions provides additional credence to the conclusion that the saltstone will likely maintain a reducing environment in excess of 10,000 years.

Kaplan, D; Thong Hang, T

2007-01-22

367

Water and tritium movement through the unsaturated zone at a low-level radioactive-waste disposal site near Sheffield, Illinois, 1981-85  

USGS Publications Warehouse

The movement of water and tritium through the unsaturated zone was studied at a low-level radioactive-waste disposal site near Sheffield, Bureau County, Illinois, from 1981 to 1985. Water and tritium movement occurred in an annual, seasonally timed cycle; recharge to the saturated zone generally occurred in the spring and early summer. Mean annual precipitation (1982-85) was 871 millimeters; mean annual recharge to the disposal trenches (July 1982 through June 1984) was estimated to be 107 millimeters. Average annual tritium flux below the study trenches was estimated to be 3.4 millicuries per year. Site geology, climate, and waste-disposal practices influenced the spatial and temporal variability of water and tritium movement. Of the components of the water budget, evapotranspiration contributed most to the temporal variability of water and tritium movement. Disposal trenches are constructed in complexly layered glacial and postglacial deposits that average 17 meters in thickness and overlie a thick sequence of Pennsylvanian shale. The horizontal saturated hydraulic conductivity of the clayey-silt to sand-sized glacial and postglacial deposits ranges from 4.8x10^-1 to 3.4x10^4 millimeters per day. A 120-meter-long horizontal tunnel provided access for hydrologic measurements and collection of sediment and water samples from the unsaturated and saturated geologic deposits below four disposal trenches. Trench-cover and subtrench deposits were monitored with soil-moisture tensiometers, vacuum and gravity lysimeters, piezometers, and a nuclear soil-moisture gage. A cross-sectional, numerical ground-water-flow model was used to simulate water movement in the variably saturated geologic deposits in the tunnel area. Concurrent studies at the site provided water-budget data for estimating recharge to the disposal trenches. Vertical water movement directly above the trenches was impeded by a zone of compaction within the clayey-silt trench covers. Water entered the trenches primarily at the trench edges where the compacted zone was absent and the cover was relatively thin. Collapse holes in the trench covers that resulted from inadequate compaction of wastes within the trenches provided additional preferential pathways for surface-water drainage into the trenches; drainage into one collapse hole during a rainstorm was estimated to be 1,700 liters. Till deposits near trench bases induced lateral water and tritium movement. Limited temporal variation in water movement and small flow gradients (relative to the till deposits) were detected in the unsaturated subtrench sand deposit; maximum gradients during the spring recharge period averaged 1.62 millimeters per millimeter. Time-of-travel of water moving from the trench covers to below the trenches was estimated to be as rapid as 41 days (assuming individual water molecules move this distance in one recharge cycle). Tritium concentrations in water from the unsaturated zone ranged from 200 (background) to 10,000,000 pCi/L (picocuries per liter). Tritium concentrations generally were higher below trench bases (averaging 91,000 pCi/L) than below intertrench sediments (averaging 3,300 pCi/L), and in the subtrench Toulon Member of the Glasford Formation (sand) (averaging 110,000 pCi/L) than in the Hulick Till Member of the Glasford Formation (clayey silt) (averaging 59,000 pCi/L). Average subtrench tritium concentration increased from 28,000 to 100,000 pCi/L during the study period. Within the trench covers, there was a strong seasonal trend in tritium concentrations; the highest concentrations occurred in late summer when soil-moisture contents were at a minimum. Subtrench tritium movement occurred in association with the annual cycle of water movement, as well as independently of the cycle, in apparent response to continuous water movement through the subtrench sand deposits and to the deterioration of trench-waste containers. The increase in concentrations of tritium with incre

Mills, Patrick C.; Healy, R. W.

1991-01-01

368

Water and tritium movement through the unsaturated zone at a low-level radioactive-waste disposal site near Sheffield, Illinois, 1981-85  

USGS Publications Warehouse

The movement of water and tritium through the unsaturated zone was studied at a low-level radioactive-waste disposal site near Sheffield, Bureau County, Illinois, from 1981 to 1985. Water and tritium movement occurred in an annual, seasonally timed cycle; recharge to the saturated zone generally occurred in the spring and early summer. Mean annual precipitation (1982-85) was 871 mm (millimeters); mean annual recharge to the disposal trenches (July 1982 through June 1984) was estimated to be 107 mm. Average annual tritium flux below the study trenches was estimated to be 3.4 mCi/yr (millicuries per year). Site geology, climate, and waste-disposal practices influenced the spatial and temporal variability of water and tritium movement. Of the components of the water budget, evapotranspiration contributed most to the temporal variability of water and tritium movement. Disposal trenches are constructed in complexly layered glacial and postglacial deposits that average 17 m (meters) in thickness and overlie a thick sequence of Pennsylvanian shale. The horizontal saturated hydraulic conductivity of the clayey-silt to sand-sized glacial and postglacial deposits ranges from 4.8x10 -1 to 3.4x10 4 mm/d (millimeters per day). A 120-m-long horizontal tunnel provided access for hydrologic measurements and collection of sediment and water samples from the unsaturated and saturated geologic deposits below four disposal trenches. Trench-cover and subtrench deposits were monitored with soil-moisture tensiometers, vacuum and gravity lysimeters, piezometers, and a nuclear soil-moisture gage. A cross-sectional, numerical ground-water-flow model was used to simulate water movement in the variably saturated geologic deposits in the tunnel area. Concurrent studies at the site provided water-budget data for estimating recharge to the disposal trenches. Vertical water movement directly above the trenches was impeded by a zone of compaction within the clayey-silt trench covers. Water entered the trenches primarily at the trench edges where the compacted zone was absent and the cover was relatively thin. Collapse holes in the trench covers that resulted from inadequate compaction of wastes within the trenches provided additional preferential pathways for surface-water drainage into the trenches; drainage into one collapse hole during a rainstorm was estimated to be 1,700 L (liters). Till deposits near trench bases induced lateral water and tritium movement. Limited temporal variation in water movement and small flow gradients (relative to the till deposits) were detected in the unsaturated subtrench sand deposit; maximum gradients during the spring recharge period averaged 1.62 mm/mm (millimeter per millimeter). Time-of-travel of water moving from the trench covers to below the trenches was estimated to be as rapid as 41 days (assuming individual water molecules move this distance in one recharge cycle). Tritium concentrations in water from the unsaturated zone ranged from 200 (background) to 10,000,000 pCi/L (picocuries per liter). Tritium concentrations generally were higher below trench bases (averaging 91,000 pCi/L) than below intertrench sediments (averaging 3,300 pCi/L), and in the subtrench Toulon Member of the Glasford Formation (sand) (averaging 110,000 pCi/L) than in the Hulick Till Member of the Glasford Formation (clayey silt) (averaging 59,000 pCi/L). Average subtrench tritium concentration increased from 28,000 to 100,000 pCi/L during the study period. Within the trench covers, there was a strong seasonal trend in tritium concentrations; the highest concentrations occurred in late summer when soil-moisture contents were at a minimum. Subtrench tritium movement occurred in association with the annual cycle of water movement, as well as independently of the cycle, in apparent response to continuous water movement through the subtrench sand deposits and to the deterioration of trench-waste containers. The increase in concen

Mills, Patrick C.; Healy, Richard W.

1993-01-01

369

Fate of high loads of ammonia in a pond and wetland downstream from a hazardous waste disposal site.  

PubMed

Halls Brook (eastern Massachusetts, USA) is a significant source of total dissolved ammonia (sum of NH(3) and NH(4)(+); (NH(3))(T)) to the Aberjona River, a water body listed for NH(3) impairment on the Clean Water Act section 303(d) list. We hypothesized (1) that (NH(3))(T) in Halls Brook derived from a hazardous waste site via groundwater discharging to a two-basin pond that feeds the brook; and (2) that transport of (NH(3))(T) to the Aberjona River was controlled by lacustrine and wetland processes. To test these hypotheses we measured (NH(3))(T) levels in the brook, the pond, and a wetlands directly downstream of the pond during both dry and wet weather over a ten month period. In addition, we analyzed sediment cores and nitrogen isotopes, and performed mass balance calculations. Groundwater discharge from beneath the hazardous waste site was the major source of (NH(3))(T) (20-67 kg d(-1)) and salinity to the north basin of the pond. The salty bottom waters of the north basin were anoxic on all sampling dates, and exhibited relatively stable (NH(3))(T) concentrations between 200 and 600 mg Nl(-1). These levels were >100-times higher than typical background levels, and 8-24-times above the acute effects level for (NH(3))(T) toxicity. Bottom waters from the north basin continuously spill over into the south basin contributing approximately 50% of the (NH(3))(T) load entering this basin. The remainder comes from Halls Brook, which receives (NH(3))(T) loadings from as yet unknown sources upstream. During storm events up to 50% of the mass of (NH(3))(T) was flushed from the south basin and into the wetlands. The wetlands acted as a (NH(3))(T) sink in dry weather in the growing season and a discharge-dependent (NH(3))(T) source to the Aberjona River during rainstorms. PMID:17346773

Cutrofello, Michele; Durant, John L

2007-07-01

370

Results of a Survey of Residential Home Heating Fuel and Stove Type and Use in the Shiprock Area of the Navajo Nation  

USGS Publications Warehouse

For many Navajo people, coal provides an affordable and convenient means of home heating. However, coal combustion results in the formation and mobilization of materials that are known risk factors for respiratory and other diseases. The level of respiratory morbidity among the Navajo people is higher than can be explained by usual epidemiological risk factors. The Shiprock area of the Navajo Nation is somewhat unique in that atmospheric thermal inversions trap air pollution low to the ground, especially in winter. There are two large mine mouth coal-fired power plants located in the vicinity, with a third plant in the planning stages. Both of the existing power plants are exempt from regulation under the U.S. Environmental Protection Agency 1990 Amendments to the Clean Air Act due to their age. The purpose of this survey was to assess the fuel and stove type and use, and document other household characteristics that might be related to the exposure of potentially toxic coal combustion products. A total of 137 surveys was conducted in English and Navajo to ascertain and document fuel usage and the type, size and conditions of heating stoves used in both traditional and modern homes. Results have been presented to the community at the Shiprock Chapter in the Navajo language. To increase public awareness, ways to properly use and store coal and to improve stove function and ventilation were also shared.

Bunnell, Joseph E.; Garcia, Linda V.

2008-01-01

371

Disposal of radioactive waste  

NASA Astrophysics Data System (ADS)

The aim of radioactive and non-radioactive waste management is to protect man and the environment from unacceptable risks. Protection criteria for both should therefore be based on similar considerations. From overall protection criteria, performance criteria for subsystems in waste management can be derived, for example for waste disposal. International developments in this field are summarized. A brief overview of radioactive waste sorts and disposal concepts is given. Currently being implemented are trench disposal and engineered near-surface facilities for low-level wastes. For low-and intermediate-level waste underground facilities are under construction. For high-level waste site selection and investigation is being carried out in several countries. In all countries with nuclear programmes, the predicted performance of waste disposal systems is being assessed in scenario and consequence analyses. The influences of variability and uncertainty of parameter values are increasingly being treated by probabilistic methods. Results of selected performance assessments show that radioactive waste disposal sites can be found and suitable repositories can be designed so that defined radioprotection limits are not exceeded.

Van Dorp, Frits; Grogan, Helen; McCombie, Charles

372

Estimated duration of the subsurface reduction environment produced by the salt-stone disposal facility on the Savannah River Site  

SciTech Connect

The formula for Savannah River Site (SRS) salt-stone includes {approx}25 wt% slag to create a reducing environment for mitigating the subsurface transport of several radionuclides, including Tc-99. Based on laboratory measurements and two-dimensional reactive transport calculations, it was estimated that the SRS salt-stone waste form will maintain a reducing environment, and therefore its ability to sequester Tc-99, for well over 10,000 years. For example, it was calculated that {approx}16% of the salt-stone reduction capacity would be consumed after 213,000 years. For purposes of comparison, a second calculation was presented that was based on entirely different assumptions (direct spectroscopic measurements and diffusion calculations). The results from this latter calculation were near identical to those from this study. Obtaining similar conclusions by two extremely different calculations and sets of assumptions provides additional credence to the conclusion that the salt-stone will likely maintain a reducing environment in excess of 10,000 years. (authors)

Kaplan, D.I.; Hang, T. [Savannah River National Laboratory, Carolina (United States)

2007-07-01

373

Assessing doses to terrestrial wildlife at a radioactive waste disposal site: inter-comparison of modelling approaches.  

PubMed

Radiological doses to terrestrial wildlife were examined in this model inter-comparison study that emphasised factors causing variability in dose estimation. The study participants used varying modelling approaches and information sources to estimate dose rates and tissue concentrations for a range of biota types exposed to soil contamination at a shallow radionuclide waste burial site in Australia. Results indicated that the dominant factor causing variation in dose rate estimates (up to three orders of magnitude on mean total dose rates) was the soil-to-organism transfer of radionuclides that included variation in transfer parameter values as well as transfer calculation methods. Additional variation was associated with other modelling factors including: how participants conceptualised and modelled the exposure configurations (two orders of magnitude); which progeny to include with the parent radionuclide (typically less than one order of magnitude); and dose calculation parameters, including radiation weighting factors and dose conversion coefficients (typically less than one order of magnitude). Probabilistic approaches to model parameterisation were used to encompass and describe variable model parameters and outcomes. The study confirms the need for continued evaluation of the underlying mechanisms governing soil-to-organism transfer of radionuclides to improve estimation of dose rates to terrestrial wildlife. The exposure pathways and configurations available in most current codes are limited when considering instances where organisms access subsurface contamination through rooting, burrowing, or using different localised waste areas as part of their habitual routines. PMID:22578842

Johansen, M P; Barnett, C L; Beresford, N A; Brown, J E; ?erne, M; Howard, B J; Kamboj, S; Keum, D-K; Smodi, B; Twining, J R; Vandenhove, H; Vives i Batlle, J; Wood, M D; Yu, C

2012-06-15

374

A slingram survey on the Nevada Test Site: part of an integrated geologic geophysical study of site evaluation for nuclear waste disposal  

USGS Publications Warehouse

A slingram geophysical survey was made in early 1978 as part of the integrated geologlcal-geophysical study aimed at evaluating the Eleana Formation as a possible repository for nuclear waste. The slingram data were taken over an alluvial fan and pediments along the eastern flank of Syncline Ridge about 45 km north of Mercury, Nevada, on the Nevada Test Site. The data show that the more conductive argillaceous Eleana Formation varies in depth from 40 to 85 m from west to east along traverse lines. Northeast-trending linear anomalies suggest rather abrupt changes in subsurface geology that may be associated with faults and fractures. The results of the slingram survey will, when interpreted in the light of other geologic and geophysical evidence, assist in understanding the shallow parts of the geologic setting of the Eleana Formation.

Flanigan, Vincent J.

1979-01-01

375

Results of Tritium Tracking and Groundwater Monitoring at the Hanford Site 200 Area State-Approved Land Disposal Site--Fiscal Year 2000  

SciTech Connect

The Hanford Site 200 Area Effluent Treatment Facility (ETF) processes contaminated liquids derived from Hanford Site facilities. Groundwater monitoring for tritium and other constituents is required by the state-issued permit at 22 wells surrounding the facility. Water level measurements in nearby wells indicate that a small hydraulic mound exists around the SALDS facility as a result of discharges. Evaluation of this condition indicates that the network is currently adequate for tracking potential effects of the SALDS on the groundwater. During FY 2000, average tritium activities in most wells declined from average activities in 1999. The exception was deep well 699-48-77C, where tritium results were at an all-time high (710,000 pCi/L) as a result of the delayed penetration of effluent deeper into the aquifer. Of the 12 constituents with permit enforcement limits, which are monitored in SALDS proximal wells, all were within groundwater limitations during FY 2000. Analyses for conductivity, total dissolved solids, sulfate, chloride, sulfate, dissolved calcium, and dissolved sodium indicate that well 699-48-77A and, to a lesser extent, well 699-48-77D show the effects of dilute effluent entering groundwater, resulting in a depression of concentrations of these constituents below natural background levels. Recommendations for future monitoring include temporarily increasing the frequency of tritium sampling at wells 299-W7-3, 299-W7-5, and 299-W7-7 to quarterly. This measure may assist in a more accurate determination of the southern bounds of the SALDS-generated tritium plume, provide estimates of travel time for model comparisons, and help preserve the distinction between this plume and the older 200 West tritium plume further east.

Barnett, D. Brent

2000-09-26

376

Improved production of recombinant human Fas ligand extracellular domain in Pichia pastoris: yield enhancement using disposable culture-bag and its application to site-specific chemical modifications  

PubMed Central

Background A useful heterologous production system is required to obtain sufficient amounts of recombinant therapeutic proteins, which are often necessary for chemical characterization and engineering studies on the development of molecules with improved properties. Human Fas ligand extracellular domain (hFasLECD) is an agonistic death ligand protein that has potential applications for medical purposes. Site-specific chemical modifications can provide a powerful means for the development of engineered proteins with beneficial functions. This study aimed to enhance the yield of hFasLECD using a Pichia pastoris secretory expression system suitable for efficient production on a small laboratory scale, and further to provide procedures for its site-specific chemical modification without impairing the biological functions based on the developed production system. Results A convenient cultivation system using a disposable plastic bag provided a three-fold increase in purification yield of tag-free hFasLECD as compared with the conventional system using a baffled glass flask. The system was further applied to the production of a mutant, which contains an additional reactive cysteine residue in the N-terminal tag-sequence region. Site-specific conjugations and cross-linking without impairing biological functions were achieved by reaction of the mutant hFasLECD with single maleimide group containing compounds and a linear polyethylene glycol derivative containing two maleimide groups at either end, respectively. All purified tag-free and chemically modified hFasLECDs showed an evident receptor binding activity in co-immunoprecipitation experiments mediated by wild-type and N-glycosylation site deficient mutant human Fas receptor extracellular domain derivatives. An N-Ethylmaleimide conjugated hFasLECD derivative demonstrated a significant cytotoxic activity against human HT-29 colorectal cancer cells. Conclusions A new, efficient cultivation system for enhanced secretory production of hFasLECD using P. pastoris and an effective strategy for site-specific chemical modifications of hFasLECD were devised. The results obtained constitute the basis for biomedical applications including developments of novel therapeutic proteins and diagnostic tools targeted to related diseases and their biomarkers.

2014-01-01

377

Diversity and characterization of sulfate-reducing bacteria in groundwater at a uranium mill tailings site.  

PubMed

Microbially mediated reduction and immobilization of U(VI) to U(IV) plays a role in both natural attenuation and accelerated bioremediation of uranium-contaminated sites. To realize bioremediation potential and accurately predict natural attenuation, it is important to first understand the microbial diversity of such sites. In this paper, the distribution of sulfate-reducing bacteria (SRB) in contaminated groundwater associated with a uranium mill tailings disposal site at Shiprock, N.Mex., was investigated. Two culture-independent analyses were employed: sequencing of clone libraries of PCR-amplified dissimilatory sulfite reductase (DSR) gene fragments and phospholipid fatty acid (PLFA) biomarker analysis. A remarkable diversity among the DSR sequences was revealed, including sequences from delta-Proteobacteria, gram-positive organisms, and the Nitrospira division. PLFA analysis detected at least 52 different mid-chain-branched saturate PLFA and included a high proportion of 10me16:0. Desulfotomaculum and Desulfotomaculum-like sequences were the most dominant DSR genes detected. Those belonging to SRB within delta-Proteobacteria were mainly recovered from low-uranium (< or =302 ppb) samples. One Desulfotomaculum-like sequence cluster overwhelmingly dominated high-U (>1,500 ppb) sites. Logistic regression showed a significant influence of uranium concentration over the dominance of this cluster of sequences (P = 0.0001). This strong association indicates that Desulfotomaculum has remarkable tolerance and adaptation to high levels of uranium and suggests the organism's possible involvement in natural attenuation of uranium. The in situ activity level of Desulfotomaculum in uranium-contaminated environments and its comparison to the activities of other SRB and other functional groups should be an important area for future research. PMID:11425735

Chang, Y J; Peacock, A D; Long, P E; Stephen, J R; McKinley, J P; Macnaughton, S J; Hussain, A K; Saxton, A M; White, D C

2001-07-01

378

Diversity and characterization of sulfate-reducing bacteria in groundwater at a uranium mill tailings site  

SciTech Connect

Microbially mediated reduction and immobilization of U(VI) to U(TV) plays a role in both natural attenuation and accelerated bioremediation of uranium contaminated sites. To realize bioremediation potential and accurately predict natural attenuation, it is important to first understand the microbial diversity of such sites. In this paper, the distribution of sulfate-reducing bacteria (SRB) in contaminated groundwater associated with a uranium mill tailings disposal site at Shiprock, N.Mex,, was investigated. Two culture-independent analyses were employed: sequencing of clone libraries of PCR-amplified dissimilatory sulfite reductase (DSR) gene fragments and phospholipid fatty acid (PLFA) biomarker analysis. A remarkable diversity among the DSR sequences was revealed, including sequences from F-Proteobacteria, gram-positive organisms, and the Nitrospira division. PLFA analysis detected at least,52 different mid-chain-branched saturate PLFA and included a high proportion of 10me16:0, Desulfotomaculum and Desulfotomaculum-like sequences were the most dominant DSR genes detected. Those belonging to SRB within F-Proteobacteria were mainly recovered from low-uranium (less than or equal to 302 ppb) samples. One Desulfotomaculum like sequence cluster overwhelmingly dominated high-U (> 1,500 ppb) sites. Logistic regression showed a significant influence of uranium concentration over the dominance of this cluster of sequences (P= 0.0001), This strong association indicates that Desulfotomaculum has remarkable tolerance and adaptation to high levels of uranium and suggests the organism's possible involvement in natural attenuation of uranium. The in situ activity level of Desulfotomaculum in uranium-contaminated environments and its comparison to the activities of other SRB and other functional groups should be an important area for future research.

Chang, Yun-Juan (Unknown); Peacock, A D. (Tennessee, Univ Of); Long, Philip E. (BATTELLE (PACIFIC NW LAB)); Stephen, John R. (Unknown); McKinley, James P. (BATTELLE (PACIFIC NW LAB)); Mcnaughton, Sarah J. (Unknown); Hussain, A K M A.; Saxton, A M.; White, D C. (Unknown)

2000-12-01

379

Characterization of a Cd(2+)-resistant strain of Ochrobactrum sp. isolated from slag disposal site of an iron and steel factory.  

PubMed

A cadmium-resistant bacterium designated as CdSP9 was isolated from the slag disposal site of IISCO, Burnpur, West Bengal, India. The isolate was identified as Ochrobactrum sp. on the basis of 16S rDNA sequence-based molecular phylogenetic approach and phenotypic characteristics. It is a Gram negative, short rod (0.5-1.0 micro), aerobic bacterium, growing well in LB medium between temperatures 10-42 degrees C, pH 6.0-9.0, and between 2 and 6% NaCl. The most preferred nitrogen and carbon sources for the strain are L: -proline, L: -lysine and fructose, maltose, respectively. Superoxide toxicity minimization by increased level of SOD activity also occurs in this bacterium. The heavy metal accumulation efficiency as determined by atomic absorption spectroscopy was found to be 0.214 mg/g of the dry weight at late log phase. The accumulation efficiency was directly proportional to the optimum growth conditions. PMID:20091408

Pandey, Sanjeev; Saha, Pradipta; Barai, Prabir Kumar; Maiti, Tushar K

2010-08-01

380

Lung cancer in relation to residence in census tracts with toxic-waste disposal sites: a case-control study in Niagara County, New York  

SciTech Connect

Nine selected census tracts containing 12 toxic-waste disposal sites with known or suspected lung carcinogens were identified in Niagara County, New York. Analysis of death certificates of 339 lung cancer cases (decedents) and 676 controls who died of other causes excluding respiratory diseases in 1978-1981 showed no association between death from lung cancer and residence in the selected census tracts (odds ratio = 0.95; 95% confidence interval = 0.65-1.38). Analysis of mail questionnaires from surrogate respondents for 209 lung cancer decedents and 417 controls showed no significant association between lung cancer and a history of ever having resided in the selected census tracts (age-adjusted odds ratio = 1.17; 95% CI = 0.78-1.76) and no significant interaction between such residence and cigarette smoking. Duration of residence in the selected census tracts did not differ between cases and controls. The limitations of this low-cost study design, in terms of response rates and potential misclassification of exposure, were discussed along with its value in interim studies of potentially hazardous dumpsites (prior to more intensive case-control or other studies using better exposure data).

Polednak, A.P.; Janerich, D.T.

1989-02-01

381

Rapid on-site separation of As(III) and As(V) in waters using a disposable thiol-modified sand cartridge.  

PubMed

The rapid redox transformation of arsenic (As) species in waters presents a great environmental challenge in the accurate determination of its concentration and toxicity. The motivation of the present study was therefore to develop a method for rapid on-site separation of As(V) and As(III) in various aqueous matrices. The authors synthesized a thiol-modified sand (T-sand) that selectively removed As(III) but did not adsorb As(V). The novel application of this T-sand in a disposable cartridge was able to successfully separate As(V) (37-970?g?L(-1) ) and As(III) (not detected to 488?g?L(-1) ) in 23 groundwater samples collected in areas with naturally occurring As. The As speciation results determined with T-sand separation in the field were consistent with those obtained using high-performance liquid chromatography-atomic fluorescence spectrometry. Furthermore, the T-sand cartridge was applicable in a wide variety of matrices, including groundwater, leachants of the toxicity-characteristic leaching procedure, and extracts from the California waste extraction test; sequential extraction test; and in vitro gastrointestinal extraction. This easy-to-use separation method is especially suitable for routine field monitoring of As speciation. Environ Toxicol Chem 2014;33:1692-1696. 2014 SETAC. PMID:24619954

Du, Jingjing; Che, Dongsheng; Zhang, Jianfeng; Jing, Chuanyong

2014-08-01

382

Field study for disposal of solid wastes from Advanced Coal Processes: Ohio LIMB Site Assessment. Final report, April 1986--November 1994  

SciTech Connect

New air pollution regulations will require cleaner, more efficient processes for converting coal to electricity, producing solid byproducts or wastes that differ from conventional pulverized-coal combustion ash. Large scale landfill test cells containing byproducts were built at 3 sites and are to be monitored over at least 3 years. This report presents results of a 3-y field test at an ash disposal site in northern Ohio; the field test used ash from a combined lime injection-multistage burner (LIMB) retrofit at the Ohio Edison Edgewater plant. The landfill test cells used LIMB ash wetted only to control dusting in one cell, and LIMB ash wetted to optimize compaction density in the other cell. Both test cells had adequate load-bearing strength for landfill stability but had continuing dimensional instability. Heaving and expansion did not affect the landfill stability but probably contributed to greater permeability to infiltrating water. Leachate migration occurred from the base, but effects on downgradient groundwater were limited to increased chloride concentration in one well. Compressive strength of landfilled ash was adequate to support equipment, although permeability was higher and strength was lower than anticipated. Average moisture content has increased to about 90% (dry weight basis). Significant water infiltration has occurred; the model suggests that as much as 20% of the incident rainfall will pass through and exit as leachate. However, impacts on shallow ground water is minimal. Results of this field study suggest that LIMB ash from combustion of moderate to high sulfur coals will perform acceptably if engineering controls are used to condition and compact the materials, reduce water influx to the landfill, and minimize leachate production. Handling of the ash did not pose serious problems during cell construction; steaming and heat buildup were moderate.

Weinberg, A.; Coel, B.J.; Butler, R.D.

1994-10-01

383

Disposable Scholarship?  

ERIC Educational Resources Information Center

The digital materials that faculty produce for their classrooms often are saved only to storage devices that might become obsolete in a few years. Without an institutional effort to provide access systems, storage, and services for their digital media, are campuses in danger of creating "Disposable Scholarship"? In this article, the author

Miller, Fredrick

2004-01-01

384

Disposal rabbit  

DOEpatents

A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

Lewis, L.C.; Trammell, D.R.

1983-10-12

385

Disposable rabbit  

DOEpatents

A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

Lewis, Leroy C. (Idaho Falls, ID) [Idaho Falls, ID; Trammell, David R. (Rigby, ID) [Rigby, ID

1986-01-01

386

DREDGED MATERIAL DISPOSAL MANAGEMENT MODELS  

EPA Science Inventory

US Army Corps of Engineers public web site with computer models, available for download, used in evaluating various aspects of dredging and dredged material disposal. (landfill and water Quality models are also available at this site.) The site includes the following dredged mate...

387

Removal site evaluation report L-area rubble pile (131-3L) gas cylinder disposal facility (131-2L)  

SciTech Connect

This Removal Site Evaluation Report (RSER) is prepared in accordance with Sections 300.410 and 300.415 of the National Contingency Plan and Section XIV of the Savannah River Site (SRS) Federal Facility Agreement (FFA). The purpose of this investigation is to report information concerning conditions at the L-Area Rubble Pile (LRP) (131-3L) and the L-Area Gas Cylinder Disposal Facility (LGCDF) (131- 2L) sufficient to assess the threat posed to human health and the environment. This investigation also assesses the need for additional Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) actions. The scope of this investigation included a review of files, limited sampling efforts, and visits to the area. An investigation of the LRP (1131-3L) indicates the presence of semi volatile organic compounds (SVOCs), volatile organic compounds (VOCs), metals, and asbestos. Potential contaminants in the waste piles could migrate into the secondary media (soils and groundwater), and the presence of some of the contaminants in the piles poses an exposure threat to site works. The Department of Energy (DOE), United States Environmental Protection Agency (EPA) and South Carolina Department of Health and Environmental Control (SCDHEC) discussed the need for a removal action at the Resource Conservation and Recovery Act (RCRA) Facility Investigation/Remedial Investigation (RFI/RI) work plan scoping meetings on the waste unit, and agreed that the presence of the waste piles limits the access to secondary media for sampling, and the removal of the piles would support future characterization of the waste unit. In addition, the DOE, EPA, and SCDHEC agreed that the proposed removal action for the LRP (131-3L) would be documented in the RFI/RI work plan. The LGCDF (131-2L) consists of a backfilled pit containing approximately 28 gas cylinders. The gas cylinders were supposed to have been vented prior to burial; however, there is a potential that a number of the cylinders are still pressurized. (Abstract Truncated)

Palmer, E.R. [Westinghouse Savannah River Company, AIKEN, SC (United States); Mason, J.T.

1997-10-01

388

Modeling Np and Pu Transport with a Surface Complexation Model and Spatially Variant Sorption Capacities: Implications for Reactive Transport Modeling and Performance Assessments of Nuclear Waste Disposal Sites  

NASA Astrophysics Data System (ADS)

One-dimensional (1D) geochemical transport modeling is used to demonstrate the effects of speciation and sorption reactions on the ground-water transport of Np and Pu, two redox-sensitive elements. Earlier 1D simulations (Reardon, 1981) considered the kinetically-limited dissolution of calcite and its effect on ion-exchange reactions (involving 90Sr, Ca, Na, Mg and K), and documented the spatial variation of a 90Sr partition coefficient under both transient and steady-state chemical conditions. In contrast, the simulations presented here assume local equilibrium for all reactions, and consider sorption on constant potential, rather than constant charge, surfaces. Reardon's (1981) findings documenting the spatial and temporal variability of 90Sr partitioning are reexamined and found partially caused by his assumption of a kinetically-limited reaction. In the present simulations, sorption is assumed the only retardation process controlling Pu and Np transport, and is modeled using a diffuse-double-layer-surface-complexation model. Transport simulations consider the inflow of Np- and Pu-contaminated waters into an initially uncontaminated environment, followed by the cleanup of the resultant contamination with uncontaminated water. Simulations are conducted using different spatial distributions of sorption capacities (with the same total potential sorption capacity, i.e. the same total number of sorption sites, but with different variances and spatial correlation structures). A case with a spatially uniform distribution of sorption capacities was also simulated. Results obtained differ markedly from those that would be obtained in transport simulations using constant Kd, Langmuir, or Freundlich sorption models. When possible, simulation results (breakthrough curves) are fitted to a constant Kd advection-dispersion transport model and compared to each other. Functional differences are often great enough that they prevent a meaningful fit of the simulation results with a constant Kd (or even a Langmuir or Freundlich) model, even in the case of Np, a weakly sorbed radionuclide under the simulation conditions. Functional behaviors that cannot be fitted include concentration trend reversals and radionuclide desorption spikes. Other simulation results can be successfully fitted but the fitting parameters (Kd and dispersivity) vary significantly depending on simulation conditions (e.g. infiltration vs. cleanup conditions). Notably, an increase in the variance of the specified sorption capacities results in a marked increase in the dispersion of the radionuclides, and a decrease in the fitted Kd. These results have implications for the simulation of radionuclide migration in performance assessments of nuclear waste disposal sites, for the future monitoring of those sites, and more generally for modeling contaminant transport in ground-water environments.

Glynn, P. D.

2002-12-01

389

Adequacy of Nasqan data to describe areal and temporal variability of water quality of the San Juan River Drainage basin upstream from Shiprock New Mexico  

USGS Publications Warehouse

Analyses indicate that water quality in the San Juan River drainage basin upstream from Shiprock, New Mexico, is quite variable from station to station. Analyses are based on water quality data from the U.S. Geological Survey WATSTORE files and the New Mexico Environmental Improvement Division 's files. In the northeastern part of the basin, most streams are calcium-bicarbonate waters. In the northwestern and southern part of the basin, the streams are calcium-sulfate and sodium-sulfate waters. Geology, climate, and land use and water use affect the water quality. Statistical analysis shows that streamflow, suspended-sediment, dissolved-iron, dissolved-orthophosphate-phosphorus, dissolved-sodium, dissolved-sulfate, and dissolved-manganese concentrations, specific conductance, and pH are highly variable among most stations. Dissolved-radium-226 concentration is the least variable among stations. A trend in one or more water quality constituents for the time period, October 1, 1973, through September 30, 1981, was detected at 15 out of 36 stations tested. The NASQAN stations Animas River at Farmington and San Juan River at Shiprock, New Mexico, record large volumes of flow that represent an integration of the flow from many upstream tributaries. The data collected do not represent what is occurring at specific points upstream in the basin, but do provide accurate information on how water quality is changing over time at the station location. A water quality, streamflow model would be necessary to predict accurately what is occurring simultaneously in the entire basin. (USGS)

Goetz, C. L.; Abeyta, Cynthia G.

1987-01-01

390

Assessment of soil and water contamination around an ash-disposal site: a case study from the Seyitmer coal-fired power plant in western Turkey  

Microsoft Academic Search

Seyitmer power plant comprises 4.8% of Turkey's total energy production. The fly ash produced has been deposited in the\\u000a area, since the 1960s, by a dry disposal technique. In 1997, wet disposal was improperly exercised in the area causing ash\\u000a flow over agricultural fields. This study is concerned with the chemical analysis of ash, soil and water samples collected\\u000a in

N. Gle; A. Erler

2001-01-01

391

Modeling Np and Pu transport with a surface complexation model and spatially variant sorption capacities: implications for reactive transport modeling and performance assessments of nuclear waste disposal sites  

NASA Astrophysics Data System (ADS)

One-dimensional (1D) geochemical transport modeling is used to demonstrate the effects of speciation and sorption reactions on the ground-water transport of Np and Pu, two redox-sensitive elements. Earlier 1D simulations (Reardon, 1981) considered the kinetically limited dissolution of calcite and its effect on ion-exchange reactions (involving 90Sr, Ca, Na, Mg and K), and documented the spatial variation of a 90Sr partition coefficient under both transient and steady-state chemical conditions. In contrast, the simulations presented here assume local equilibrium for all reactions, and consider sorption on constant potential, rather than constant charge, surfaces. Reardon's (1981) seminal findings on the spatial and temporal variability of partitioning (of 90Sr) are reexamined and found partially caused by his assumption of a kinetically limited reaction. In the present work, sorption is assumed the predominant retardation process controlling Pu and Np transport, and is simulated using a diffuse-double-layer-surface-complexation (DDLSC) model. Transport simulations consider the infiltration of Np- and Pu-contaminated waters into an initially uncontaminated environment, followed by the cleanup of the resultant contamination with uncontaminated water. Simulations are conducted using different spatial distributions of sorption capacities (with the same total potential sorption capacity, but with different variances and spatial correlation structures). Results obtained differ markedly from those that would be obtained in transport simulations using constant Kd, Langmuir or Freundlich sorption models. When possible, simulation results (breakthrough curves) are fitted to a constant Kd advection-dispersion transport model and compared. Functional differences often are great enough that they prevent a meaningful fit of the simulation results with a constant Kd (or even a Langmuir or Freundlich) model, even in the case of Np, a weakly sorbed radionuclide under the simulation conditions. Functional behaviors that cannot be fit include concentration trend reversals and radionuclide desorption spikes. Other simulation results are fit successfully but the fitted parameters ( Kd and dispersivity) vary significantly depending on simulation conditions (e.g. "infiltration" vs. "cleanup" conditions). Notably, an increase in the variance of the specified sorption capacities results in a marked increase in the dispersion of the radionuclides. The results presented have implications for the simulation of radionuclide migration in performance assessments of nuclear waste-disposal sites, for the future monitoring of those sites, and more generally for modeling contaminant transport in ground-water environments.

Glynn, Pierre D.

2003-04-01

392

Modeling Np and Pu transport with a surface complexation model and spatially variant sorption capacities: Implications for reactive transport modeling and performance assessments of nuclear waste disposal sites  

USGS Publications Warehouse

One-dimensional (1D) geochemical transport modeling is used to demonstrate the effects of speciation and sorption reactions on the ground-water transport of Np and Pu, two redox-sensitive elements. Earlier 1D simulations (Reardon, 1981) considered the kinetically limited dissolution of calcite and its effect on ion-exchange reactions (involving 90Sr, Ca, Na, Mg and K), and documented the spatial variation of a 90Sr partition coefficient under both transient and steady-state chemical conditions. In contrast, the simulations presented here assume local equilibrium for all reactions, and consider sorption on constant potential, rather than constant charge, surfaces. Reardon's (1981) seminal findings on the spatial and temporal variability of partitioning (of 90Sr) are reexamined and found partially caused by his assumption of a kinetically limited reaction. In the present work, sorption is assumed the predominant retardation process controlling Pu and Np transport, and is simulated using a diffuse-double-layer-surface-complexation (DDLSC) model. Transport simulations consider the infiltration of Np- and Pu-contaminated waters into an initially uncontaminated environment, followed by the cleanup of the resultant contamination with uncontaminated water. Simulations are conducted using different spatial distributions of sorption capacities (with the same total potential sorption capacity, but with different variances and spatial correlation structures). Results obtained differ markedly from those that would be obtained in transport simulations using constant Kd, Langmuir or Freundlich sorption models. When possible, simulation results (breakthrough curves) are fitted to a constant K d advection-dispersion transport model and compared. Functional differences often are great enough that they prevent a meaningful fit of the simulation results with a constant K d (or even a Langmuir or Freundlich) model, even in the case of Np, a weakly sorbed radionuclide under the simulation conditions. Functional behaviors that cannot be fit include concentration trend reversals and radionuclide desorption spikes. Other simulation results are fit successfully but the fitted parameters (Kd and dispersivity) vary significantly depending on simulation conditions (e.g. "infiltration" vs. "cleanup" conditions). Notably, an increase in the variance of the specified sorption capacities results in a marked increase in the dispersion of the radionuclides. The results presented have implications for the simulation of radionuclide migration in performance assessments of nuclear waste-disposal sites, for the future monitoring of those sites, and more generally for modeling contaminant transport in ground-water environments. ?? 2003 Published by Elsevier Science Ltd.

Glynn, P. D.

2003-01-01

393

Hospital waste disposal by incineration.  

PubMed

Hospital waste is becoming increasingly complex due to changing technologies and increase in the services that the hospitals perform for the community. Out of the available technology for the final disposal of solid wastes, incineration is best suited for hospital waste as it renders the waste nontoxic, non hazardous, non putrescible and reduces the volume of material for ultimate disposal. Present study was carried out in a service hospital to analyze the requirement of incinerator considering the state of art available in this country. Multi chambered oil fired incinerator installation as an on site facility for hospital solid waste disposal has been recommended as more environment. friendly option. PMID:10537997

Rao, S K; Garg, R K

1994-07-01

394

The Necessity of Geologic Disposal  

SciTech Connect

Nuclear wastes are the radioactive byproducts of nuclear power generation, nuclear weapons production, and other uses of nuclear material. Experts from around the world agree that deep geologic disposal of nuclear waste in a mined repository is the most environmentally sound means of removing these potential sources of radiation from interaction with the biosphere. Of the 360 millirem of background radiation received annually by the average American, from both natural and man-made sources, less than 1 millirem results from the nuclear fuel cycle. Spent nuclear fuel and high-level radioactive waste, destined for geologic disposal, are located at 126 sites in 39 states. The proposed repository site at Yucca Mountain, Nevada, is far more isolated from the general population than any sites where these radioactive materials are presently located. Only solid forms of high-level wastes will be transported for disposal in a geologic repository. For more than 50 years, nuclear materials have been safely transported in North America, Europe, and Asia, without a single significant radiation release. Since the 1950s, select panels from the National Academy of Sciences-National Research Council and interagency advisory groups, and international experts selected by the OECD/Nuclear Energy Agency, have examined the environmental, ethical, and intergenerational aspects of nuclear waste disposal, plus alternatives to geologic disposal. All have concluded that deep geologic disposal in a mined repository is clearly the preferred option. The concept of deep geologic disposal is based on the analogy to ore deposits, which are formed deep within the Earth's crust, commonly remain isolated from the biosphere for millions to billions of years, and are, generally, extremely difficult to detect. Before selecting the unsaturated tuffs at Yucca Mountain, DOE evaluated salt formations, basalts, and both crystalline and sedimentary rocks. Other nations generating nuclear power also plan to use deep geologic disposal, and are evaluating sites in granites, argillaceous rocks, and salt formations.

R. Linden

2004-07-01

395

Corrective Action Decision Document/Closure Report for Corrective Action Unit 561: Waste Disposal Areas, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect

CAU 561 comprises 10 CASs: (1) 01-19-01, Waste Dump; (2) 02-08-02, Waste Dump and Burn Area; (3) 03-19-02, Debris Pile; (4) 05-62-01, Radioactive Gravel Pile; (5) 12-23-09, Radioactive Waste Dump; (6) 22-19-06, Buried Waste Disposal Site; (7) 23-21-04, Waste Disposal Trenches ; (8) 25-08-02, Waste Dump; (9) 25-23-21, Radioactive Waste Dump; and (10) 25-25-19, Hydrocarbon Stains and Trench. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation for closure of CAU 561 with no further corrective action. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process: (1) Determine whether COCs are present; (2) If COCs are present, determine their nature and extent; and (3) Provide sufficient information and data to complete appropriate corrective actions. The following contaminants were determined to be present at concentrations exceeding their corresponding FALs: (1) No contamination exceeding FALs was identified at CASs 01-19-01, 03-19-02, 05-62-01, 12-23-09, and 22-19-06. (2) The surface and subsurface soil within the burn area at CAS 02-08-02 contains arsenic and lead above the FALs of 23 milligrams per kilogram (mg/kg) and 800 mg/kg, respectively. The surface and subsurface soil within the burn area also contains melted lead slag (potential source material [PSM]). The soil within the waste piles contains polyaromatic hydrocarbons (PAHs) above the FALs. The contamination within the burn area is spread throughout the area, as it was not feasible to remove all the PSM (melted lead), while at the waste piles, the contamination is confined to the piles. (3) The surface and subsurface soils within Trenches 3 and 5 at CAS 23-21-04 contain arsenic and polychlorinated biphenyls (PCBs) above the FALs of 23 mg/kg and 0.74 mg/kg, respectively. The soil was removed from both trenches, and the soil that remains at this CAS does not contain contamination exceeding the FALs. Lead bricks and counterweights were also removed, and the soil below these items does not contain contamination that exceeds the FAL for lead. (4) The concrete-like material at CAS 25-08-02 contains arsenic above the FAL of 23 mg/kg. This concrete-like material was removed, and the soil that remains at this CAS does not contain contamination exceeding the FALs. Lead-acid batteries were also removed, and the soil below the batteries does not contain contamination that exceeds the FAL for lead. (5) The surface soils within the main waste dump at the posted southern radioactive material area (RMA) at CAS 25-23-21 contain cesium (Cs)-137 and PCBs above the FALs of 72.9 picocuries per gram (pCi/g) and 0.74 mg/kg, respectively. The soil was removed from the RMA, and the soil that remains at this CAS does not contain contamination exceeding the FALs. (6) The surface and subsurface soils at CAS 25-25-19 do not contain contamination exceeding the FALs. In addition, lead bricks were removed, and the soil below these items does not contain contamination that exceeds the FAL for lead. The following best management practices were implemented: (1) Housekeeping debris at CASs 02-08-02, 23-21-04, 25-08-02, 25-23-21, and 25-25-19 was removed and disposed of; (2) The open trenches at CAS 23-21-04 were backfilled; (3) The waste piles at CAS 25-08-02 were removed and the area leveled to ground surface; and (4) The remaining waste piles at the main waste dump at CAS 25-23-21 were leveled to ground surface. Therefore, NNSA/NSO provides the following recommendations: (1) No further action for CASs 01-19-01, 03-19-02, 05-62-01, 12-23-09, and 22-19-06; (2) Closure in place with an FFACO use restriction (UR) at CAS 02-08-02 for the remaining PAH-, arsenic-, and lead-contaminated soil, and the melted lead PSM. The UR form and map have been filed in the NNSA/NSO Facility Information Management System, the FFACO database, and the NNSA/NSO CAU/CAS files; (3) No further corrective action at CAS 23-21-04, as the lead bricks and counterweights (PSM) have been removed, and the COCs of arsenic and PCBs in soil have be

Mark Krauss

2011-08-01

396

Landfill disposal systems  

PubMed Central

The current status of landfill disposal of hazardous wastes in the United States is indicated by presenting descriptions of six operating landfills. These landfills illustrate the variety of techniques that exist in landfill disposal of hazardous wastes. Although some landfills more effectively isolate hazardous waste than others, all landfills must deal with the following problems. Leachate from hazardous waste landfills is generally highly polluted. Most landfills attempt to contain leachate at the site and prevent its discharge to surface or groundwaters. To retain leachate within a disposal area, subsurface barriers of materials such as concrete, asphalt, butyl rubber, vinyl, and clay are used. It is difficult to assure that these materials can seal a landfill indefinitely. When a subsurface barrier fails, the leachate enters the groundwater in a concentrated, narrow band which may bypass monitoring wells. Once a subsurface barrier has failed, repairs are time-consuming and costly, since the waste above the repair site may have to be removed. The central problem in landfill disposal is leachate control. Recent emphasis has been on developing subsurface barriers to contain the wastes and any leachate. Future emphasis should also be on techniques for removing water from hazardous wastes before they are placed in landfills, and on methods for preventing contact of the wastes with water during and after disposal operations. When leachate is eliminated, the problems of monitoring, and subsurface barrier failure and repair can be addressed, and a waste can be effectively isolated. A surface seal landfill design is recommended for maintaining the dry state of solid hazardous wastes and for controlling leachate. Any impervious liner is utilized over the top of the landfill to prevent surface water from seeping into the waste. The surface barrier is also the site where monitoring and maintenance activities are focused. Barrier failure can be detected by visual inspections and any repairs can be made without disturbing the waste. The surface seal landfill does not employ a subsurface barrier. The surface seal landfill successfully addresses each of the four environmental problems listed above, provided that this landfill design is utilized for dry wastes only and is located at a site which provides protection from groundwater and temporary perched water tables. ImagesFIGURE 3.FIGURE 4.FIGURE 7.FIGURE 7.

Slimak, Karen M.

1978-01-01

397

Real-time 4D ERT monitoring of river water intrusion into a former nuclear disposal site using a transient warping-mesh water table boundary (Invited)  

NASA Astrophysics Data System (ADS)

The Hanford 300 Area, located adjacent to the Columbia River in south-central Washington, USA, is the site of former research and uranium fuel rod fabrication facilities. Waste disposal practices at site included discharging between 33 and 59 metric tons of uranium over a 40 year period into shallow infiltration galleries, resulting in persistent uranium contamination within the vadose and saturated zones. Uranium transport from the vadose zone to the saturated zone is intimately linked with water table fluctuations and river water intrusion driven by upstream dam operations. As river stage increases, the water table rises into the vadose zone and mobilizes contaminated pore water. At the same time, river water moves inland into the aquifer, and river water chemistry facilitates further mobilization by enabling uranium desorption from contaminated sediments. As river stage decreases, flow moves toward the river, ultimately discharging contaminated water at the river bed. River water specific conductance at the 300 Area varies around 0.018 S/m whereas groundwater specific conductance varies around 0.043 S/m. This contrast provides the opportunity to monitor groundwater/river water interaction by imaging changes in bulk conductivity within the saturated zone using time-lapse electrical resistivity tomography. Previous efforts have demonstrated this capability, but have also shown that disconnecting regularization constraints at the water table is critical for obtaining meaningful time-lapse images. Because the water table moves with time, the regularization constraints must also be transient to accommodate the water table boundary. This was previously accomplished with 2D time-lapse ERT imaging by using a finely discretized computational mesh within the water table interval, enabling a relatively smooth water table to be defined without modifying the mesh. However, in 3D this approach requires a computational mesh with an untenable number of elements. In order to accommodate the water table boundary in 3D, we propose a time-lapse warping mesh inversion, whereby mesh elements that traverse the water table are modified to generate a smooth boundary at the known water table position, enabling regularization constraints to be accurately disconnected across the water table boundary at a given time. We demonstrate the approach using a surface ERT array installed adjacent to the Columbia River at the 300 Area, consisting of 352 electrodes and covering an area of approximately 350 m x 350 m. Using autonomous data collection, transmission, and filtering tools coupled with high performance computing resources, the 4D imaging process is automated and executed in real time. Each time lapse survey consists of approximately 40,000 measurements and 4 surveys are collected and processed per day from April 1st , 2013 to September 30th, 2013. The data are inverted on an unstructured tetrahedral mesh that honors LiDAR-based surface topography and is comprised of approximately 905,000 elements. Imaging results show the dynamic 4D extent of river water intrusion, and are validated with well-based fluid conductivity measurements at each monitoring well within the imaging domain.

Johnson, T.; Hammond, G. E.; Versteeg, R. J.; Zachara, J. M.

2013-12-01

398

Low-level-waste-disposal methodologies  

Microsoft Academic Search

This report covers the following: (1) history of low level waste disposal; (2) current practice at the five major DOE burial sites and six commercial sites with dominant features of these sites and radionuclide content of major waste types summarized in tables; (3) site performance with performance record on burial sites tabulated; and (4) proposed solutions. Shallow burial of low

M. L. Wheeler; K. Dragonette

1981-01-01

399

Options and cost for disposal of NORM waste  

Microsoft Academic Search

Oil field waste containing naturally occurring radioactive material (NORM) is presently disposed of both on the lease site and at off-site commercial disposal facilities. The majority of NORM waste is disposed of through underground injection, most of which presently takes place at a commercial injection facility located in eastern Texas. Several companies offer the service of coming to an operator's

Veil

1998-01-01

400

Movement of a tritium plume in shallow groundwater at a legacy low-level radioactive waste disposal site in eastern Australia.  

PubMed

Between 1960 and 1968 low-level radioactive waste was buried in a series of shallow trenches near the Lucas Heights facility, south of Sydney, Australia. Groundwater monitoring carried out since the mid 1970s indicates that with the exception of tritium, no radioactivity above typical background levels has been detected outside the immediate vicinity of the trenches. The maximum tritium level detected in ground water was 390 kBq/L and the median value was 5400 Bq/L, decay corrected to the time of disposal. Since 1968, a plume of tritiated water has migrated from the disposal trenches and extends at least 100 m from the source area. Tritium in rainfall is negligible, however leachate from an adjacent and fill represents a significant additional tritium source. Study data indicate variation in concentration levels and plume distribution in response to wet and dry climatic periods and have been used to determine pathways for tritium migration through the subsurface. PMID:20573429

Hughes, C E; Cendn, D I; Harrison, J J; Hankin, S I; Johansen, M P; Payne, T E; Vine, M; Collins, R N; Hoffmann, E L; Loosz, T

2011-10-01

401

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

Microsoft Academic Search

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

D. E. Prudic; A. D. Randall

1977-01-01

402

Carbon Isotopes in Unsaturated-Zone Gases and Ground Water Near a Radioactive-Waste Disposal Area, Amargosa Desert Research Site, Nye County, Nevada  

Microsoft Academic Search

To test hypotheses about radionuclide distribution and transport, vertical profiles of 14C in carbon dioxide were determined on gas samples from a 110-m deep unsaturated zone 32, 100, and 3,000 m from a low-level radioactive-waste disposal area. A direct-scintillation-counting method for radiocarbon was developed that minimized sample handling and compared favorably with the more labor-intensive benzene-synthesis method. Values of delta

D. A. Stonestrom; R. L. Michel; W. C. Evans; T. R. Smith; D. E. Prudic; R. G. Striegl; H. Haas; F. J. Brockman; B. J. Andraski

2001-01-01

403