Science, Society, and America's Nuclear Waste: Nuclear Waste, Unit 1. Teacher Guide. Second Edition.

Science.gov (United States)

Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

This guide is Unit 1 of the four-part series Science, Society, and America's Nuclear Waste produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to help students establish the relevance of the topic of nuclear waste to their everyday lives and activities. Particular attention is…

Science, society, and America's nuclear waste: Unit 4, The waste management system

International Nuclear Information System (INIS)

1992-01-01

This is the teachers guide to unit 4, (The Waste Management System), of a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

Plutonium Finishing Plant (PFP) Treatment and Storage Unit Waste Analysis Plan

International Nuclear Information System (INIS)

PRIGNANO, A.L.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Plutonium Finishing Plant Treatment and Storage Unit (PFP Treatment and Storage Unit) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (4)(a) and (5). The PFP Treatment and Storage Unit is an interim status container management unit for plutonium bearing mixed waste radiologically managed as transuranic (TRU) waste. TRU mixed (TRUM) waste managed at the PFP Treatment and Storage Unit is destined for the Waste Isolation Pilot Plant (WIPP) and therefore is not subject to land disposal restrictions [WAC 173-303-140 and 40 CFR 268]. The PFP Treatment and Storage Unit is located in the 200 West Area of the Hanford Facility, Richland Washington (Figure 1). Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

Science, Society, and America's Nuclear Waste: The Nuclear Waste Policy Act, Unit 3. Teacher Guide. Second Edition.

Science.gov (United States)

Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

This guide is Unit 3 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to identify the key elements of the United States' nuclear waste dilemma and introduce the Nuclear Waste Policy Act and the role of the…

Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

International Nuclear Information System (INIS)

1992-01-01

This is the 3rd unit, (The Nuclear Waste Policy Act) a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

Review, mapping and analysis of the agricultural plastic waste generation and consolidation in Europe.

Science.gov (United States)

Briassoulis, Demetres; Babou, Epifania; Hiskakis, Miltiadis; Scarascia, Giacomo; Picuno, Pietro; Guarde, Dorleta; Dejean, Cyril

2013-12-01

A review of agricultural plastic waste generation and consolidation in Europe is presented. A detailed geographical mapping of the agricultural plastic use and waste generation in Europe was conducted focusing on areas of high concentration of agricultural plastics. Quantitative data and analysis of the agricultural plastic waste generation by category, geographical distribution and compositional range, and physical characteristics of the agricultural plastic waste per use and the temporal distribution of the waste generation are presented. Data were collected and cross-checked from a variety of sources, including European, national and regional services and organizations, local agronomists, retailers and farmers, importers and converters. Missing data were estimated indirectly based on the recorded cultivated areas and the characteristics of the agricultural plastics commonly used in the particular regions. The temporal distribution, the composition and physical characteristics of the agricultural plastic waste streams were mapped by category and by application. This study represents the first systematic effort to map and analyse agricultural plastic waste generation and consolidation in Europe.

United Kingdom government policy towards radioactive waste

International Nuclear Information System (INIS)

Pritchard, G.

1986-01-01

There are three areas of radioactive waste management which exemplify, beyond any reasonable doubt, that the United Kingdom has in the past (and intends in the future), to pursue a policy of dispersal and disposal of radioactive wastes: These are: (I) dumping of low-level waste in the deep ocean and, on a parallel, seabed emplacement of highly active waste; (II) the liquid discharges from Windscale into the Irish Sea; and (III) land dumping of low- and intermediate-level waste

Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

International Nuclear Information System (INIS)

1992-01-01

This teachers guide is unit 3, the nuclear waste policy act, in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear power plants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

40 CFR 258.16 - Closure of existing municipal solid waste landfill units.

Science.gov (United States)

2010-07-01

... waste landfill units. 258.16 Section 258.16 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES CRITERIA FOR MUNICIPAL SOLID WASTE LANDFILLS Location Restrictions § 258.16 Closure of existing municipal solid waste landfill units. (a) Existing MSWLF units that cannot make the...

Waste To Biogas Mapping Tool | Pacific Southwest, Region 9 ...

Science.gov (United States)

2018-04-10

Interactive map (California, Arizona, Hawaii, Nevada) showing the location and contact information to connect organic waste producers and potential users. Add your business, ensure your information is correct.

Geologic mapping of the air intake shaft at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Holt, R.M.; Powers, D.W.

1990-12-01

The air intake shaft (AS) was geologically mapped from the surface to the Waste Isolation Pilot Plant (WIPP) facility horizon. The entire shaft section including the Mescalero Caliche, Gatuna Formation, Santa Rosa Formation, Dewey Lake Redbeds, Rustler Formation, and Salado Formation was geologically described. The air intake shaft (AS) at the Waste Isolation Pilot Plant (WIPP) site was constructed to provide a pathway for fresh air into the underground repository and maintain the desired pressure balances for proper underground ventilation. It was up-reamed to minimize construction-related damage to the wall rock. The upper portion of the shaft was lined with slip-formed concrete, while the lower part of the shaft, from approximately 903 ft below top of concrete at the surface, was unlined. As part of WIPP site characterization activities, the AS was geologically mapped. The shaft construction method, up-reaming, created a nearly ideal surface for geologic description. Small-scale textures usually best seen on slabbed core were easily distinguished on the shaft wall, while larger scale textures not generally revealed in core were well displayed. During the mapping, newly recognized textures were interpreted in order to refine depositional and post-depositional models of the units mapped. The objectives of the geologic mapping were to: (1) provide confirmation and documentation of strata overlying the WIPP facility horizon; (2) provide detailed information of the geologic conditions in strata critical to repository sealing and operations; (3) provide technical basis for field adjustments and modification of key and aquifer seal design, based upon the observed geology; (4) provide geological data for the selection of instrument borehole locations; (5) and characterize the geology at geomechanical instrument locations to assist in data interpretation. 40 refs., 27 figs., 1 tab

The 1986 United Kingdom radioactive waste inventory

International Nuclear Information System (INIS)

Shepherd, J.; Harrison, J.; McNicholas, P.

1987-11-01

This report gives information on the radioactive wastes which arise in the United Kingdom, updated to 1 January 1986. It has been compiled from information provided by the principal producers of the wastes, Amersham International plc, British Nuclear Fuels plc, the Central Electricity Generating Board, the South of Scotland Electricity Board, and the United Kingdom Atomic Energy Authority. The report lists the waste types, or streams, which these organisations produce, or will produce, as part of their normal operations or from decommissioning of their plant. For each stream is given the volume (or in a few cases mass) of existing stocks, estimated arisings to the year 2030 (2080 in the case of some decommissioning wastes), specific activity, and conditioning factor (volume change from ''raw'' waste volume to volume conditioned for disposal). Details of the radionuclide compositions of individual waste streams are separately listed. Waste streams are allocated to one of the three categories High, Intermediate or Low-Level, although this does not necessarily imply any commitment to a particular disposal route. The report includes tables summarising the data, arranged in a hierarchical manner to enable totals to be readily extracted as required. Summary tables of both ''raw'' and ''conditioned'' waste volumes are given. Also included are a commentary on the data and important changes from the 1985 inventory, and information on scenarios on which estimates of future arisings are based. (author)

40 CFR 60.1015 - What is a new municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... combustion unit? 60.1015 Section 60.1015 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... for Small Municipal Waste Combustion Units for Which Construction is Commenced After August 30, 1999... What is a new municipal waste combustion unit? (a) A new municipal waste combustion unit is a municipal...

Waste management regroups units into Rust International

International Nuclear Information System (INIS)

Kirschner, E.

1992-01-01

Three Waste Management (Oak Brook, IL) subsidiaries have proposed merging units from Chemical Waste Management (CWM) and Wheelabrator Technologies with the Brand Companies (Park Ridge, IL). Waste Management says the new company, to be called Rust International, will become one of the US's largest environmental consulting and infrastructure organizations and will include design and construction services. Waste Management expects the merged company's 1993 revenues to reach $1.8 billion. It will be based in Birmingham, AL and have 12,000 employees

Geomorphic Unit Tool (GUT): Applications of Fluvial Mapping

Science.gov (United States)

Kramer, N.; Bangen, S. G.; Wheaton, J. M.; Bouwes, N.; Wall, E.; Saunders, C.; Bennett, S.; Fortney, S.

2017-12-01

Geomorphic units are the building blocks of rivers and represent distinct habitat patches for many fluvial organisms. We present the Geomorphic Unit Toolkit (GUT), a flexible GIS geomorphic unit mapping tool, to generate maps of fluvial landforms from topography. GUT applies attributes to landforms based on flow stage (Tier 1), topographic signatures (Tier 2), geomorphic characteristics (Tier 3) and patch characteristics (Tier 4) to derive attributed maps at the level of detail required by analysts. We hypothesize that if more rigorous and consistent geomorphic mapping is conducted, better correlations between physical habitat units and ecohydraulic model results will be obtained compared to past work. Using output from GUT for coarse bed tributary streams in the Columbia River Basin, we explore relationships between salmonid habitat and geomorphic spatial metrics. We also highlight case studies of how GUT can be used to showcase geomorphic impact from large wood restoration efforts. Provided high resolution topography exists, this tool can be used to quickly assess changes in fluvial geomorphology in watersheds impacted by human activities.

United States steps up waste isolation programme

Energy Technology Data Exchange (ETDEWEB)

Smedes, H W [Department of Energy, Germantown, MD (USA). Office of Waste Isolation; Carbiener, W A [Battelle Columbus Labs., OH (USA)

1982-11-01

A description is given of the United States' waste isolation programme which now involves tests of specific sites. The US Department of Energy plans to build a system of mined geological repositories for the disposal of commercially generated high-level and transuranic radioactive waste. It is hoped that the first repository will be available by 1998. Studies of the geology and hydrology of the proposed sites, the waste packaging and the repository design are reported.

Low-level radioactive waste disposal technologies used outside the United States

International Nuclear Information System (INIS)

Templeton, K.J.; Mitchell, S.J.; Molton, P.M.; Leigh, I.W.

1994-01-01

Low-level radioactive waste (LLW) disposal technologies are an integral part of the waste management process. In the United States, commercial LLW disposal is the responsibility of the State or groups of States (compact regions). The United States defines LLW as all radioactive waste that is not classified as spent nuclear fuel, high- level radioactive waste, transuranic waste, or by-product material as defined in Section II(e)(2) of the Atomic Energy Act. LLW may contain some long-lived components in very low concentrations. Countries outside the United States, however, may define LLW differently and may use different disposal technologies. This paper outlines the LLW disposal technologies that are planned or being used in Canada, China, Finland, France, Germany, Japan, Sweden, Taiwan, and the United Kingdom (UK)

Radioactive waste management in the United Kingdom

International Nuclear Information System (INIS)

Hill, J.

1976-01-01

The principles to be followed in the processing and disposal of radioactive wastes are summarized and the procedures practiced in the United Kingdom for different types of wastes are reviewed to illustrate how these principles are being observed. The objectives for the future in modification of current practices are discussed

Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

International Nuclear Information System (INIS)

1997-07-01

This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization

Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization.

Evaluation of a TRU fundamental criterion and reference TRU waste units

International Nuclear Information System (INIS)

Klett, R.

1993-01-01

The comparison of two options for regulating transuranic (TRU) waste disposal is explained in this paper. The two options are (1) fundamental and derived standards developed specifically for the TRU waste and (2) a family of procedures that use a reference to the TRU waste unit with procedures that use a reference to the TRU waste unit with commercial high-level waste (HLW) criteria. Background information pertaining to both options is covered. A section on criteria specifically for TRUE waste suggests a methodology for developing or adapting fundamental and derived criteria that are consistent with all other aspects of the standards. The section on references TRU waste units covers all the parameter variations that have been suggested for this option. The technical bases of each approach is reviewed, implementation is discussed and their relative attributes and deficiencies are evaluated

Preliminary Correlation Map of Geomorphic Surfaces in North-Central Frenchman Flat, Nevada Test Site

International Nuclear Information System (INIS)

Bechtel Nevada

2005-01-01

This correlation map (scale = 1:12,000) presents the results of a mapping initiative that was part of the comprehensive site characterization required to operate the Area 5 Radioactive Waste Management Site, a low-level radioactive waste disposal facility located in northern Frenchman Flat at the Nevada Test Site. Eight primary map units are recognized for Quaternary surfaces: remnants of six alluvial fan or terrace surfaces, one unit that includes colluvial aprons associated with hill slopes, and one unit for anthropogenically disturbed surfaces. This surficial geology map provides fundamental data on natural processes for reconstruction of the Quaternary history of northern Frenchman Flat, which in turn will aid in the understanding of the natural processes that act to develop the landscape, and the time-frames involved in landscape development. The mapping was conducted using color and color-infrared aerial photographs and field verification of map unit composition and boundaries. Criteria for defining the map unit composition of geomorphic surface units are based on relative geomorphic position, landform morphology, and degree of preservation of surface morphology. The bedrock units identified on this map were derived from previous published mapping efforts and are included for completeness

Transuranic waste transportation issues in the United States

International Nuclear Information System (INIS)

Channell, J.K.; Rodgers, J.C.; Neill, R.H.

1988-01-01

The United States Department of Energy (DOE) expects to begin disposal of defence transuranic wastes at the Waste Isolation Pilot Plant (WIPP) in Southeastern New Mexico before the end of 1988. Approximately 25,000 truck shipments involving 35 million vehicle kilometers will be required to transport about 175,000 m 3 of contact-handled transuranic waste. Up to 5,000 shipments of remote-handled transuranic waste (RH-TRU) will also be shipped to WIPP in shielded casks. This paper addresses the shipment of CH-TRU wastes

WTP Waste Feed Qualification: Glass Fabrication Unit Operation Testing Report

Energy Technology Data Exchange (ETDEWEB)

Stone, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Hanford Missions Programs; Newell, J. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Process Technology Programs; Johnson, F. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development; Edwards, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development

2016-07-14

The waste feed qualification program is being developed to protect the Hanford Tank Waste Treatment and Immobilization Plant (WTP) design, safety basis, and technical basis by assuring waste acceptance requirements are met for each staged waste feed campaign prior to transfer from the Tank Operations Contractor to the feed receipt vessels inside the Pretreatment Facility. The Waste Feed Qualification Program Plan describes the three components of waste feed qualification: 1. Demonstrate compliance with the waste acceptance criteria 2. Determine waste processability 3. Test unit operations at laboratory scale. The glass fabrication unit operation is the final step in the process demonstration portion of the waste feed qualification process. This unit operation generally consists of combining each of the waste feed streams (high-level waste (HLW) and low-activity waste (LAW)) with Glass Forming Chemicals (GFCs), fabricating glass coupons, performing chemical composition analysis before and after glass fabrication, measuring hydrogen generation rate either before or after glass former addition, measuring rheological properties before and after glass former addition, and visual observation of the resulting glass coupons. Critical aspects of this unit operation are mixing and sampling of the waste and melter feeds to ensure representative samples are obtained as well as ensuring the fabrication process for the glass coupon is adequate. Testing was performed using a range of simulants (LAW and HLW simulants), and these simulants were mixed with high and low bounding amounts of GFCs to evaluate the mixing, sampling, and glass preparation steps in shielded cells using laboratory techniques. The tests were performed with off-the-shelf equipment at the Savannah River National Laboratory (SRNL) that is similar to equipment used in the SRNL work during qualification of waste feed for the Defense Waste Processing Facility (DWPF) and other waste treatment facilities at the

Analysis of car shredder polymer waste with Raman mapping and chemometrics

Directory of Open Access Journals (Sweden)

B. Vajna

2012-02-01

Full Text Available A novel evaluation method was developed for Raman microscopic quantitative characterization of polymer waste. Car shredder polymer waste was divided into different density fractions by magnetic density separation (MDS technique, and each fraction was investigated by Raman mapping, which is capable of detecting the components being present even in low concentration. The only method available for evaluation of the mapping results was earlier to assign each pixel to a component visually and to count the number of different polymers on the Raman map. An automated method is proposed here for pixel classification, which helps to detect the different polymers present and enables rapid assignment of each pixel to the appropriate polymer. Six chemometric methods were tested to provide a basis for the pixel classification, among which multivariate curve resolution-alternating least squares (MCR-ALS provided the best results. The MCR-ALS based pixel identification method was then used for the quantitative characterization of each waste density fraction, where it was found that the automated method yields accurate results in a very short time, as opposed to manual pixel counting method which may take hours of human work per dataset.

Radioactive waste management in the United States

International Nuclear Information System (INIS)

Smiley, J.L.

1985-01-01

In the United States, efforts to dispose of the nation's high- and low-level radioactive wastes are based on somewhat different approaches.The individual States are responsible for disposing of low-level wastes with the Federal Government providing technical and financial support to help the States in the early phases of their efforts. The Federal Government has responsibility for developing facilities for the disposal of high-level waste. However, both efforts show a common need to meet national objectives while satisfying the concerns of the public. (author)

40 CFR 60.1010 - Does this subpart apply to my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... waste combustion unit? 60.1010 Section 60.1010 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY... Performance for Small Municipal Waste Combustion Units for Which Construction is Commenced After August 30....1010 Does this subpart apply to my municipal waste combustion unit? Yes, if your municipal waste...

3-D Mapping Technologies For High Level Waste Tanks

International Nuclear Information System (INIS)

Marzolf, A.; Folsom, M.

2010-01-01

This research investigated four techniques that could be applicable for mapping of solids remaining in radioactive waste tanks at the Savannah River Site: stereo vision, LIDAR, flash LIDAR, and Structure from Motion (SfM). Stereo vision is the least appropriate technique for the solids mapping application. Although the equipment cost is low and repackaging would be fairly simple, the algorithms to create a 3D image from stereo vision would require significant further development and may not even be applicable since stereo vision works by finding disparity in feature point locations from the images taken by the cameras. When minimal variation in visual texture exists for an area of interest, it becomes difficult for the software to detect correspondences for that object. SfM appears to be appropriate for solids mapping in waste tanks. However, equipment development would be required for positioning and movement of the camera in the tank space to enable capturing a sequence of images of the scene. Since SfM requires the identification of distinctive features and associates those features to their corresponding instantiations in the other image frames, mockup testing would be required to determine the applicability of SfM technology for mapping of waste in tanks. There may be too few features to track between image frame sequences to employ the SfM technology since uniform appearance may exist when viewing the remaining solids in the interior of the waste tanks. Although scanning LIDAR appears to be an adequate solution, the expense of the equipment ($80,000-$120,000) and the need for further development to allow tank deployment may prohibit utilizing this technology. The development would include repackaging of equipment to permit deployment through the 4-inch access ports and to keep the equipment relatively uncontaminated to allow use in additional tanks. 3D flash LIDAR has a number of advantages over stereo vision, scanning LIDAR, and SfM, including full frame

Assessment of microwave-based clinical waste decontamination unit.

Science.gov (United States)

Hoffman, P N; Hanley, M J

1994-12-01

A clinical waste decontamination unit that used microwave-generated heat was assessed for operator safety and efficacy. Tests with loads artificially contaminated with aerosol-forming particles showed that no particles were detected outside the machine provided the seals and covers were correctly seated. Thermometric measurement of a self-generated steam decontamination cycle was used to determine the parameters needed to ensure heat disinfection of the waste reception hopper, prior to entry for maintenance or repair. Bacterial and thermometric test pieces were passed through the machine within a full load of clinical waste. These test pieces, designed to represent a worst case situation, were enclosed in aluminium foil to shield them from direct microwave energy. None of the 100 bacterial test pieces yielded growth on culture and all 100 thermal test pieces achieved temperatures in excess of 99 degrees C during their passage through the decontamination unit. It was concluded that this method may be used to render safe the bulk of of ward-generated clinical waste.

Quaternary geologic map of the Austin 4° x 6° quadrangle, United States

Science.gov (United States)

State compilations by Moore, David W.; Wermund, E.G.; edited and integrated by Moore, David W.; Richmond, Gerald Martin; Christiansen, Ann Coe; Bush, Charles A.

1993-01-01

This map is part of the Quaternary Geologic Atlas of the United States (I-1420). It was first published as a printed edition in 1993. The geologic data have now been captured digitally and are presented here along with images of the printed map sheet and component parts as PDF files. The Quaternary Geologic Map of the Austin 4° x 6° Quadrangle was mapped as part of the Quaternary Geologic Atlas of the United States. The atlas was begun as an effort to depict the areal distribution of surficial geologic deposits and other materials that accumulated or formed during the past 2+ million years, the period that includes all activities of the human species. These materials are at the surface of the Earth. They make up the ground on which we walk, the dirt in which we dig foundations, and the soil in which we grow crops. Most of our human activity is related in one way or another to these surface materials that are referred to collectively by many geologists as regolith, the mantle of fragmental and generally unconsolidated material that overlies the bedrock foundation of the continent. The maps were compiled at 1:1,000,000 scale. In recent years, surficial deposits and materials have become the focus of much interest by scientists, environmentalists, governmental agencies, and the general public. They are the foundations of ecosystems, the materials that support plant growth and animal habitat, and the materials through which travels much of the water required for our agriculture, our industry, and our general well being. They also are materials that easily can become contaminated by pesticides, fertilizers, and toxic wastes. In this context, the value of the surficial geologic map is evident.

MAPPING A BASIC HEALTH UNIT: AN EXPERIENCE REPORT

Directory of Open Access Journals (Sweden)

Bárbara Carvalho Malheiros

2015-01-01

Full Text Available Backgound and Objectives: This study is an experience report on the construction of a map of a Basic Health Unit (BHU. The objective was to understand the relevance and/or importance of mapping a BHU and acquire more knowledge on the health-disease status of the registered population and identify the importance of cartography as a working tool. Case description: After reading some texts, evaluating information systems and on-site visits, it was possible to identify the health status of the population of the neighborhoods. The proposed objectives were considered to be achieved, considering the mapping of the assessed population’s health-disease situation with a closer-to-reality viewpoint, identifying the number of individuals, the diseases, living situation and health care. Conclusion: The mapping approach is a powerful working tool for allowing the planning of strategic interventions that enables the development of assistance activities, aiming to promote health and disease prevention. KEYWORDS: Mapping; Basic Health Unit; Health Planning.

Science, Society, and America's Nuclear Waste: The Waste Management System, Unit 4. Teacher Guide. Second Edition.

Science.gov (United States)

Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

This guide is Unit 4 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office Civilian Radioactive Waste Management. The goal of this unit is to explain how transportation, a geologic repository, and the multi-purpose canister will work together to provide short-term and long-term…

Remote Sensing Analysis Techniques and Sensor Requirements to Support the Mapping of Illegal Domestic Waste Disposal Sites in Queensland, Australia

Directory of Open Access Journals (Sweden)

Katharine Glanville

2015-10-01

Full Text Available Illegal disposal of waste is a significant management issue for contemporary governments with waste posing an economic, social, and environmental risk. An improved understanding of the distribution of illegal waste disposal sites is critical to enhance the cost-effectiveness and efficiency of waste management efforts. Remotely sensed data has the potential to address this knowledge gap. However, the literature regarding the use of remote sensing to map illegal waste disposal sites is incomplete. This paper aims to analyze existing remote sensing methods and sensors used to monitor and map illegal waste disposal sites. The purpose of this paper is to support the evaluation of existing remote sensing methods for mapping illegal domestic waste sites in Queensland, Australia. Recent advances in technology and the acquisition of very high-resolution remote sensing imagery provide an important opportunity to (1 revisit established analysis techniques for identifying illegal waste disposal sites, (2 examine the applicability of different remote sensors for illegal waste disposal detection, and (3 identify opportunities for future research to increase the accuracy of any illegal waste disposal mapping products.

The juridic control of transboundary shipments of hazardous waste in the United States

International Nuclear Information System (INIS)

Juergensmeyer, J.C.

1989-01-01

An intergovernmental conflict over location of disposal of hazardous waste is discussed; the several definitions of hazardous waste in the United States are analysed; moreover the American Law Regulating the transport and disposal of hazardous waste as well is put in question; also the restrictions an disposal of waste are examined in light of the Constitution of the United States, finally, transboundary shipments of hazardous waste and international agreements on hazardous waste shipment are considered [pt

USGS Governmental Unit Boundaries Overlay Map Service from The National Map

Data.gov (United States)

U.S. Geological Survey, Department of the Interior — The USGS Governmental Unit Boundaries service from The National Map (TNM) represents major civil areas for the Nation, including States or Territories, counties (or...

The 1987 United Kingdom radioactive waste inventory

International Nuclear Information System (INIS)

1988-10-01

This report describes the stocks of radioactive wastes in the United Kingdom, together with projections of future arisings. Operational and decommissioning wastes are considered for both committed and prospective plant. Arisings are from power reactors, commercial reprocessing, fuel manufacture, medical and industrial sources and research and development. Data are presented for the wastes in their raw form and as conditioned for disposal. The data which refer to the situation on 1.1.87 are shown by producer and globally, in summary tables. The information presented for each producer includes a description of the activities that generate the wastes and a discussion of how stocks and arisings may have changed from earlier predictions. This is supplemented by a stream by stream tabulation showing the waste type, volume, density, conditioning factor and gross alpha and beta activity. The global projections are presented in tabular and graphical manner, and the changes from earlier projections are discussed. The scenarios which underly the projections are also presented. (author)

The reality of waste management in primary health care units in Brazil.

Science.gov (United States)

Alves, Sergiane B; e Souza, Adenícia C S; Tipple, Anaclara F V; Rezende, Keyti C A D; de Resende, Fabiana R; Rodrigues, Érika G; Pereira, Milca S

2014-09-01

A large number of users are serviced in primary health care units in Brazil, both in health facilities and in households. These services generate waste that must be managed safely, but there is no legislation that regulates this type of waste management in Brazil. The objective of this study was to analyse the production and management of waste in primary health care. A direct observation was performed of the stages in the handling and weighing of waste generated in primary health care units in the municipality of Goiânia (Brazil). The units generated infectious, chemical, and common waste, as well as sharp objects. The generation of waste ranged between 0.027 and 0.075 kg user-day. The generated waste was classified mostly as common and recyclable. Flaws were observed in the management of all types of waste. The critical point is segregation. Only 34.1% of the waste disposed of as infectious actually belonged to this group, the rest was ordinary waste. Flaws at this stage increase the volume of infectious waste, the occupational and environmental risks, and associated costs. Intervention to change this reality is needed and it requires the careful preparation of a waste management plan, corroborating structural changes to the implementation of this plan, and professional training and public policies to guide waste management in primary care, especially those generated in households. © The Author(s) 2014.

Mapping ENM from consumer products in solid waste flows in Denmark

DEFF Research Database (Denmark)

Heggelund, Laura Roverskov; Boldrin, Alessio; Hansen, Steffen Foss

To address the challenges regarding management of waste from ENM-enabled consumer products, we mapped the flow of these products available online in Denmark and the EU. To do this, we used the Nanodatabase (www.nanodb.dk). A representative sample of products from the database was analyzed......, and placed into suitable waste material fractions. Subsequently, the distribution of ENM in the individual waste fractions, by number of products, was found. Overall, the results showed that nanosilver was present in seven of the eight identified waste material fractions, whereas other ENMs (e.g. CNTs...... and silicon) were only present in one or two fractions. Furthermore, the waste material fraction "dirty plastic" was the most diversified, containing five different ENMs. To our knowledge this type of analysis has not previously been performed, and the results hold promise for gaining a better understanding...

Cuttings and waste injection, shale fracturing pressure decline, and domain mapping

Energy Technology Data Exchange (ETDEWEB)

Shokanov, T.; Ronderos, J. [M-I SWACO, a Schlumberger company (United States)

2011-07-01

Cuttings and waste injection surfaced as an innovative waste management technique in the early 1990s. It is a practical application of drilling and hydraulic fracturing techniques to the problem of waste disposal in remote and environmentally sensitive regions. In recent years this method has been favored for waste management in many parts of the world. This paper presents an overview of the historical evolution of the waste disposal domain from early developments, the drill cuttings experiment at Mounds, Oklahoma, to the current understanding that derives from microseismic observations of fracturing in the Barnett, Haynesville and Marcellus shale formations. The presence of fissures in shale formations and their impact on refracture initiation and an alternative assessment of the disposal domain based on microseismic observations are also discussed. The study demonstrates that high levels of assurance and risk control can be achieved in cuttings and waste injection disposal through accurate mapping of the fracture.

Status of activities: Low-level radioactive waste management in the United States

International Nuclear Information System (INIS)

Ozaki, C.B.; Shilkett, R.C.; Kirkpatrick, T.D.

1989-01-01

A primary objective of low-level radioactive waste management in the United States is to protect the health and safety of the public and the quality of the environment. In support of this objective is the development of waste treatment and disposal technologies designed to provide stabilization and long-term institutional control of low-level radioactive wastes. Presented herein is a technical review of specific low-level radioactive waste management activities in the United States. Waste treatment and disposal technologies are discussed along with the performance objectives of the technologies aimed at protecting the health and safety of the public and the quality of the environment. 13 refs., 4 figs

40 CFR 60.1555 - Are any small municipal waste combustion units exempt from my State plan?

Science.gov (United States)

2010-07-01

... qualifies for the exemption. (d) Municipal waste combustion units that combust only tires. Units are exempt... single-item waste stream of tires and no other municipal waste (the unit can co-fire coal, fuel oil.../rubber recycling units. Units are exempt from your State plan if four requirements are met: (1) The...

40 CFR 62.15020 - Can my small municipal waste combustion unit be exempt from this subpart?

Science.gov (United States)

2010-07-01

...) Municipal waste combustion units that combust only tires. Your unit is exempt from this subpart if three requirements are met: (1) Your municipal waste combustion unit combusts a single-item waste stream of tires and...) Plastics/rubber recycling units. Your unit is exempt from this subpart if four requirements are met: (1...

40 CFR 60.1810 - How do I monitor the load of my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... municipal waste combustion unit? 60.1810 Section 60.1810 Protection of Environment ENVIRONMENTAL PROTECTION... Guidelines and Compliance Times for Small Municipal Waste Combustion Units Constructed on or Before August 30... combustion unit? (a) If your municipal waste combustion unit generates steam, you must install, calibrate...

Current researches on safety assessment of radioactive waste disposal in the United States

International Nuclear Information System (INIS)

Tasaka, Hiroshi; Kiyose, Ryohei

1980-01-01

Recently, the problem of safe disposal of radioactive waste generated from nuclear fuel cycle becomes more important in Japan. On the other hand, many researches on shallow land burial of low-level wastes and geologic isolation of high-level wastes have been carried out in the United States of America. In this report, the researches on the safety assessment of radioactive waste disposal in the United States of America were briefly introduced with emphasis on the studies on behavior and migration of radionuclide from disposed waste in geosphere. (author)

Waste-surface mapping of the Fernald K-65 silos using a structured light measurement system

International Nuclear Information System (INIS)

Burks, B.L.; DePiero, F.W.; Dinkins, M.A.; Rowe, J.C.; Selleck, C.B.; Jacoboski, D.L.

1992-10-01

A remotely operated surface-mapping measurement system was developed by the Robotics ampersand Process Systems Division at Oak Ridge National Laboratory for use in the K-65 waste-storage silos at Fernald, Ohio. The mapping system used three infrared line-generating laser diodes as illumination sources and three high-resolution, low-lux, calibrated, black-and-white, charge-coupled-device video cameras as receivers. These components were combined to form structured light source range and direction sensors with six different possible emitter-receiver pairs. A technology demonstration and predeployment tests were performed at Fernald using the empty Silo 4 into which was placed rectangular objects of known dimensions. These objects were scanned by the structured light sources to demonstrate functionality and verify that the system was giving sufficiently accurate range data in three dimensions. The structured light sources were deployed in Silos 1 and 2 to scan the waste surfaces. The resulting data were merged to create three-dimensional maps of those surfaces. A bentonite clay cap was placed over the waste surfaces and surface maps were obtained. The change in surface height before and after bentonite addition was utilized as a measure of clay cap thickness

Low-level radioactive waste disposal in the United States

International Nuclear Information System (INIS)

Ozaki, Calvin B.; Kerr, Thomas A.; Williams, R. Eric

1991-01-01

Two national systems comprise the low-level radioactive waste management system in the United States of America. The U.S. Nuclear Regulatory Commission regulates low-level radioactive waste produced in the public sector (commercial waste), and the U.S. Department of Energy manages low-level radioactive waste produced by government-sponsored programs. The primary distinction between the two national systems is the source of regulatory control. This paper discusses two issues critical to the success of each system: the site selection process used by the commercial low-level waste disposal system, and the evaluation process used to determine configuration of the DOE waste management system. The two national systems take different approaches to reach the same goals, which are increased social responsibility, protection of public health and safety, and protection of the environment

Chemical health risk assessment for hazardous and mixed waste management units at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

1992-09-01

The waste characterization for each treatment unit or process is based on treatment records from LLNL's computerized Hazardous Waste Management Inventory System (HWMIS). In 1990, these data were compiled into a single database comprising both hazardous waste and mixed waste data. Even though these data originate from the same source used in the previous HRA, the database was modified to set quantities and concentrations to a consistent set of units. This allowed an analysis of waste types by Hazardous Waste Management unit that was more accurate and did not rely upon many of the conservative assumptions used in the Phase II HRA waste characterization. Finally, the current waste characterizations are considered more representative of potential long-term wastes because they were developed by combining all wastes that could be treated in each unit, as opposed to the wastes treated only during 1988 to 1989. This final step more appropriately accounts for the variability in waste types likely to be seen by the Hazardous Waste Management Division. The quantities of each waste listed in the characterization tables represent the sum of all chemical quantities belonging to hazardous and mixed waste types potentially handled by each area

Uruguay Hydrogeological map scale 1/1.000.000

International Nuclear Information System (INIS)

Heinzen, W.; Carrion, R.; Massa, E.; Pena, S.; Stapff, M.

2003-06-01

Between the main items the Uruguayan Hydrogeological map show us: aquifers productivity, geographical references, well information, depth, level, caudal, dry waste, from Hydrologic unit cuaternario differenced, Villa Soriano, Chuy, Raigon, Salto, Cretacico Superior, Tacuarembo, Las Arenas, Del Terciario, Cretacico Superior, Tres Islas, Cerrezuelo, Arapey, Neoproterozoico, Paleoproterozoico. It shows a brief map about Guarani Aquifer

40 CFR 264.101 - Corrective action for solid waste management units.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Corrective action for solid waste management units. 264.101 Section 264.101 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES Releases From Soli...

Design and operational parameters of transportable supercritical water oxidation waste destruction unit

International Nuclear Information System (INIS)

McFarland, R.D.; Brewer, G.R.; Rofer, C.K.

1991-12-01

Supercritical water oxidation (SCWO) is the destruction of hazardous waste by oxidation in the presence of water at temperatures and pressures above its critical point. A 1 gal/h SCWO waste destruction unit (WDU) has been designed, built, and operated at Los Alamos National Laboratory. This unit is transportable and is intended to demonstrate the SCWO technology on wastes at Department of Energy sites. This report describes the design of the WDU and the preliminary testing phase leading to demonstration

Hanford Site waste treatment/storage/disposal integration

International Nuclear Information System (INIS)

MCDONALD, K.M.

1999-01-01

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

Closure of hazardous and mixed radioactive waste management units at DOE facilities

International Nuclear Information System (INIS)

1990-06-01

This is document addresses the Federal regulations governing the closure of hazardous and mixed waste units subject to Resource Conservation and Recovery Act (RCRA) requirements. It provides a brief overview of the RCRA permitting program and the extensive RCRA facility design and operating standards. It provides detailed guidance on the procedural requirements for closure and post-closure care of hazardous and mixed waste management units, including guidance on the preparation of closure and post-closure plans that must be submitted with facility permit applications. This document also provides guidance on technical activities that must be conducted both during and after closure of each of the following hazardous waste management units regulated under RCRA

Radiological emergency response in a medical waste treatment unit

Energy Technology Data Exchange (ETDEWEB)

Suzuki, Fabio F.; Boni-Mitake, Malvina; Vianna, Estanislau B.; Nicolau, Jose R.A.; Rodrigues, Demerval L. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

2000-07-01

Radioactive materials are largely used in medicine, research and industry. The amount of radioactive material employed in each application varies from negligible to large and it can be in sealed or non-sealed form. A medical waste treatment unit that deals only with A-type medical waste (ABNT-NBR 12808), which does not include radioactive waste, detected abnormal radiation levels in a collecting truck and the IPEN-CNEN/SP Nuclear and Radiological Emergency Response Team was called. The presence of radioactive material inside the truck was confirmed; however, its origin and nature were not possible to be determined because the truck had collected medical waste in several facilities. So, an operation in order to segregate and identify that material was carried out. During the operation, a second collecting truck presenting abnormal radiation levels arrived to the unit and the same procedure was carried out on that truck. In both situations, the contaminated objects found were infantile diapers. The radioactive waste was transported to IPEN-CNEN/SP to be managed. Samples of the radioactive materials were submitted to gamma spectrometry and the radionuclide was identified as Iodine-131. Since that attendance, similar occurrences have been frequent. These events suggest that it is necessary a better control of the radioactive waste at the generating facilities and there should be basic radioprotection orientations to the discharging patients that were submitted to nuclear medicine procedures. (author)

Radiological emergency response in a medical waste treatment unit

International Nuclear Information System (INIS)

Suzuki, Fabio F.; Boni-Mitake, Malvina; Vianna, Estanislau B.; Nicolau, Jose R.A.; Rodrigues, Demerval L.

2000-01-01

Radioactive materials are largely used in medicine, research and industry. The amount of radioactive material employed in each application varies from negligible to large and it can be in sealed or non-sealed form. A medical waste treatment unit that deals only with A-type medical waste (ABNT-NBR 12808), which does not include radioactive waste, detected abnormal radiation levels in a collecting truck and the IPEN-CNEN/SP Nuclear and Radiological Emergency Response Team was called. The presence of radioactive material inside the truck was confirmed; however, its origin and nature were not possible to be determined because the truck had collected medical waste in several facilities. So, an operation in order to segregate and identify that material was carried out. During the operation, a second collecting truck presenting abnormal radiation levels arrived to the unit and the same procedure was carried out on that truck. In both situations, the contaminated objects found were infantile diapers. The radioactive waste was transported to IPEN-CNEN/SP to be managed. Samples of the radioactive materials were submitted to gamma spectrometry and the radionuclide was identified as Iodine-131. Since that attendance, similar occurrences have been frequent. These events suggest that it is necessary a better control of the radioactive waste at the generating facilities and there should be basic radioprotection orientations to the discharging patients that were submitted to nuclear medicine procedures. (author)

40 CFR 60.1320 - How do I monitor the load of my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... municipal waste combustion unit? 60.1320 Section 60.1320 Protection of Environment ENVIRONMENTAL PROTECTION... of Performance for Small Municipal Waste Combustion Units for Which Construction is Commenced After... Monitoring Requirements § 60.1320 How do I monitor the load of my municipal waste combustion unit? (a) If...

IDENTIFICATION AND CLASSIFICATION OF INDUSTRIAL SOLID WASTES IN AMMONIA UNIT OF RAZI PETROCHEMICAL COMPLEX AND FEASIBILITY OF WASTE MINIMIZATION

Directory of Open Access Journals (Sweden)

F. Fakheri Raouf, R. Nabizadeh and N. Jafarzadeh

2005-10-01

Full Text Available Petrochemical industries are considered as strategic and important sectors in economic development of Iran. Razi petrochemical factory is one of complex in Iran, established in 1970 with 100 hectare. In this research, the possibility of waste minimization in the ammonia unit of Razi petrochemical complex with about 1000 tons per year was studied for a period of 18 months from September 2003 to April 2005. More than 20 site visits were conducted and the required information was collected. Factors such as industrial solid wastes quality and quantity, sources of generation, production period and the present management practice, were studied. Petrochemical solid wastes were classified based on the recommended method of the United Nations and appropriate policies were suggested for waste minimization. The collected results of this study show production of 185 tons of industrial solid wastes from 45 sources which contained 68.5% catalysts, 10.25% metal barrels, 18.61% aluminum ball, 2.62% plastic barrels and 0.02% paper. 93.3% of these wastes were generated as the result of catalysts change, 3.3% as the result of using chemicals and oils, 1.7% as the result of methanol solution amid application, and 1.1% because of aluminum ball changes. Based on the UNEP methods, the ammonia unit wastes classified as 19/7%hazadrous and 87,12% non hazardous. At present 87.12% of these wastes are being dumped in the area and 12.88% are sold. Proposed procedures for waste minimization contain 68.5% reuse and recycling and 31.5% recycling.

Methods for registration and mapping of waste heat emissions and their application to the regions of Rastatt, Baden-Baden and Karlsruhe-City (Federal Republic of Germany)

International Nuclear Information System (INIS)

Bartholomaei, G.; Kinzelbach, W.

1978-05-01

Methods are developed that allow the registration and mapping of waste heat emissions on a grid of 2 x 2 km 2 . They are directly applicable in the Federal Republik of Germany and may be extended to neighbouring countries. Such a mapping provides the distribution of anthropogeneous waste heat emissions in space and time and serves in the case of the upper Rhine Valley as a basis for the numerical evaluation of climate modification by man. In a close approximation the distribution of waste heat is equal to the distribution of energy consumption. Therefore, the first step is the registration and mapping of energy consumption. Data about the consumption of the most important types of energy such as coal, fuel oil, gas, electricity etc. are available only partially and on the level of administrative units which are considerably larger than the grid size. Therefore, models were developed which allow to determine energy consumption on the commune and grid level with the help of local structural data like the distribution of population, households, traffic etc. The second step to be taken is the transformation of energy of energy consumption into waste heat emissions categorized in terms of the components convection, radiation, latent heat and discharge of heated water. Energy consumption and waste heat were determined separately for the various sectors of economy. Large sources in the industrial and energy supply sectors were analyzed individually by questionnaires. The results obtained with foresaid methods in the districts of Rastatt and Baden-Baden and in the township of Karlsruhe are presented. (orig.) 891 HP [de

Plutonium Finishing Plant Treatment and Storage Unit Dangerous Waste Training Plan

International Nuclear Information System (INIS)

ENTROP, G.E.

2000-01-01

The training program for personnel performing waste management duties pertaining to the Plutonium Finishing Plant (PFP) Treatment and Storage Unit is governed by the general requirements established in the Plutonium Finishing Plant Dangerous Waste Training Plan (PFP DWTP). The PFP Treatment and Storage Unit DWTP presented below incorporates all of the components of the PFP DWTP by reference. The discussion presented in this document identifies aspects of the training program specific to the PFP Treatment and Storage Unit. The training program includes specifications for personnel instruction through both classroom and on-the-job training. Training is developed specific to waste management duties. Hanford Facility personnel directly involved with the PFP Treatment and Storage Unit will receive training to container management practices, spill response, and emergency response. These will include, for example, training in the cementation process and training pertaining to applicable elements of WAC 173-303-330(1)(d). Applicable elements from WAC 173-303-330(1)(d) for the PFP Treatment and Storage Unit include: procedures for inspecting, repairing, and replacing facility emergency and monitoring equipment; communications and alarm systems; response to fires or explosions; and shutdown of operations

Mapping and monitoring nuclear waste repositories with subsurface electrical resistivity arrays

International Nuclear Information System (INIS)

Asch, T.; Morrison, H.F.

1987-01-01

The siting and future integrity of nuclear waste repositories is critically dependent on the local ground water regime. Electrical methods seem particularly promising in mapping and monitoring this regime since the electrical conductivity of rocks depends almost entirely on the fluid saturation, salinity and distribution. The most important recent developments in resistivity include the use of numerical modeling and resistivity mapping using subsurface electrodes. The latter yields far greater accuracy and resolution than can be obtained with surface arrays. To illustrate the power of subsurface-surface arrays the authors studied an idealized two dimensional model of a nuclear repository. Since they are interested in emphasizing the anomaly caused by the repository, or subsequent changes over time in its vicinity, the authors discovered that it is very useful to express the apparent resistivity results as percentage differences from either the background (for surface arrays) or from the apparent resistivities observed at a particular depth of the current source (for subsurface arrays). Percent differencing with respect to data at the repository depth dramatically reduce near-surface and topographic effects that usually confound quantitative interpretation of surface surveys. Thus, dc resistivity appears to have great potential for nuclear waste repository mapping and monitoring

40 CFR 63.6092 - Are duct burners and waste heat recovery units covered by subpart YYYY?

Science.gov (United States)

2010-07-01

... Combustion Turbines What This Subpart Covers § 63.6092 Are duct burners and waste heat recovery units covered by subpart YYYY? No, duct burners and waste heat recovery units are considered steam generating units... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Are duct burners and waste heat...

Organic Rankine cycle unit for waste heat recovery on ships (PilotORC)

DEFF Research Database (Denmark)

Haglind, Fredrik; Montagud, Maria E. Mondejar; Andreasen, Jesper Graa

The project PilotORC was aimed at evaluating the technical and economic feasibility of the use of organic Rankine cycle (ORC) units to recover low-temperature waste heat sources (i.e. exhaust gases, scavenge air, engine cooling system, and lubricant oil system) on container vessels. The project...... included numerical simulations and experimental tests on a 125 kW demonstration ORC unit that utilizes the waste heat of the main engine cooling system on board one of Mærsk's container vessels. During the design of the demonstration ORC unit, different alternatives for the condenser were analyzed in order...... of using ORC units for maritime applications, and the relevance of this technology for new-building projects. Firstly, an evaluation of the waste heat resources available on board Mærsk containers fleet, and an estimation of the potential energy recovery by means of the ORC technology was performed...

The State Geologic Map Compilation (SGMC) geodatabase of the conterminous United States

Science.gov (United States)

Horton, John D.; San Juan, Carma A.; Stoeser, Douglas B.

2017-06-30

The State Geologic Map Compilation (SGMC) geodatabase of the conterminous United States (https://doi. org/10.5066/F7WH2N65) represents a seamless, spatial database of 48 State geologic maps that range from 1:50,000 to 1:1,000,000 scale. A national digital geologic map database is essential in interpreting other datasets that support numerous types of national-scale studies and assessments, such as those that provide geochemistry, remote sensing, or geophysical data. The SGMC is a compilation of the individual U.S. Geological Survey releases of the Preliminary Integrated Geologic Map Databases for the United States. The SGMC geodatabase also contains updated data for seven States and seven entirely new State geologic maps that have been added since the preliminary databases were published. Numerous errors have been corrected and enhancements added to the preliminary datasets using thorough quality assurance/quality control procedures. The SGMC is not a truly integrated geologic map database because geologic units have not been reconciled across State boundaries. However, the geologic data contained in each State geologic map have been standardized to allow spatial analyses of lithology, age, and stratigraphy at a national scale.

Karst in the United States: a digital map compilation and database

Science.gov (United States)

Weary, David J.; Doctor, Daniel H.

2014-01-01

This report describes new digital maps delineating areas of the United States, including Puerto Rico and the U.S. Virgin Islands, having karst or the potential for development of karst and pseudokarst. These maps show areas underlain by soluble rocks and also by volcanic rocks, sedimentary deposits, and permafrost that have potential for karst or pseudokarst development. All 50 States contain rocks with potential for karst development, and about 18 percent of their area is underlain by soluble rocks having karst or the potential for development of karst features. The areas of soluble rocks shown are based primarily on selection from State geologic maps of rock units containing significant amounts of carbonate or evaporite minerals. Areas underlain by soluble rocks are further classified by general climate setting, degree of induration, and degree of exposure. Areas having potential for volcanic pseudokarst are those underlain chiefly by basaltic-flow rocks no older than Miocene in age. Areas with potential for pseudokarst features in sedimentary rocks are in relatively unconsolidated rocks from which pseudokarst features, such as piping caves, have been reported. Areas having potential for development of thermokarst features, mapped exclusively in Alaska, contain permafrost in relatively thick surficial deposits containing ground ice. This report includes a GIS database with links from the map unit polygons to online geologic unit descriptions.

Development of waste unit for use in shallow land burial

International Nuclear Information System (INIS)

Brodersen, K.

1986-01-01

A hexagonal waste unit has been developed for use in shallow land burial of low- and medium-level radioactive waste. The waste units used as overpack on empty standard 210 1 drums have been tested for tightness and mechanical resistance. Experimental burial of 21 empty full-size units has demonstrated the emplacement of the containers and the sealing of the crevises between them with molten bitumen. The development of the experimental burial with time is being followed. Three different conceptual designs for advanced burial systems using the hexagonal standard units are described. The outer barrier is a thick concrete structure covered by 2, 10 or 20 m soil, respectively. The waste units were cast from a normal high-quality concrete as well as from Densit, a new, very strong and impermeable type of concrete prepared by the combined use of silica-fume (microsilica) and a superplastizicer as additives. The migration of Cl - , Cs + and tritiated water was found to be much slower in Densit than in normal concrete. In combination with leaching measurements for Cs + from the same materials the results are used to present some theoretical considerations concerning transport through solution-filled pore systems as dependent on pore-size distribution, tortuosity, etc. A method based on neutron-activated cement cast in form of thin plates has been developed and used to study the dissolution chemistry of concrete. A preliminary model is presented. Indications for precipitation mechanisms were obtained. Densit was demonstrated to ensure a high degree of corrosion protection for steel reinforcement. The reason is mainly the high electrical resistivity combined with low diffusive transport in the material. The pozzolanic reaction results in somewhat lower pH in the pore water than in normal concrete, but the effect is not so pronounced that the passivation of steel reinforcement is endangered

United States National Waste Terminal Storage argillaceous rock studies

International Nuclear Information System (INIS)

Brunton, G.D.

1981-01-01

The past and present argillaceous rock studies for the US National Waste Terminal Storage Program consist of: (1) evaluation of the geological characteristics of several widespread argillaceous formations in the United States; (2) laboratory studies of the physical and chemical properties of selected argillaceous rock samples; and (3) two full-scale in situ surface heater experiments that simulate the emplacement of heat-generating radioactive waste in argillaceous rock

United States National Waste Terminal Storage argillaceous rock studies

International Nuclear Information System (INIS)

Brunton, G.D.

1979-01-01

The past and present argillaceous rock studies for the US National Waste Terminal Storage Program consist of: (1) evaluation of the geological characteristics of several widespread argillaceous formations in the United States; (2) laboratory studies of the physical and chemical properties of selected argillaceous rock samples; and (3) two full-scale in-situ surface heater experiments that simulate the emplacement of heat-generating radioactive waste in argillaceous rock

40 CFR 60.1025 - Do subpart E new source performance standards also apply to my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... standards also apply to my municipal waste combustion unit? 60.1025 Section 60.1025 Protection of... NEW STATIONARY SOURCES Standards of Performance for Small Municipal Waste Combustion Units for Which... municipal waste combustion unit? If this subpart AAAA applies to your municipal waste combustion unit, then...

Mapping severe fire potential across the contiguous United States

Science.gov (United States)

Brett H. Davis

2016-01-01

The Fire Severity Mapping System (FIRESEV) project is an effort to provide critical information and tools to fire managers that enhance their ability to assess potential ecological effects of wildland fire. A major component of FIRESEV is the development of a Severe Fire Potential Map (SFPM), a geographic dataset covering the contiguous United States (CONUS) that...

The Holdridge life zones of the conterminous United States in relation to ecosystem mapping

Science.gov (United States)

A.E. Lugo; S. L. Brown; R. Dodson; T. S Smith; H. H. Shugart

1999-01-01

Aim Our main goals were to develop a map of the life zones for the conterminous United States, based on the Holdridge Life Zone system, as a tool for ecosystem mapping, and to compare the map of Holdridge life zones with other global vegetation classification and mapping efforts. Location The area of interest is the forty-eight contiguous states of the United States....

Element partitioning in combustion- and gasification-based waste-to-energy units

International Nuclear Information System (INIS)

Arena, Umberto; Di Gregorio, Fabrizio

2013-01-01

Highlights: ► Element partitioning of waste-to-energy units by means of a substance flow analysis. ► A comparison between moving grate combustors and high temperature gasifiers. ► Classification of key elements according to their behavior during WtE processes. ► Slags and metals from waste gasifiers are completely and immediately recyclable. ► Potential reduction of amounts of solid residue to be sent to landfill disposal. - Abstract: A critical comparison between combustion- and gasification-based waste-to-energy systems needs a deep knowledge of the mass flows of materials and elements inside and throughout the units. The study collected and processed data from several moving grate conventional incinerators and high-temperature shaft gasifiers with direct melting, which are in operation worldwide. A material and substance flow analysis was then developed to systematically assess the flows and stocks of materials and elements within each waste-to-energy unit, by connecting the sources, pathways, and intermediate and final sinks of each species. The patterns of key elements, such as carbon, chloride and heavy metals, in the different solid and gaseous output streams of the two compared processes have been then defined. The combination of partitioning coefficients with the mass balances on atomic species and results of mineralogical characterization from recent literatures was used to estimate a composition of bottom ashes and slags from the two types of waste-to-energy technologies. The results also allow to quantify some of the performance parameters of the units and, in particular, the potential reduction of the amount of solid residues to be sent to final disposal

40 CFR 62.15265 - How do I monitor the load of my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... continuously estimate load level (for example, the feed rate of municipal solid waste or refuse-derived fuel... municipal waste combustion unit? 62.15265 Section 62.15265 Protection of Environment ENVIRONMENTAL... DESIGNATED FACILITIES AND POLLUTANTS Federal Plan Requirements for Small Municipal Waste Combustion Units...

Science, society, and America's nuclear waste: Unit 2, Ionizing radiation

International Nuclear Information System (INIS)

1992-01-01

''Science, Society and America's Nuclear Waste'' is a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

Methodology to design a municipal solid waste generation and composition map: A case study

International Nuclear Information System (INIS)

Gallardo, A.; Carlos, M.; Peris, M.; Colomer, F.J.

2014-01-01

Highlights: • To draw a waste generation and composition map of a town a lot of factors must be taken into account. • The methodology proposed offers two different depending on the available data combined with geographical information systems. • The methodology has been applied to a Spanish city with success. • The methodology will be a useful tool to organize the municipal solid waste management. - Abstract: The municipal solid waste (MSW) management is an important task that local governments as well as private companies must take into account to protect human health, the environment and to preserve natural resources. To design an adequate MSW management plan the first step consist in defining the waste generation and composition patterns of the town. As these patterns depend on several socio-economic factors it is advisable to organize them previously. Moreover, the waste generation and composition patterns may vary around the town and over the time. Generally, the data are not homogeneous around the city as the number of inhabitants is not constant nor it is the economic activity. Therefore, if all the information is showed in thematic maps, the final waste management decisions can be made more efficiently. The main aim of this paper is to present a structured methodology that allows local authorities or private companies who deal with MSW to design its own MSW management plan depending on the available data. According to these data, this paper proposes two ways of action: a direct way when detailed data are available and an indirect way when there is a lack of data and it is necessary to take into account bibliographic data. In any case, the amount of information needed is considerable. This paper combines the planning methodology with the Geographic Information Systems to present the final results in thematic maps that make easier to interpret them. The proposed methodology is a previous useful tool to organize the MSW collection routes including the

Impact of hazardous waste handling legislation on nuclear installations and radioactive waste management in the United States

International Nuclear Information System (INIS)

Trosten, L.M.

1988-01-01

The United States has enacted complex legislation to help assure proper handling of hazardous waste and the availability of funds to cover the expenditures. There are a number of uncertainties concerning the impact of this legislation, and regulations promulgated by the Environmental Protection Agency and the states, upon nuclear installations and radioactive waste management. This report provides an overview of the U.S. hazardous waste legislation and examines the outlook for its application to the nuclear industry (NEA) [fr

The management of household hazardous waste in the United Kingdom.

Science.gov (United States)

Slack, R J; Gronow, J R; Voulvoulis, N

2009-01-01

Waste legislation in the United Kingdom (UK) implements European Union (EU) Directives and Regulations. However, the term used to refer to hazardous waste generated in household or municipal situations, household hazardous waste (HHW), does not occur in UK, or EU, legislation. The EU's Hazardous Waste Directive and European Waste Catalogue are the principal legislation influencing HHW, although the waste categories described are difficult to interpret. Other legislation also have impacts on HHW definition and disposal, some of which will alter current HHW disposal practices, leading to a variety of potential consequences. This paper discusses the issues affecting the management of HHW in the UK, including the apparent absence of a HHW-specific regulatory structure. Policy and regulatory measures that influence HHW management before disposal and after disposal are considered, with particular emphasis placed on disposal to landfill.

40 CFR 60.1370 - What records must I keep for municipal waste combustion units that use activated carbon?

Science.gov (United States)

2010-07-01

... waste combustion unit at your plant. Include supporting calculations. (b) Records of low carbon feed... waste combustion units that use activated carbon? 60.1370 Section 60.1370 Protection of Environment... SOURCES Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is...

A summary of radiological waste disposal practices in the United States and the United Kingdom - 16379

International Nuclear Information System (INIS)

Maranville, Victoria M.; McGrath, Richard

2009-01-01

A systematic review of near-surface repositories for radioactive waste in the United States (US) was conducted. The main focus of the review consisted of a literature search of available documents and other published sources on low level radioactive waste (LLRW) disposal practices, remediation of LLRW sites in the US, and public participation for remediation efforts of near-surface radiological waste disposal sites in the US. This review was undertaken to provide background information in support of work by the United Kingdom's (UK) Low Level Waste Repository (LLWR) and to aid in optimizing the future management of this site. The review contained a summary of the US and UK radiological waste classification requirements including a discussion of the waste types, disposal requirements, and the differences between US and UK disposal practices. A regulatory overview and evolution of regulatory requirements in the US is presented. The UK regulatory environment is also discussed and contrasted to the US process. The public participation, as part of the US regulatory process, is provided and the mechanism for stakeholder identification and involvement is detailed. To demonstrate how remediation of radiologically impacted sites is implemented in the US, existing US case studies, in which remediation activities were carried out, were reviewed. The following information was compiled: type of wastes disposed of to US shallow ground facilities [with comparison with UK classifications], facility designs (with special emphasis on those directly comparable to the subsurface conditions in the UK), and deficiencies identified in operation or in demonstrating safe post closure; and processes and difficulties in remedial actions encountered at the selected sites. Stakeholder involvement is discussed within the case studies. Publicly available information related to radiological waste management and disposal practices were reviewed. Two sites are presented in this publication for

RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2010-07-19

The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

International Nuclear Information System (INIS)

2010-01-01

The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

RCRA Part A Permit Application for Waste Management Activities at the Nevada Test Site, Part B Permit Application Hazardous Waste Storage Unit, Nevada Test Site, and Part B Permit Application - Explosives Ordnance Disposal Unit (EODU)

International Nuclear Information System (INIS)

2010-01-01

The Area 5 Hazardous Waste Storage Unit (HWSU) was established to support testing, research, and remediation activities at the Nevada Test Site (NTS), a large-quantity generator of hazardous waste. The HWSU, located adjacent to the Area 5 Radioactive Waste Management Site (RWMS), is a prefabricated, rigid steel-framed, roofed shelter used to store hazardous nonradioactive waste generated on the NTS. No offsite generated wastes are managed at the HWSU. Waste managed at the HWSU includes the following categories: Flammables/Combustibles; Acid Corrosives; Alkali Corrosives; Oxidizers/Reactives; Toxics/Poisons; and Other Regulated Materials (ORMs). A list of the regulated waste codes accepted for storage at the HWSU is provided in Section B.2. Hazardous wastes stored at the HWSU are stored in U.S. Department of Transportation (DOT) compliant containers, compatible with the stored waste. Waste transfer (between containers) is not allowed at the HWSU and containers remain closed at all times. Containers are stored on secondary containment pallets and the unit is inspected monthly. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational Resource Conservation and Recovery Act (RCRA) units at the NTS and their respective regulatory status.

RCRA Part A Permit Application for Waste Management Activities at the Nevada Test Site, Part B Permit Application Hazardous Waste Storage Unit, Nevada Test Site, and Part B Permit Application - Explosives Ordnance Disposal Unit (EODU)

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Programs

2010-06-17

The Area 5 Hazardous Waste Storage Unit (HWSU) was established to support testing, research, and remediation activities at the Nevada Test Site (NTS), a large-quantity generator of hazardous waste. The HWSU, located adjacent to the Area 5 Radioactive Waste Management Site (RWMS), is a prefabricated, rigid steel-framed, roofed shelter used to store hazardous nonradioactive waste generated on the NTS. No offsite generated wastes are managed at the HWSU. Waste managed at the HWSU includes the following categories: Flammables/Combustibles; Acid Corrosives; Alkali Corrosives; Oxidizers/Reactives; Toxics/Poisons; and Other Regulated Materials (ORMs). A list of the regulated waste codes accepted for storage at the HWSU is provided in Section B.2. Hazardous wastes stored at the HWSU are stored in U.S. Department of Transportation (DOT) compliant containers, compatible with the stored waste. Waste transfer (between containers) is not allowed at the HWSU and containers remain closed at all times. Containers are stored on secondary containment pallets and the unit is inspected monthly. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational Resource Conservation and Recovery Act (RCRA) units at the NTS and their respective regulatory status.

Geomorphic Surface Maps of Northern Frenchman Flat, Nevada Test Site, Southern Nevada

International Nuclear Information System (INIS)

Bechtel Nevada

2005-01-01

Large-scale (1:6000) surficial geology maps of northern Frenchman Flat were developed in 1995 as part of comprehensive site characterization required to operate a low-level radioactive waste disposal facility in that area. Seven surficial geology maps provide fundamental data on natural processes and are the platform needed to reconstruct the Quaternary history of northern Frenchman Flat. Reconstruction of the Quaternary history provides an understanding of the natural processes that act to develop the landscape, and the time-frames involved in landscape development. The mapping was conducted using color and color-infrared aerial photographs and field verification of map unit composition and boundaries. Criteria for defining the map unit composition of geomorphic surface units are based on relative geomorphic position, landform morphology, and degree of preservation of surface morphology. Seven geomorphic surfaces (Units 1 through 7) are recognized, spanning from the early Quaternary to present time

SOLID WASTE MANAGEMENT IN TABRIZ PETROCHEMICAL COMPLEX

Directory of Open Access Journals (Sweden)

M. A. Abduli, M. Abbasi, T. Nasrabadi, H. Hoveidi, N. Razmkhah

2006-07-01

Full Text Available Tabriz petrochemical complex is located in the northwest of Iran. Major products of this industry include raw plastics like, polyethylene, polystyrene, acrylonitrile, butadiene, styrene, etc. Sources of waste generation include service units, health and cure units, water, power, steam and industrial processes units. In this study, different types of solid waste including hazardous and non hazardous solid wastes were investigated separately. The aim of the study was to focus on the management of the industrial wastes in order to minimize the adverse environmental impacts. In the first stage, locating map and dispersion limits were prepared. Then, the types and amounts of industrial waste generated in were evaluated by an inventory and inspection. Wastes were classified according to Environmental Protection Agency and Basel Standards and subsequently hazards of different types were investigated. The waste management of TPC is quite complex because of the different types of waste and their pollution. In some cases recycling/reuse of waste is the best option, but treatment and disposal are also necessary tools. In this study, using different sources and references, generally petrochemical sources, various solid waste management practices were investigated and the best options were selected. Some wastes should be treated before land filling and some of them should be reused or recycled. In the case of solid waste optimization, source reduction ways were recommended as well as prior incineration system was modified.

Karst mapping in the United States: Past, present and future

Science.gov (United States)

Weary, David J.; Doctor, Daniel H.

2015-01-01

The earliest known comprehensive karst map of the entire USA was published by Stringfield and LeGrand (1969), based on compilations of William E. Davies of the U.S. Geological Survey (USGS). Various versions of essentially the same map have been published since. The USGS recently published new digital maps and databases depicting the extent of known karst, potential karst, and pseudokarst areas of the United States of America including Puerto Rico and the U.S. Virgin Islands (Weary and Doctor, 2014). These maps are based primarily on the extent of potentially karstic soluble rock types, and rocks with physical properties conducive to the formation of pseudokarst features. These data were compiled and refined from multiple sources at various spatial resolutions, mostly as digital data supplied by state geological surveys. The database includes polygons delineating areas with potential for karst and that are tagged with attributes intended to facilitate classification of karst regions. Approximately 18% of the surface of the fifty United States is underlain by significantly soluble bedrock. In the eastern United States the extent of outcrop of soluble rocks provides a good first-approximation of the distribution of karst and potential karst areas. In the arid western states, the extent of soluble rock outcrop tends to overestimate the extent of regions that might be considered as karst under current climatic conditions, but the new dataset encompasses those regions nonetheless. This database will be revised as needed, and the present map will be updated as new information is incorporated.

Strategy and design of Innovation Policy Road Mapping for a waste biorefinery.

Science.gov (United States)

Rama Mohan, S

2016-09-01

Looming energy crisis, climate change concerns coupled with decreasing fossil fuel resources has garnered significant global attention toward development of alternative, renewable, carbon-neutral and eco-friendly fuels to fulfil burgeoning energy demands. Waste utilization and its management are being pursued with renewed interest due to the gamut of biobased products it can offer apart from providing enough energy to meet a major fraction of the world's energy demand. Biorefining is the sustainable processing of biomass into a spectrum of marketable products and energy. Integrating all components of waste treatment culminating into biobased products and energy recovery in a single integrated waste biorefinery is self sufficient, highly sustainable and is very beneficial. Designing systematic innovation policies are essential for development and commercialization of new technologies in this important futuristic research area. This communication explores Innovation Policy Road Mapping (IPRM) methodology available in the literature and applies it to design integrated waste biorefinery. Copyright © 2016 Elsevier Ltd. All rights reserved.

Environmental aspects of engineering geological mapping in the United States

Science.gov (United States)

Radbruch-Hall, Dorothy H.

1979-01-01

Many engineering geological maps at different scales have been prepared for various engineering and environmental purposes in regions of diverse geological conditions in the United States. They include maps of individual geological hazards and maps showing the effect of land development on the environment. An approach to assessing the environmental impact of land development that is used increasingly in the United States is the study of a single area by scientists from several disciplines, including geology. A study of this type has been made for the National Petroleum Reserve in northern Alaska. In the San Francisco Bay area, a technique has been worked out for evaluating the cost of different types of construction and land development in terms of the cost of a number of kinds of earth science factors. ?? 1979 International Association of Engineering Geology.

Technology evaluation report for the Buried Waste Robotics Program Subsurface Mapping Project

International Nuclear Information System (INIS)

Griebenow, B.E.

1992-01-01

This document presents a summary of the work performed in support of the Buried Waste Robotics Program Subsurface Mapping Project. The project objective was to demonstrate the feasibility of remotely characterizing buried waste sites. To fulfill this objective, a remotely-operated vehicle, equipped with several sensors, was deployed at the Idaho National Engineering Laboratory. Descriptions of the equipment and areas involved in the project are included in this report. Additionally, this document provides data that was obtained during characterization operations at the Cold Test Pit and the Subsurface Disposal Area, both at the Idaho National Engineering Laboratory's Radioactive Waste Management Complex, and at the Idaho Chemical Processing Plant. The knowledge gained from the experience, that can be applied to the next generation remote-characterization system, is extensive and is presented in this report

40 CFR 62.15145 - What are the operating practice requirements for my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... requirements for my municipal waste combustion unit? 62.15145 Section 62.15145 Protection of Environment... Combustion Units Constructed on or Before August 30, 1999 Good Combustion Practices: Operating Requirements § 62.15145 What are the operating practice requirements for my municipal waste combustion unit? (a) You...

MethodS of radioactive waste processing and disposal in the United Kingdom

International Nuclear Information System (INIS)

Tolstykh, V.D.

1983-01-01

The results of investigations into radioactive waste processing and disposal in the United Kingdom are discussed. Methods for solidification of metal and graphite radioactive wastes and radioactive slime of the Magnox reactors are described. Specifications of different installations used for radioactive waste disposal are given. Climatic and geological conditions in the United Kingdom are such that any deep storages of wastes will be lower than the underground water level. That is why dissolution and transport by underground waters will inevitably result in radionuclide mobility. In this connection an extended program of investigations into the main three aspects of disposal problem namely radionucleide release in storages, underground water transport and radionuclide migration is realized. The program is divided in two parts. The first part deals with retrival of hydrological and geochemical data on geological formations, development of specialized methods of investigations which are necessary for identification of places for waste final disposal. The second part represents theoretical and laboratory investigations into provesses of radionuclide transport in the system of ''sttorage-geological formation''. It is concluded that vitrification on the base of borosilicate glass is the most advanced method of radioactive waste solidification

Gas cooled reactor decommissioning. Packaging of waste for disposal in the United Kingdom deep repository

International Nuclear Information System (INIS)

Barlow, S.V.; Wisbey, S.J.; Wood, P.

1998-01-01

United Kingdom Nirex Limited has been established to develop and operate a deep underground repository for the disposal of the UK's intermediate and certain low level radioactive waste. The UK has a significant Gas Cooled Reactor (GCR) programme, including both Magnox and AGR (Advanced Gas-cooled Reactor) capacity, amounting to 26 Magnox reactors, 15 AGR reactors as well as research and prototype reactor units such as the Windscale AGR and the Windscale Piles. Some of these units are already undergoing decommissioning and Nirex has estimated that some 15,000 m 3 (conditioned volume) will come forward for disposal from GCR decommissioning before 2060. This volume does not include final stage (Stage 3) decommissioning arisings from commercial reactors since the generating utilities in the UK are proposing to adopt a deferred safe store strategy for these units. Intermediate level wastes arising from GCR decommissioning needs to be packaged in a form suitable for on-site interim storage and eventual deep disposal in the planned repository. In the absence of Conditions for Acceptance for a repository in the UK, the dimensions, key features and minimum performance requirements for waste packages are defined in Waste Package Specifications. These form the basis for all assessments of the suitability of wastes for disposal, including GCR wastes. This paper will describe the nature and characteristics of GCR decommissioning wastes which are intended for disposal in a UK repository. The Nirex Waste Package Specifications and the key technical issues, which have been identified when considering GCR decommissioning waste against the performance requirements within the specifications, are discussed. (author)

The effects of unit pricing system upon household solid waste management: The Korean experience

Energy Technology Data Exchange (ETDEWEB)

Hong, S.

1999-09-01

Initial effects of adoption of a unit pricing system paired with aggressive recycling programs appear to be substantial. This paper explores the impact of price incentives under the unit pricing system on household solid waste generation and recycling in Korea. The author employs a simultaneous equation model considering the feedback effects between total waste generation and recycling. Estimation results using 3017 Korean household survey data indicate that a rise in waste collection fee induces households to recycle more wastes. However, this effect is partially offset by decreases in source-reduction efforts due to the feedback effects, resulting in relatively lower price elasticity of demand for solid waste collection services. This implies that household demand for solid waste collection services will not decrease much with additional increases in the collection fee, unless further recycling incentives such as more frequent recyclable pickup services are accompanied.

A review of the disposal of miscellaneous radioactive wastes in the United Kingdom

International Nuclear Information System (INIS)

Hookway, B.

1980-01-01

Current practices in the United Kingdom for waste disposal from ''minor users'' of radioactive materials are reviewed. The regulation of the disposal of solid, liquid and airborne wastes is discussed. (H.K.)

Science, Society, and America's Nuclear Waste: Ionizing Radiation, Unit 2. Teacher Guide. Second Edition.

Science.gov (United States)

Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

This guide is Unit 2 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to convey factual information relevant to radioactivity and radiation and relate that information both to the personal lives of students…

Public perceptions of aspects of radioactive waste management

International Nuclear Information System (INIS)

1985-04-01

The paper concerns a study of peoples' attitude towards the siting of radioactive waste repositories, carried out by the University of Surrey, United Kingdom. The work has been commissioned by the Department of the Environment as part of its radioactive waste management research programme. The people taking part were asked to mark on a map of Great Britain places they felt radioactive waste repositories would be least objectionable. The degree to which people worried about the technology and the management of radioactive waste disposal was monitored. Questions were asked about storage, disposal and transportation aspects, and about present and future worries. (UK)

Planet Patrol. An Environmental Unit on Solid Waste Solutions for Grades 4-6.

Science.gov (United States)

Procter and Gamble Educational Services, Cincinnati, OH.

This classroom unit was developed for use in grades 4-6 to help teach the concept of solid waste management. The teacher's guide provides an overview of the issue of solid waste disposal, a description of government, industry, and consumer roles in resolving the solid waste issue, and four lessons involving sanitary landfills, the reduction of…

The General Urban Plan of Casimcea territorial administrative unit, map of natural and anthropogenic risks

Directory of Open Access Journals (Sweden)

Sorin BĂNICĂ

2013-08-01

Full Text Available The General Urban Plan represents the legal ground for any development action proposed. After endorsement and approval as required by law, GUP is act of authority of local government for the area in which it applies. The aim is to establish priorities regulations applied in land use planning and construction of structures. In terms of geographical location, the administrative territory of Casimcea, Tulcea county, falls in the central Northwest Plateau Casimcei. This is the second unit of the Central Dobrogea Plateau. Geographical location in southeastern Romania, climatic and relief conditions and anthropogenic pressure, expose the village administrative territorial unit Casimcea, permanent susceptibility to produce natural and antropogenical risks. In this context, we identified the following categories of natural and anthropogenic risks: i natural risk phenomena (earthquakes, strong winds, heavy rains, floods caused by overflowing or precipitation, erosion of river banks and torrents, gravitational processes, rain droplet erosion and surface soil erosion; and ii anthropogenic risk phenomena (overgrazing, chemicals use in agriculture, road transport infrastructure and electricity, wind turbines for electricity production, waste deposits, agro-zootechnical complexs, and human cemeteries. Extending their surface was materialized by creating a map of natural and anthropogenic risk on Casimcea territorial administrative unit, explaining the share of potentially affected areas as territorial balance

40 CFR Table 1 to Subpart Aaaa of... - Emission Limits for New Small Municipal Waste Combustion Units

Science.gov (United States)

2010-07-01

... Waste Combustion Units 1 Table 1 to Subpart AAAA of Part 60 Protection of Environment ENVIRONMENTAL... Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is Commenced... Combustion Units For the following pollutants You must meet thefollowing emission limits a Using the...

The causes of the municipal solid waste and the greenhouse gas emissions from the waste sector in the United States.

Science.gov (United States)

Lee, Seungtaek; Kim, Jonghoon; Chong, Wai K O

2016-10-01

The United States generated approximately 730kg of waste per capita in 2013, which is the highest amount of waste among OECD countries. The waste has adverse effects to human health and the environment. One of the most serious adverse effects is greenhouse gas emissions, especially methane (CH4), which causes global warming. However, the United States' amount of waste generation is not decreasing, and the recycling rate is only 26%, which is lower than other OECD countries. In order to decrease waste generation and greenhouse gas emissions, identifying the causality of the waste generation and greenhouse gas emissions from waste sector should be made a priority. The research objective is to verify whether the Environmental Kuznets Curve relationship is supported for waste generation and GDP across the U.S. Moreover, it also confirmed that total waste generation and recycling of waste influences carbon dioxide emissions from the waste sector. Based on the results, critical insight and suggestions were offered to policymakers, which is the potential way to lower the solid waste and greenhouse gas emissions from the waste sector. This research used annually based U.S. data from 1990 to 2012, and these data were collected from various data sources. To verify the causal relationship, the Granger causality test was applied. The results showed that there is no causality between GDP and waste generation, but total waste and recycling generate significantly increasing and decreasing greenhouse gas emissions from the waste sector, respectively. This implies that waste generation will not decrease even if GDP increases. And, if waste generation decreases or the recycling rate increases, greenhouse gas emission will decrease. Based on these results, increasing the recycling rate is first suggested. The second suggestion is to break the causal relationship between MSW and greenhouse gas emission from the waste sector. The third is that the U.S. government should benchmark a

The status of radioactive waste repository development in the United States - December 2011

International Nuclear Information System (INIS)

Hill, David R.

2012-01-01

The current state of affairs concerning development in the United States of a permanent repository for disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) is, in a word, uncertain. The President of the United States has asserted that he believes licensing and development of the Yucca Mountain repository should be abandoned, while other important parties believe licensing and development should continue. And not surprisingly, there is a disagreement as to what the law requires and whether the licensing process for the Yucca Mountain repository can be terminated at this point, even if the President would like for that to happen. The future of Yucca Mountain, and the future of radioactive waste disposal in the United States generally, currently are pending before the US Court of Appeals for the District of Columbia Circuit, and eventually the Supreme Court of the United States may decide some of the important legal issues concerning Yucca Mountain's future. The November 2012 US elections also likely will have a significant impact on future radioactive waste repository development

Site Specific Waste Management Instruction for the 116-F-4 soil storage unit

International Nuclear Information System (INIS)

Hopkins, G.G.

1996-08-01

This Site Specific Waste Management Instruction provides guidance for management of waste generated during the excavation and remediation of soil and debris from the 116-4 soil storage unit located at the Hanford Site in Richland, Washington. This document outlines the waste management practices that will be performed in the field to implement federal, state, and US Department of Energy requirements

78 FR 9111 - Commercial and Industrial Solid Waste Incineration Units: Reconsideration and Final Amendments...

Science.gov (United States)

2013-02-07

... impacts? 2. What are the water and solid waste impacts? 3. What are the energy impacts? 4. What are the.... Pulp and Paper Sludge 4. Rulemaking Petition Process for Other Categorical Non-Waste Determinations (40... and 241 Commercial and Industrial Solid Waste Incineration Units: Reconsideration and Final Amendments...

40 CFR 60.1200 - What are the operating practice requirements for my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... requirements for my municipal waste combustion unit? 60.1200 Section 60.1200 Protection of Environment... SOURCES Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is... Good Combustion Practices: Operating Requirements § 60.1200 What are the operating practice...

Plate waste of adults in the United States measured in free-living conditions.

Directory of Open Access Journals (Sweden)

Brian E Roe

Full Text Available We analyze food-item level data collected from 50 adults from the United States using the Remote Food Photography Method® to provide the first estimates of plate waste gathered from adults across multiple consecutive meals and days in free-living conditions, and during laboratory-based meals with fixed food items and quantities. We find average plate waste in free-living conditions is 5.6 grams (7.7 kcals per item and that 3.3% of all food selected is returned as plate waste, where the percent waste figure is substantially lower than previously published plate waste estimates gathered primarily from dine-out settings in the United States such as buffets and institutional settings with limited-choice meals (e.g., school cafeterias. Plate waste from the same participants during the laboratory-based meals is significantly higher with an average of 203.2 grams of solid plate waste per meal (531.3 kcals or 39.1% of the food provided, which is similar to the plate waste percentages found reported in some school cafeteria settings. The amount of plate waste generated in free-living conditions is significantly positively associated with portion size selected for an item. In a multivariate analysis that controls for macronutrient profile, items selected from the vegetables, fats/oils/dressings, and grains categories are associated with significantly greater amounts of plate waste per item. We find no significant associations between free-living plate waste and gender, age, race or body mass index but find that women leave more plate waste in the lab meal where portion sizes are pre-determined by the researcher and similar for all respondents. We discuss possible implications of these findings for programs focused on reducing plate waste and food waste among consumers.

Plate waste of adults in the United States measured in free-living conditions

Science.gov (United States)

Allen, H. Raymond

2018-01-01

We analyze food-item level data collected from 50 adults from the United States using the Remote Food Photography Method® to provide the first estimates of plate waste gathered from adults across multiple consecutive meals and days in free-living conditions, and during laboratory-based meals with fixed food items and quantities. We find average plate waste in free-living conditions is 5.6 grams (7.7 kcals) per item and that 3.3% of all food selected is returned as plate waste, where the percent waste figure is substantially lower than previously published plate waste estimates gathered primarily from dine-out settings in the United States such as buffets and institutional settings with limited-choice meals (e.g., school cafeterias). Plate waste from the same participants during the laboratory-based meals is significantly higher with an average of 203.2 grams of solid plate waste per meal (531.3 kcals) or 39.1% of the food provided, which is similar to the plate waste percentages found reported in some school cafeteria settings. The amount of plate waste generated in free-living conditions is significantly positively associated with portion size selected for an item. In a multivariate analysis that controls for macronutrient profile, items selected from the vegetables, fats/oils/dressings, and grains categories are associated with significantly greater amounts of plate waste per item. We find no significant associations between free-living plate waste and gender, age, race or body mass index but find that women leave more plate waste in the lab meal where portion sizes are pre-determined by the researcher and similar for all respondents. We discuss possible implications of these findings for programs focused on reducing plate waste and food waste among consumers. PMID:29444094

Development and status of the AL Mixed Waste Treatment Plan or I love that mobile unit of mine

International Nuclear Information System (INIS)

Bounini, L.; Williams, M.; Zygmunt, S.

1995-01-01

Nine Department of Energy (DOE) sites reporting to the Albuquerque Office (AL) have mixed waste that is chemically hazardous and radioactive. The hazardous waste regulations require the chemical portion of mixed waste to be to be treated to certain standards. The total volume of low-level mixed waste at the nine sites is equivalent to 7,000 drums, with individual site volumes ranging from 1 gallon of waste at the Pinellas Plant to 4,500 drums at Los Alamos National Laboratory. Nearly all the sites have a diversity of wastes requiring a diversity of treatment processes. Treatment capacity does not exist for much of this waste, and it would be expensive for each site to build the diversity of treatment processes needed to treat its own wastes. DOE-AL assembled a team that developed the AL Mixed Waste Treatment Plan that uses the resources of the nine sites to treat the waste at the sites. Work on the plan started in October 1993, and the plan was finalized in March 1994. The plan uses commercial treatment, treatability studies, and mobile treatment units. The plan specifies treatment technologies that will be built as mobile treatment units to be moved from site to site. Mobile units include bench-top units for very small volumes and treatability studies, drum-size units that treat one drum per day, and skid-size units that handle multiple drum volumes. After the tools needed to treat the wastes were determined, the sites were assigned to provide part of the treatment capacity using their own resources and expertise. The sites are making progress on treatability studies, commercial treatment, and mobile treatment design and fabrication. To date, this is the only plan for treating waste that brings the resources of several DOE sites together to treat mixed waste. It is the only program actively planning to use mobile treatment coordinated between DOE sites

Applying value stream mapping techniques to eliminate non-value-added waste for the procurement of endovascular stents

International Nuclear Information System (INIS)

Teichgräber, Ulf K.; Bucourt, Maximilian de

2012-01-01

Objectives: To eliminate non-value-adding (NVA) waste for the procurement of endovascular stents in interventional radiology services by applying value stream mapping (VSM). Materials and methods: The Lean manufacturing technique was used to analyze the process of material and information flow currently required to direct endovascular stents from external suppliers to patients. Based on a decision point analysis for the procurement of stents in the hospital, a present state VSM was drawn. After assessment of the current status VSM and progressive elimination of unnecessary NVA waste, a future state VSM was drawn. Results: The current state VSM demonstrated that out of 13 processes for the procurement of stents only 2 processes were value-adding. Out of the NVA processes 5 processes were unnecessary NVA activities, which could be eliminated. The decision point analysis demonstrated that the procurement of stents was mainly a forecast driven push system. The future state VSM applies a pull inventory control system to trigger the movement of a unit after withdrawal by using a consignment stock. Conclusion: VSM is a visualization tool for the supply chain and value stream, based on the Toyota Production System and greatly assists in successfully implementing a Lean system.

40 CFR 60.1690 - What are the operating practice requirements for my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... requirements for my municipal waste combustion unit? 60.1690 Section 60.1690 Protection of Environment... SOURCES Emission Guidelines and Compliance Times for Small Municipal Waste Combustion Units Constructed on or Before August 30, 1999 Model Rule-Good Combustion Practices: Operating Requirements § 60.1690 What...

40 CFR 257.5 - Disposal standards for owners/operators of non-municipal non-hazardous waste disposal units that...

Science.gov (United States)

2010-07-01

... compliance with §§ 257.7 through 257.30 prior to the receipt of CESQG hazardous waste. (b) Definitions.... Waste management unit boundary means a vertical surface located at the hydraulically downgradient limit.../operators of non-municipal non-hazardous waste disposal units that receive Conditionally Exempt Small...

The concept of value stream mapping to reduce of work-time waste as applied the smart construction management

Science.gov (United States)

Elizar, Suripin, Wibowo, Mochamad Agung

2017-11-01

Delays in construction sites occur due to systematic additions of time waste in various activities that are part of the construction process. Work-time waste is non-adding value activity which used to differentiate between physical construction waste found on site and other waste which occurs during the construction process. The aim of this study is identification using the concept of Value Stream Mapping (VSM) to reduce of work-time waste as applied the smart construction management.VSM analysis is a method of business process improvement. The application of VSM began in the manufacturing community. The research method base on theoretically informed case study and literature review. The data have collected using questionnaire through personal interviews from 383 respondents on construction project in Indonesia. The results show that concept of VSM can identify causes of work-time waste. Base on result of questioners and quantitative approach analysis was obtained 29 variables that influence of work-time waste or non-value-adding activities. Base on three cases of construction project founded that average 14.88% of working time was classified as waste. Finally, the concept of VSM can recommend to identification of systematic for reveal current practices and opportunities for improvement towards global challenges. The concept of value stream mapping can help optimize to reduce work-time waste and improve quality standard of construction management. The concept is also can help manager to make a decision to reduce work-time waste so as to obtain of result in more efficient for performance and sustainable construction project.

Mobile calcination and cementation unit for solidification of concentrated radioactive wastes

International Nuclear Information System (INIS)

Napravnik, J.; Sazavsky, P.; Skaba, V.; Skvarenina, R.; Ditl, P.

1985-01-01

Mobile experimental unit MESA-1 was developed and manufactured for processing radioactive concentrates by direct cementation. The unit is mainly designed for processing low-level liquid wastes from nuclear power plants and other nuclear installations, in which the level of radioactivity does not exceed 10 10 Bq/m 3 , the salt content of liquid solutions does not exceed 500 kg/m 3 and the maximum amount of boric acid is 130 kg/m 3 . The equipment is built into three modules which may be assembled and dismantled in a short time and transported separately. The unit without the calciner module was tested in non-radioactive mode and in operation with actual radioactive wastes from the V-1 nuclear power plant. The course and results of the tests are described in detail. All project design values were achieved, a total of 18 dm 3 model solutions were processed and 1 m 3 of actual wastes with a salt content of 450 kg/m 3 . The test showed that with regard to the radiation level reached it will be necessary in the process of calcination to increase the shielding of certain exposed points. The calciner module is being assembled for completion. (Z.M.)

Design of chemical treatment unit for radioactive liquid wastes in Serpong nuclear facilities

International Nuclear Information System (INIS)

Salimin, Z.; Walman, E.; Santoso, P.; Purnomo, S.; Sugito; Suwardiyono; Wintono

1996-01-01

The chemical treatment unit for radioactive liquid wastes arising from nuclear fuel fabrication, radioisotopes production and radiometallurgy facility has been designed. The design of chemical processing unit is based on the characteristics of liquid wastes containing fluors from uranium fluoride conversion process to ammonium uranyl carbonate on the fuel fabrication. The chemical treatment has the following process steps: coagulation-precipitation of fluoride ion by calcium hydroxide coagulant, separation of supernatant solution from sludge, coagulation of remaining fluoride on the supernatant solution by alum, separation of supernatant from sludge, and than precipitation of fluors on the supernatant by polymer resin WWS 116. The processing unit is composed of 3 storage tanks for raw liquid wastes (capacity 1 m 3 per tank), 5 storage tanks for chemicals (capacity 0.5 m 3 per tank), 2 mixing reactors (capacity 0.5 m 3 per reactor), 1 storage tank for supernatant solution (capacity 1 m 3 ), and 1 storage tank for sludge (capacity 1 m 3 )

Evaluating pharmaceutical waste disposal in pediatric units.

Science.gov (United States)

Almeida, Maria Angélica Randoli de; Wilson, Ana Maria Miranda Martins; Peterlini, Maria Angélica Sorgini

2016-01-01

To verify the disposal of pharmaceutical waste performed in pediatric units. A descriptive and observational study conducted in a university hospital. The convenience sample consisted of pharmaceuticals discarded during the study period. Handling and disposal during preparation and administration were observed. Data collection took place at pre-established times and was performed using a pre-validated instrument. 356 drugs disposals were identified (35.1% in the clinic, 31.8% in the intensive care unit, 23.8% in the surgical unit and 9.3% in the infectious diseases unit). The most discarded pharmacological classes were: 22.7% antimicrobials, 14.8% electrolytes, 14.6% analgesics/pain killers, 9.5% diuretics and 6.7% antiulcer agents. The most used means for disposal were: sharps' disposable box with a yellow bag (30.8%), sink drain (28.9%), sharps' box with orange bag (14.3%), and infectious waste/bin with a white bag (10.1%). No disposal was identified after drug administration. A discussion of measures that can contribute to reducing (healthcare) waste volume with the intention of engaging reflective team performance and proper disposal is necessary. Verificar o descarte dos resíduos de medicamentos realizado em unidades pediátricas. Estudo descritivo e observacional, realizado em um hospital universitário. A amostra de conveniência foi constituída pelos medicamentos descartados durante o período de estudo. Observaram-se a manipulação e o descarte durante o preparo e a administração. A coleta dos dados ocorreu em horários preestabelecidos e realizada por meio de instrumento pré-validado. Identificaram-se 356 descartes de medicamentos (35,1% na clínica, 31,8% na unidade de cuidados intensivos, 23,8% na cirúrgica e 9,3% na infectologia). As classes farmacológicas mais descartadas foram: 22,7% antimicrobianos, 14,8% eletrólitos, 14,6% analgésicos, 9,5% diuréticos e 6,7% antiulcerosos. Vias mais utilizadas: caixa descartável para perfurocortante com

Achieving compliance with healthcare waste management regulations : empirical evidence from small European healthcare units

OpenAIRE

Botelho, Anabela

2011-01-01

Healthcare units generate substantial amounts of hazardous or potentially hazardous wastes as by-products of their medical services. The inappropriate management of these wastes poses significant risks to people and the environment. In Portugal, as in other EU countries, the collection, storage, treatment and disposal of healthcare waste is regulated by law. Although legal provisions covering the safe management of healthcare waste date back to the 1990s, little is known about the compliance ...

Resource Conservation and Recovery Act (RCRA) Part B permit application for tank storage units at the Oak Ridge Y-12 Plant

International Nuclear Information System (INIS)

1994-05-01

In compliance with the Resource Conservation and Recovery Act (RCRA), this report discusses information relating to permit applications for three tank storage units at Y-12. The storage units are: Building 9811-1 RCRA Tank Storage Unit (OD-7); Waste Oil/Solvent Storage Unit (OD-9); and Liquid Organic Solvent Storage Unit (OD-10). Numerous sections discuss the following: Facility description; waste characteristics; process information; groundwater monitoring; procedures to prevent hazards; contingency plan; personnel training; closure plan, post closure plan, and financial requirements; record keeping; other federal laws; organic air emissions; solid waste management units; and certification. Sixteen appendices contain such items as maps, waste analyses and forms, inspection logs, equipment identification, etc

Efficiency Effects of Unit-based Pricing Systems and Institutional Choices of Waste Collection

NARCIS (Netherlands)

Dijkgraaf, E.; Gradus, R.H.J.M.

2015-01-01

Municipal residential waste costs are rising. Therefore, it is important to introduce measures that lower waste collection and disposal costs. Based on a large panel data set for the Netherlands we show that unit-based pricing systems are more important from a cost-minimizing point of view than the

Design of Biochemical Oxidation Process Engineering Unit for Treatment of Organic Radioactive Liquid Waste

International Nuclear Information System (INIS)

Zainus Salimin; Endang Nuraeni; Mirawaty; Tarigan, Cerdas

2010-01-01

Organic radioactive liquid waste from nuclear industry consist of detergent waste from nuclear laundry, 30% TBP-kerosene solvent waste from purification or recovery of uranium from process failure of nuclear fuel fabrication, and solvent waste containing D 2 EHPA, TOPO, and kerosene from purification of phosphoric acid. The waste is dangerous and toxic matter having low pH, high COD and BOD, and also low radioactivity. Biochemical oxidation process is the effective method for detoxification of organic waste and decontamination of radionuclide by bio sorption. The result process are sludges and non radioactive supernatant. The existing treatment facilities radioactive waste in Serpong can not use for treatment of that’s organics waste. Dio chemical oxidation process engineering unit for continuous treatment of organic radioactive liquid waste on the capacity of 1.6 L/h has been designed and constructed the equipment of process unit consist of storage tank of 100 L capacity for nutrition solution, 2 storage tanks of 100 L capacity per each for liquid waste, reactor oxidation of 120 L, settling tank of 50 L capacity storage tank of 55 L capacity for sludge, storage tank of 50 capacity for supernatant. Solution on the reactor R-01 are added by bacteria, nutrition and aeration using two difference aerators until biochemical oxidation occurs. The sludge from reactor of R-01 are recirculated to the settling tank of R-02 and on the its reverse operation biological sludge will be settled, and supernatant will be overflow. (author)

Risk maps for targeting exotic plant pest detection programs in the United States

Science.gov (United States)

R.D. Magarey; D.M. Borchert; J.S. Engle; M Garcia-Colunga; Frank H. Koch; et al

2011-01-01

In the United States, pest risk maps are used by the Cooperative Agricultural Pest Survey for spatial and temporal targeting of exotic plant pest detection programs. Methods are described to create standardized host distribution, climate and pathway risk maps for the top nationally ranked exotic pest targets. Two examples are provided to illustrate the risk mapping...

40 CFR Table 11 to Subpart G of... - Wastewater-Inspection and Monitoring Requirements for Waste Management Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 9 2010-07-01 2010-07-01 false Wastewater-Inspection and Monitoring Requirements for Waste Management Units 11 Table 11 to Subpart G of Part 63 Protection of Environment... and Monitoring Requirements for Waste Management Units To comply with Inspection or monitoring...

40 CFR Table 7 to Subpart Ggg of... - Wastewater-Inspection and Monitoring Requirements for Waste Management Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 11 2010-07-01 2010-07-01 true Wastewater-Inspection and Monitoring Requirements for Waste Management Units 7 Table 7 to Subpart GGG of Part 63 Protection of Environment... for Waste Management Units To comply with Inspection or monitoring requirement Frequency of inspection...

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

International Nuclear Information System (INIS)

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

1984-01-01

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

Applying value stream mapping techniques to eliminate non-value-added waste for the procurement of endovascular stents.

Science.gov (United States)

Teichgräber, Ulf K; de Bucourt, Maximilian

2012-01-01

OJECTIVES: To eliminate non-value-adding (NVA) waste for the procurement of endovascular stents in interventional radiology services by applying value stream mapping (VSM). The Lean manufacturing technique was used to analyze the process of material and information flow currently required to direct endovascular stents from external suppliers to patients. Based on a decision point analysis for the procurement of stents in the hospital, a present state VSM was drawn. After assessment of the current status VSM and progressive elimination of unnecessary NVA waste, a future state VSM was drawn. The current state VSM demonstrated that out of 13 processes for the procurement of stents only 2 processes were value-adding. Out of the NVA processes 5 processes were unnecessary NVA activities, which could be eliminated. The decision point analysis demonstrated that the procurement of stents was mainly a forecast driven push system. The future state VSM applies a pull inventory control system to trigger the movement of a unit after withdrawal by using a consignment stock. VSM is a visualization tool for the supply chain and value stream, based on the Toyota Production System and greatly assists in successfully implementing a Lean system. Copyright © 2010 Elsevier Ireland Ltd. All rights reserved.

Cost savings of unit-based pricing of household waste; the case of the Netherlands

NARCIS (Netherlands)

E. Dijkgraaf (Elbert); R.H.J.M. Gradus (Raymond)

2003-01-01

textabstractUsing a panel data set for Dutch municipalities we estimate effects for weight-based, bag-based, frequency-based and volume-based pricing of household waste collection. Unit-based pricing shows to be effective in reducing solid and compostable and increasing recyclable waste. Pricing has

Radioactive solid waste inventories at United States Department of Energy burial and storage sites

International Nuclear Information System (INIS)

Watanabe, T.

1987-06-01

Radioactive solid waste inventories are given for United States Department of Energy (DOE) burial and storage sites. These data are obtained from the Solid Waste Information Management System (SWIMS) and reflect the inventories as of the end of the calendar year 1986. 4 figs., 7 tabs

Radioactive-waste classification in the United States: history and current predicaments

International Nuclear Information System (INIS)

Lowenthal, M. D.

1997-01-01

Within the United States we have taken disposal to mean the permanent emplacement of waste in the earth in a manner such that, after a brief period of monitoring and active maintenance, institutional control could be abandoned without damaging human health and the environment. But several attempts at disposal (the AEC facilities mentioned in Section 2, and commercial facilities at Maxey Flats and West Valley), and even attempts at short-term management (such as Hanford), have fallen far short of the our hopes for disposal. Most of the problems arose out of insufficient restrictions on waste forms (the untreated hazardous chemicals), disposal facilities that by nature or poor design saw infiltration, or a combination that resulted in facilities that failed because the designs and the waste forms were incompatible. Lessons have been learned from experience and some of these problems have been addressed, but fundamentally the tension between top-down classes defined by the generator and bottom-up considerations based on the disposal environment has not been resolved, and the government has not effected integrated planning for management of nuclear materials in the country. There appears, for example, to be a continued disconnect between the designers of disposal facilities and the policy and decision makers. Performance assessments are generally carried out with a set of assumptions about the waste streams corresponding to the classes of waste designated for disposal at the site. Little consideration is given to problem wastes within known waste classes, such as spent fuel from research reactors. And as the wastes that do not fit, the so-called ''orphan wastes'' such as greater-than-class-C low-level waste (GTCC LLW), excess weapons-grade plutonium, and mixed waste, are redirected for co-disposal with other wastes, the waste stream changes. In the case of GTCC LLW, the waste forms will be radically different from those used in modeling of the high-level waste

Record of Decision for the Ford Building Waste Unit (643-11G) Operable Unit; FINAL

International Nuclear Information System (INIS)

Fraley, S.

2002-01-01

This decision document presents the selected remedial for the Ford Building Waste Unit (FBWU), in Aiken, South Carolina, which was chosen in accordance with CERCLA, as amended by SARA, and, to the extent practical, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). This decision is based on the Administrative Record File for this specific RCRA/CERCLA site

Unit operations used to treat process and/or waste streams at nuclear power plants

International Nuclear Information System (INIS)

Godbee, H.W.; Kibbey, A.H.

1980-01-01

Estimates are given of the annual amounts of each generic type of LLW [i.e., Government and commerical (fuel cycle and non-fuel cycle)] that is generated at LWR plants. Many different chemical engineering unit operations used to treat process and/or waste streams at LWR plants include adsorption, evaporation, calcination, centrifugation, compaction, crystallization, drying, filtration, incineration, reverse osmosis, and solidification of waste residues. The treatment of these various streams and the secondary wet solid wastes thus generated is described. The various treatment options for concentrates or solid wet wastes, and for dry wastes are discussed. Among the dry waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting and shredding. Organic materials [liquids (e.g., oils or solvents) and/or solids], could be incinerated in most cases. The filter sludges, spent resins, and concentrated liquids (e.g., evaporator concentrates) are usually solidified in cement, or urea-formaldehyde or unsaturated polyester resins prior to burial. Incinerator ashes can also be incorporated in these binding agents. Asphalt has not yet been used. This paper presents a brief survey of operational experience at LWRs with various unit operations, including a short discussion of problems and some observations on recent trends

Quaternary allostratigraphy of surficial deposit map units at Yucca Mountain, Nevada: A progress report

International Nuclear Information System (INIS)

Lundstrom, S.C.; Wesling, J.R.; Swan, F.H.; Taylor, E.M.; Whitney, J.W.

1993-01-01

Surficial geologic mapping at Yucca Mountain, Nevada, is relevant to site characterization studies of paleoclimate, tectonics, erosion, flood hazards, and water infiltration. Alluvial, colluvial, and eolian allostratigraphic map units are defined on the basis of age-related surface characteristics and soil development, as well as lithology and sedimentology indicative of provenance and depositional mode. In gravelly alluvial units, which include interbedded debris flows, the authors observe a useful qualitative correlation between surface and soil properties. Map units of estimated middle Pleistocene age typically have a well-developed, varnished desert pavement, and minimal erosional and preserved depositional microrelief, associated with a soil with a reddened Bt horizon and stage 3 carbonate and silica morphology. Older units have greater erosional relief, an eroded argillic horizon and stage 4 carbonate morphology, whereas younger units have greater preservation of depositional morphology, but lack well-developed pavements, rock varnish, and Bt and Kqm soil horizons. Trench and gully-wall exposures show that alluvial, colluvial and eolian dominated surface units are underlain by multiple buried soils separating sedimentologically similar deposits; this stratigraphy increases the potential for understanding the long-term Quaternary paleoenvironmental history of Yucca Mountain. Age estimates for allostratigraphic units, presently based on uranium-trend dating and regional correlation using soil development, will be further constrained by ongoing dating studies that include tephra identification, uranium-series disequilibrium, and thermoluminescence methods

Hanford Central Waste Complex: Waste Receiving and Processing Facility dangerous waste permit application

International Nuclear Information System (INIS)

1991-10-01

The Hanford Central Waste Complex is an existing and planned series of treatment, and/or disposal (TSD) unites that will centralize the management of solid waste operations at a single location on the Hanford Facility. The Complex includes two units: the WRAP Facility and the Radioactive Mixed Wastes Storage Facility (RMW Storage Facility). This Part B permit application addresses the WRAP Facility. The Facility will be a treatment and storage unit that will provide the capability to examine, sample, characterize, treat, repackage, store, and certify radioactive and/or mixed waste. Waste treated and stored will include both radioactive and/or mixed waste received from onsite and offsite sources. Certification will be designed to ensure and demonstrate compliance with waste acceptance criteria set forth by onsite disposal units and/or offsite facilities that subsequently are to receive waste from the WRAP Facility. This permit application discusses the following: facility description and general provisions; waste characterization; process information; groundwater monitoring; procedures to prevent hazards; contingency plant; personnel training; exposure information report; waste minimization plan; closure and postclosure requirements; reporting and recordkeeping; other relevant laws; certification

Public responses to radioactive wastes in the United States

International Nuclear Information System (INIS)

Kasperson, R.E.

1993-01-01

Whatever the actual public health and environmental risks posed by nuclear power and the disposal of radioactive wastes, they pale in comparison with what the public believes they are. There can be little doubt that members of the public perceive substantial dangers from such facilities and are intensely concerned about them. Intense concern is apparent in the controversy that has erupted not only in the United States but in many societies where search activities have been conducted for a radioactive or other hazardous waste disposal facility. It is also apparent in the findings from a significant accumulation of polls, surveys, attitude studies, and psychometric research as well as in direct experience in diverse countries in Europe, North America, and Asia. (author). 10 refs

Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Wickline, Alfred

2005-01-01

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) 137: Waste Disposal Sites. 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. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action

Basement domain map of the conterminous United States and Alaska

Science.gov (United States)

Lund, Karen; Box, Stephen E.; Holm-Denoma, Christopher S.; San Juan, Carma A.; Blakely, Richard J.; Saltus, Richard W.; Anderson, Eric D.; DeWitt, Ed

2015-01-01

The basement-domain map is a compilation of basement domains in the conterminous United States and Alaska designed to be used at 1:5,000,000-scale, particularly as a base layer for national-scale mineral resource assessments. Seventy-seven basement domains are represented as eighty-three polygons on the map. The domains are based on interpretations of basement composition, origin, and architecture and developed from a variety of sources. Analysis of previously published basement, lithotectonic, and terrane maps as well as models of planetary development were used to formulate the concept of basement and the methodology of defining domains that spanned the ages of Archean to present but formed through different processes. The preliminary compilations for the study areas utilized these maps, national-scale gravity and aeromagnetic data, published and limited new age and isotopic data, limited new field investigations, and conventional geologic maps. Citation of the relevant source data for compilations and the source and types of original interpretation, as derived from different types of data, are provided in supporting descriptive text and tables.

Reflections on the Value of Mapping the Final Theory Examination in a Molecular Biochemistry Unit †

OpenAIRE

Eri, Rajaraman; Cook, Anthony; Brown, Natalie

2014-01-01

This article assesses the impact of examination mapping as a tool to enhancing assessment and teaching quality in a second-year biochemistry unit for undergraduates. Examination mapping is a process where all questions in a written examination paper are assessed for links to the unit’s intended learning outcomes. We describe how mapping a final written examination helped visualise the impact of the assessment task on intended learning outcomes and skills for that biochemistry unit. The method...

Mapping 1995 global anthropogenic emissions of mercury

Science.gov (United States)

Pacyna, Jozef M.; Pacyna, Elisabeth G.; Steenhuisen, Frits; Wilson, Simon

This paper presents maps of anthropogenic Hg emissions worldwide within a 1°×1° latitude/longitude grid system in 1995. As such, the paper is designed for modelers simulating the Hg transport within air masses and Hg deposition to aquatic and terrestrial ecosystems. Maps of total Hg emissions and its three main chemical species: elemental gaseous Hg, divalent gaseous Hg, and particle-associated Hg are presented. The main emissions occur in southeast Asia (particularly in China), South Africa, Central and Eastern Europe, and the Eastern United States. These are the regions where coal combustion is the main source of electricity and heat production. Waste incineration adds to these emissions in the Eastern United States. Emissions of total Hg and its three species are quite similar in terms of their (global) spatial distributions. They reflect the worldwide distribution of coal consumption in large power plants, industrial burners, and small combustion units, such as residential and commercial furnaces.

Quaternary Geologic Map of the Lake Nipigon 4 Degrees x 6 Degrees Quadrangle, United States and Canada

Science.gov (United States)

Sado, Edward V.; Fullerton, David S.; Farrand, William R.; Edited and Integrated by Fullerton, David S.

1994-01-01

The Quaternary Geologic Map of the Lake Nipigon 4 degree x 6 degree Quadrangle was mapped as part of the Quaternary Geologic Atlas of the United States. The atlas was begun as an effort to depict the areal distribution of surficial geologic deposits and other materials that accumulated or formed during the past 2+ million years, the period that includes all activities of the human species. These materials are at the surface of the earth. They make up the 'ground' on which we walk, the 'dirt' in which we dig foundations, and the 'soil' in which we grow crops. Most of our human activity is related in one way or another to these surface materials that are referred to collectively by many geologists as regolith, the mantle of fragmental and generally unconsolidated material that overlies the bedrock foundation of the continent. The maps were compiled at 1:1,000,000 scale. This map is a product of collaboration of the Ontario Geological Survey, the University of Michigan, and the U.S. Geological Survey, and is designed for both scientific and practical purposes. It was prepared in two stages. First, separate maps and map explanations were prepared by the compilers. Second, the maps were combined, integrated, and supplemented by the editor. Map unit symbols were revised to a uniform system of classification and the map unit descriptions were prepared by the editor from information received from the compilers and from additional sources listed under Sources of Information. Diagrams accompanying the map were prepared by the editor. For scientific purposes, the map differentiates Quaternary surficial deposits on the basis of lithology or composition, texture or particle size, structure, genesis, stratigraphic relationships, engineering geologic properties, and relative age, as shown on the correlation diagram and indicated in the map unit descriptions. Deposits of some constructional landforms, such as kame moraine deposits, are distinguished as map units. Deposits of

Mapping liquid hazardous waste migration in ground water with electromagnetic terrain conductivity measurement

International Nuclear Information System (INIS)

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

1984-01-01

Electromagnetic conductivity measurements were used to map apparent ground conductivity in the vicinity of a liquid hazardous waste disposal site. Approximately 600 conductivity measurements were obtained to prepare a conductivity map of the site which includes an area of 12 ha (30 acres). Conductivity measurements in the area correlate with specific conductance measurements of surface and ground water samples. Contouring of the conductivity data located contaminant migration pathways in the subsurface. A complex contaminant plume was defined by the conductivity survey. Conductivity values obtained reflected anisotropic characteristics related to local bedrock structure. Anisotropic characteristics of measurements and the use of different instrument configurations indicated semiquantitatively the depth of the high conductivity zone and the direction of flow. 4 references, 2 figures

The problem of nuclear wastes. A possible point of conflict between Mexico and the United States

International Nuclear Information System (INIS)

Rosas Poblano, A.

1993-01-01

The objectives of this research were: a) To analyse the problem of nuclear wastes, and the importance of their safe handling; b) To investigate the best and safest technologies for the treatment of radioactive wastes and two relevant international laws or regulations; c) To study whether the wastes produced in the United States represent an environmental problem for Mexico

Low-level radioactive waste disposal in the United States: An overview of current commercial regulations and concepts

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.

1993-08-01

Commercial low-level radioactive waste disposal in the United States is regulated by the US Nuclear Regulatory Commission (NRC) under 10 CFR 61 (1991). This regulation was issued in 1981 after a lengthy and thorough development process that considered the radionuclide concentrations and characteristics associated with commercial low-level radioactive waste streams; alternatives for waste classification; alternative technologies for low-level radioactive waste disposal; and data, modeling, and scenario analyses. The development process also included the publication of both draft and final environmental impact statements. The final regulation describes the general provisions; licenses; performance objectives; technical requirements for land disposal; financial assurances; participation by state governments and Indian tribes; and records, reports, tests, and inspections. This paper provides an overview of, and tutorial on, current commercial low-level radioactive waste disposal regulations in the United States

Proposal for processes map of post-consumption reverse logistics under the perspective of the national solid waste policy

Directory of Open Access Journals (Sweden)

Emmily Caroline Cabral da Fonseca

2017-03-01

Full Text Available The National Policy on Solid Waste (NPSW points to the Reverse Logistics (RL as an instrument that enables actions and strategies that allow adequate management of Urban Solid Waste (USW according to their guidelines. After more than five years of its publication, studies of RL in Brazil haven´t met the demands for defining procedures in the implementation of proper management of MSW in accordance with the NPSW. This class of waste is the result of post-consumer and it is relevant to clarify the relationship in their reverse processes in order to help the structuring and management of reverse channels that drive the waste to proper destination, in compliance with the law. Therefore, the objective of this research was to formalize, by means of theoretical study, the necessary processes, according to the literature research and legal guidelines, for the reverse channels through the proposal for a map of RL processes. For such, literature research, detailed reading of Law number 12.305 (NPSW and interviews with professionals working in the USW reverse channels were performed. The results converged on the proposition of a map of RL macro processes in which the processes identified were: collection, processing and delivery.

Radioactive waste management and decommissioning in The United States

International Nuclear Information System (INIS)

Raymont, J.M.

2005-01-01

With their missions and access to disposal sites changing over the last decade, radioactive waste management and decommissioning practice in the U.S. commercial and federal nuclear markets has evolved to keep pace. This paper reviews the changes that have occurred and the differing waste management practices that have resulted depending on whether a nuclear facility is situated on federally owned or privately owned property in the United States, confirming that the cost of disposal generally dictates waste management and decommissioning practices. Of the 123 utility-owned licensed commercial reactors in U.S., 19 are undergoing decomissioning, with the balance of 104 reactors focusing on plant life extension, power upgrades, and power generation. As a result, almost all of the approximately dollar 400 million in annual expenditures on waste processing and disposal comes from waste generated from operations. In contrast, the U.S. Department of Energy (DOE), under its Environmental Management (EM) program, is focused on decommissioning the facilities, tanks, and ground contamination resulting from 50-years of Cold War activities and spending about dollar 7 billion a year on these activities. Other than spent fuel, U.S. federal law precludes disposal of commercial nuclear power plant radioactive wastes at DOE disposal sites. In contrast to the commercial disposal market, which must go through extensive public hearings and decision-making, the DOE has a much freer hand in siting new disposal capacity on federal land. As a result, the DOE has ample disposal capacity, 'routinely' opens new disposal sites, and enjoys disposal pricing well below the commercial market. Waste composition, volume, and activity levels drive disposal costs, which is the key life cycle parameter in determining radioactive waste management practice. Differences in these parameters drive the differences in how radioactive waste management practice is performed in the commercial and DOE markets

Site-specific waste management instruction for the 100-KR-4 Operable Unit drilling

International Nuclear Information System (INIS)

Hadley, J.T.

1996-07-01

This site-specific waste management instruction provides guidance for the management of waste generated as a result of groundwater well installations in the 100-KR-4 Operable Unit (OU). The well installations are necessary to implement the Remedial Action (RA) option (pump-and-treat using ion exchange) to prevent discharge of hexavalent chromium at levels above those considered protective of aquatic life in the Columbia River and riverbed sediments

40 CFR Table 18 to Subpart G of... - Information for Waste Management Units To Be Submitted With Notification of Compliance Status a,b

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 9 2010-07-01 2010-07-01 false Information for Waste Management Units... Subpart G of Part 63—Information for Waste Management Units To Be Submitted With Notification of Compliance Status a,b Waste management unit identification c Description d Wastewater stream(s) received or...

Resource Conservation and Recovery Act closure plan for the Intermediate-Level Transuranic Storage Facility mixed waste container storage units

International Nuclear Information System (INIS)

Nolte, E.P.; Spry, M.J.; Stanisich, S.N.

1992-11-01

This document describes the proposed plan for clean closure of the Intermediate-Level Transuranic Storage Facility mixed waste container storage units at the Idaho National Engineering Laboratory in accordance with the Resource Conservation and Recovery Act closure requirements. Descriptions of the location, size, capacity, history, and current status of the units are included. The units will be closed by removing waste containers in storage, and decontamination structures and equipment that may have contacted waste. Sufficient sampling and documentation of all activities will be performed to demonstrate clean closure. A tentative schedule is provided in the form of a milestone chart

Exposure rates from concrete covered cylindrical units containing radioactive waste

International Nuclear Information System (INIS)

Hedemann Jensen, P.

1983-03-01

Exposure rates from cylindrical waste units containing the nuclides 60 Co, 134 Cs and 137 Cs homogeneously mixed in a solidification product have been calculated. Analyses have been made for single drums and for two disposal geometries, one with the units placed below ground near the surface in a circular geometry, and one with the units placed on the ground in a pile behind a concrete wall. Due to self-shielding of the units, the exposure rate from the two geometries will be a factor of only 10 - 20 higher than from a single unit, even without soil or wall shielding. With one meter of soil above the circular pile below ground, a reduction factor of 5.10 3 to 5.10 4 can be achieved, depending on the nuclide considered. Placing a one-meter concrete wall in front of the drum pile on the ground gives rise to a reduction factor in the range of 5.10 5 to 2.10 7 . (author)

Regulatory aspects of underground disposal of radioactive waste in the United Kingdom

International Nuclear Information System (INIS)

Hookway, B.R.

1980-01-01

Government policy towards radioactive waste management in the United Kingdom of Great Britain and Northern Ireland is based on the system of dose limitations laid down by ICRP as interpreted by the National Radiological Protection Board for use in the United Kingdom. The paper describes the legislative and administrative arrangements by which this policy is enforced, including the work of the principal inspectorates, the Nuclear Installations Inspectorate and the Radiochemical Inspectorate together with the latter's equivalents in Scotland and Northern Ireland. It is concluded that the present legislation, including that relating to planning and the setting up of public inquiries, is sufficiently all-embracing to ensure both strict control of the disposal of all the radioactive waste currently arising or which will arise in the future and a high degree of public involvement in the necessary decisions. (author)

Summary report on the 1985 United Kingdom radioactive waste inventory

International Nuclear Information System (INIS)

Fletcher, A.M.; Wear, F.J.; Haselden, H.; Shepherd, J.; Tymons, B.J.

1986-04-01

Stocks of radioactive waste in the United Kingdom which have arisen, or are projected to arise, from commercial nuclear power reactors and fuel cycle facilities, research, medical and industrial uses of radioactive nuclides are given in the form of summary tables. Projected future arisings from operation and decommissioning of facilities and notional nuclear power generation programmes to 2030 are also given. (author)

40 CFR Table 5 to Subpart Jjj of... - Carbon Monoxide Emission Limits for Existing Small Municipal Waste Combustion Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 8 2010-07-01 2010-07-01 false Carbon Monoxide Emission Limits for Existing Small Municipal Waste Combustion Units 5 Table 5 to Subpart JJJ of Part 62 Protection of... of Part 62—Carbon Monoxide Emission Limits for Existing Small Municipal Waste Combustion Units...

40 CFR 267.101 - What must I do to address corrective action for solid waste management units?

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false What must I do to address corrective action for solid waste management units? 267.101 Section 267.101 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE FACILITIES OPERATING UNDER A...

Topographical mapping system for hazardous and radiological environments

International Nuclear Information System (INIS)

Armstrong, G.A.; Burks, B.L.; Bernacki, B.E.; Pardini, A.

1995-01-01

This report focuses on the results of the acceptance test of the Topographical Mapping System (TMS) delivered to the Hanford site. The TMS was tested for accuracy over the specified range of 45 feet. The TMS was also tested to ensure that the unit could be deployed through multiple risers and maintain accuracy and registration of the surface mapping data. In addition, the TMS was disassembled and reassembled and redeployed to test field replacement of modules that make up the sensor head that is deployed in the vapor space of Underground Storage Tanks such as those located at the Hanford site in southeastern Washington State. The results from these tests along with temperature testing on the complete system and radiation testing of selected susceptible components are covered in this report. The primary purpose of the TMS is to generate reliable and accurate three-dimensional maps of the internal surfaces of storage tank. One use for these mapping systems is in creating and maintaining a current map of the tank interior as input to a robotic ''world model'' that is used to test remediation strategies or plan robot trajectories. Another use is tracking the movement of the waste surface as it responds to expanding bubbles of trapped Gas. A third use of the TMS is to perform a volumetric analysis of the amount of waste removed from the tanks during remediation

Mapping variation in radon potential both between and within geological units

International Nuclear Information System (INIS)

Miles, J C H; Appleton, J D

2005-01-01

Previously, the potential for high radon levels in UK houses has been mapped either on the basis of grouping the results of radon measurements in houses by grid squares or by geological units. In both cases, lognormal modelling of the distribution of radon concentrations was applied to allow the estimated proportion of houses above the UK radon Action Level (AL, 200 Bq m -3 ) to be mapped. This paper describes a method of combining the grid square and geological mapping methods to give more accurate maps than either method can provide separately. The land area is first divided up using a combination of bedrock and superficial geological characteristics derived from digital geological map data. Each different combination of geological characteristics may appear at the land surface in many discontinuous locations across the country. HPA has a database of over 430 000 houses in which long-term measurements of radon concentration have been made, and whose locations are accurately known. Each of these measurements is allocated to the appropriate bedrock-superficial geological combination underlying it. Taking each geological combination in turn, the spatial variation of radon potential is mapped, treating the combination as if it were continuous over the land area. All of the maps of radon potential within different geological combinations are then combined to produce a map of variation in radon potential over the whole land surface

40 CFR Appendix Xiii to Part 266 - Mercury Bearing Wastes That May Be Processed in Exempt Mercury Recovery Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Mercury Bearing Wastes That May Be Processed in Exempt Mercury Recovery Units XIII Appendix XIII to Part 266 Protection of Environment... XIII to Part 266—Mercury Bearing Wastes That May Be Processed in Exempt Mercury Recovery Units These...

Overview of the United States' nuclear waste repository programme

International Nuclear Information System (INIS)

Surles, T.G.

2002-01-01

Regardless of the future of civilian or defense-based nuclear materials, the United States will be responsible for a vast array of these materials for generations to come. The cornerstone programme for the disposal of waste materials is the Yucca Mountain Programme. Based on the Nuclear Waste Policy Act of 1982, as amended in 1987, it has been the United States' policy to develop a geological repository for the permanent disposal of radioactive waste materials. This presentation will discuss the process and strategy leading to the present and will include the scientific and management activities required to support the recent Viability Assessment. Also to be discussed are the timeline and milestones leading to the opening of the repository. The focus will be on the scientific and engineering studies required for a successful Site Recommendation, and then for a similarly successful License Application. Both of these activities will require considerable management efforts in addressing legal and regulatory issues. Finally, the presentation will discuss projections for the future operation of the facility, including emplacement projections, coupled with the required locations of nuclear materials. Additional scientific research and engineering studies will also be conducted to determine the longer-term viability of the facility, which is designed, by policy, for permanent storage. Retrievability is currently not an option, although access to the facility will be maintained for several decades. The focus of the discussion will be on the scientific and engineering advances made on understanding the natural systems for preventing migration of radionuclides, coupled with new developments in engineered systems in areas such as cask cladding, drip shields, and related materials engineering developments. The coupling of engineered and natural systems is designed to offer safety factors that are several orders of magnitude greater than what is estimated to be necessary

Non-Markovianity Measure Based on Brukner–Zeilinger Invariant Information for Unital Quantum Dynamical Maps

International Nuclear Information System (INIS)

He Zhi; Zhu Lie-Qiang; Li Li

2017-01-01

A non-Markovianity measure based on Brukner–Zeilinger invariant information to characterize non-Markovian effect of open systems undergoing unital dynamical maps is proposed. The method takes advantage of non-increasing property of the Brukner–Zeilinger invariant information under completely positive and trace-preserving unital maps. The simplicity of computing the Brukner–Zeilinger invariant information is the advantage of the proposed measure because of mainly depending on the purity of quantum state. The measure effectively captures the characteristics of non-Markovianity of unital dynamical maps. As some concrete application, we consider two typical non-Markovian noise channels, i.e., the phase damping channel and the random unitary channel to show the sensitivity of the proposed measure. By investigation, we find that the conditions of detecting the non-Markovianity for the phase damping channel are consistent with the results of existing measures for non-Markovianity, i.e., information flow, divisibility and quantum mutual information. However, for the random unitary channel non-Markovian conditions are same to that of the information flow, but is different from that of the divisibility and quantum mutual information. (paper)

Map Database for Surficial Materials in the Conterminous United States

Science.gov (United States)

Soller, David R.; Reheis, Marith C.; Garrity, Christopher P.; Van Sistine, D. R.

2009-01-01

The Earth's bedrock is overlain in many places by a loosely compacted and mostly unconsolidated blanket of sediments in which soils commonly are developed. These sediments generally were eroded from underlying rock, and then were transported and deposited. In places, they exceed 1000 ft (330 m) in thickness. Where the sediment blanket is absent, bedrock is either exposed or has been weathered to produce a residual soil. For the conterminous United States, a map by Soller and Reheis (2004, scale 1:5,000,000; http://pubs.usgs.gov/of/2003/of03-275/) shows these sediments and the weathered, residual material; for ease of discussion, these are referred to as 'surficial materials'. That map was produced as a PDF file, from an Adobe Illustrator-formatted version of the provisional GIS database. The provisional GIS files were further processed without modifying the content of the published map, and are here published.

40 CFR Table 4 to Subpart Bbbb of... - Model Rule-Class II Emission Limits for Existing Small Municipal Waste Combustion Unit a

Science.gov (United States)

2010-07-01

... Existing Small Municipal Waste Combustion Unit a 4 Table 4 to Subpart BBBB of Part 60 Protection of... NEW STATIONARY SOURCES Emission Guidelines and Compliance Times for Small Municipal Waste Combustion... Part 60—Model Rule—Class II Emission Limits for Existing Small Municipal Waste Combustion Unit a For...

Preliminary geologic map of the late Cenozoic sediments of the western half of the Pasco Basin

International Nuclear Information System (INIS)

Lillie, J.T.; Tallman, A.M.; Caggiano, J.A.

1978-09-01

The U.S. Department of Energy, through the Basalt Waste Isolation Program within the Rockwell Hanford Operations, is investigating the feasibility of terminal storage of radioactive waste in deep caverns constructed in Columbia River Basalt. This report represents a portion of the geological work conducted during fiscal year 1978 to assess the geological conditions in the Pasco Basin. The surficial geology of the western half of the Pasco Basin was studied and mapped in a reconnaissance fashion at a scale of 1:62,500. The map was produced through a compilation of existing geologic mapping publications and additional field data collected during the spring of 1978. The map was produced primarily to: (1) complement other mapping work currently being conducted in the Pasco Basin and in the region by Rockwell Hanford Operations and its subcontractors; and, (2) to provide a framework for more detailed late Cenozoic studies within the Pasco Basin. A description of procedures used to produce the surficial geologic map and geologic map units is summarized in this report

Development of a unit cell model for interim performance assessment of vitrified low level waste disposal

International Nuclear Information System (INIS)

Kline, N.W.

1995-09-01

The unit cell modeling approach has been developed and used in analysis of some design options for a vitrified low level waste disposal facility. The unit cell modeling approach is likely to be useful in interim performance assessment for the facility. The present unit cell model will probably need to be refitted in terms of some model parameters for the latter purpose. Two present disposal facility concepts differ in the length of a capillary barrier proposed to limit effective recharge through the top of the facility. Results of the study summarized herein suggest design of a capillary barrier which can reduce a recharge rate of 0.1 cm/yr by one or two orders of magnitude seems feasible for both concepts. A benchmark comparison of the unit cell model against a full facility model shows comparable predictive accuracy in less than one percent of the computer time. Results suggest that model parameters include capillary barrier performance, inter-canister spacing, rate of moisture withdrawal due to glass corrosion, contaminant inventory, and the well interceptor factor. It is also important that variations of waste form hydraulic parameters suggest that transport through the waste form is dominated by diffusion

Quaternary Geologic Map of the Lake of the Woods 4 Degrees x 6 Degrees Quadrangle, United States and Canada

Science.gov (United States)

Sado, Edward V.; Fullerton, David S.; Goebel, Joseph E.; Ringrose, Susan M.; Edited and Integrated by Fullerton, David S.

1995-01-01

The Quaternary Geologic Map of the Lake of the Woods 4 deg x 6 deg Quadrangle, United States and Canada, was mapped as part of the U.S. Geological Survey Quaternary Geologic Atlas of the United States map series (Miscellaneous Investigations Series I-1420, NM-15). The atlas was begun as an effort to depict the areal distribution of surficial geologic deposits and other materials that accumulated or formed during the past 2+ million years, the period that includes all activities of the human species. These materials are at the surface of the earth. They make up the 'ground' on which we walk, the 'dirt' in which we dig foundations, and the 'soil' in which we grow crops. Most of our human activity is related in one way or another to these surface materials that are referred to collectively by many geologists as regolith, the mantle of fragmental and generally unconsolidated material that overlies the bedrock foundation of the continent. The maps were compiled at 1:1,000,000 scale. This map is a product of collaboration of the Ontario Geological Survey, the Minnesota Geological Survey, the Manitoba Department of Energy and Mines, and the U.S. Geological Survey, and is designed for both scientific and practical purposes. It was prepared in two stages. First, separate maps and map explanations were prepared by the compilers. Second, the maps were combined, integrated, and supplemented by the editor. Map unit symbols were revised to a uniform system of classification and the map unit descriptions were prepared by the editor from information received from the compilers and from additional sources listed under Sources of Information. Diagrams accompanying the map were prepared by the editor. For scientific purposes, the map differentiates Quaternary surficial deposits on the basis of lithology or composition, texture or particle size, structure, genesis, stratigraphic relationships, engineering geologic properties, and relative age, as shown on the correlation diagram and

Quaternary Geologic Map of the Regina 4 Degrees x 6 Degrees Quadrangle, United States and Canada

Science.gov (United States)

Fullerton, David S.; Christiansen, Earl A.; Schreiner, Bryan T.; Colton, Roger B.; Clayton, Lee; Bush, Charles A.; Fullerton, David S.

2007-01-01

For scientific purposes, the map differentiates Quaternary surficial deposits and materials on the basis of clast lithology or composition, matrix texture or particle size, structure, genesis, stratigraphic relations, engineering geologic properties, and relative age, as shown on the correlation diagram and indicated in the 'Description of Map Units'. Deposits of some constructional landforms, such as end moraines, are distinguished as map units. Deposits of erosional landforms, such as outwash terraces, are not distinguished, although glaciofluvial, ice-contact, fluvial, and lacustrine deposits that are mapped may be terraced. Differentiation of sequences of fluvial and glaciofluvial deposits at this scale is not possible. For practical purposes, the map is a surficial materials map. Materials are distinguished on the basis of lithology or composition, texture or particle size, and other physical, chemical, and engineering characteristics. It is not a map of soils that are recognized and classified in pedology or agronomy. Rather, it is a generalized map of soils as recognized in engineering geology, or of substrata or parent materials in which pedologic or agronomic soils are formed. As a materials map, it serves as a base from which a variety of maps for use in planning engineering, land-use planning, or land-management projects can be derived and from which a variety of maps relating to earth surface processes and Quaternary geologic history can be derived.

Development of a master plan for industrial solid waste management

International Nuclear Information System (INIS)

Karamouz, M.; Zahraie, B.; Kerachian, R.; Mahjouri, N.; Moridi, A.

2006-01-01

Rapid industrial growth in the province of Khuzestan in the south west of Iran has resulted in disposal of about 1750 tons of solid waste per day. Most of these industrial solid wastes including hazardous wastes are disposed without considering environmental issues. This has contributed considerably to the pollution of the environment. This paper introduces a framework in which to develop a master plan for industrial solid waste management. There are usually different criteria for evaluating the existing solid waste pollution loads and how effective the management schemes are. A multiple criteria decision making technique, namely Analytical Hierarchy Process, is used for ranking the industrial units based on their share in solid waste related environmental pollution and determining the share of each unit in total solid waste pollution load. In this framework, a comprehensive set of direct, indirect, and supporting projects are proposed for solid waste pollution control. The proposed framework is applied for industrial solid waste management in the province of Khuzestan in Iran and a databank including GIS based maps of the study area is also developed. The results have shown that the industries located near the capital city of the province, Ahwaz, produce more than 32 percent of the total solid waste pollution load of the province. Application of the methodology also has shown that it can be effectively used for development of the master plan and management of industrial solid wastes

Operable Unit 3-13, Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) Waste Management Plan

International Nuclear Information System (INIS)

G. L. Schwendiman

2006-01-01

This Waste Management Plan describes waste management and waste minimization activities for Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory. The waste management activities described in this plan support the selected response action presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. This plan identifies the waste streams that will be generated during implementation of the remedial action and presents plans for waste minimization, waste management strategies, and waste disposition

Processes for CO2 capture. Context of thermal waste treatment units. State of the art. Extended abstract

International Nuclear Information System (INIS)

Lopez, A.; Roizard, D.; Favre, E.; Dufour, A.

2013-01-01

For most of industrial sectors, Greenhouse Gases (GHG) such as carbon dioxide (CO 2 ) are considered as serious pollutants and have to be controlled and treated. The thermal waste treatment units are part of industrial CO 2 emitters, even if they represent a small part of emissions (2,5 % of GHG emissions in France) compared to power plants (13 % of GHG emissions in France, one third of worldwide GHG emissions) or shaper industries (20 % of GHG emissions in France). Carbon Capture and Storage (CCS) can be a solution to reduce CO 2 emissions from industries (power plants, steel and cement industries...). The issues of CCS applied to thermal waste treatment units are quite similar to those related to power plants (CO 2 flow, flue gas temperature and pressure conditions). The problem is to know if the CO 2 produced by waste treatment plants can be captured thanks to the processes already available on the market or that should be available by 2020. It seems technically possible to adapt CCS post-combustion methods to the waste treatment sector. But on the whole, CCS is complex and costly for a waste treatment unit offering small economies of scale. However, regulations concerning impurities for CO 2 transport and storage are not clearly defined at the moment. Consequently, specific studies must be achieved in order to check the technical feasibility of CCS in waste treatment context and clearly define its cost. (authors)

Use of electromagnetic terrain conductivity measurements to map liquid hazardous waste migration in groundwater

International Nuclear Information System (INIS)

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

1983-11-01

Electromagnetic conductivity measurements have been used to map apparent ground conductivity in the vicinity of a liquid hazardous waste disposal site. An area of approximately 12 ha (30 acres) was surveyed. Approximately 600 conductivity measurements were obtained to prepare a conductivity map of the site. Conductivity measurments in the area correlate with specific conductance measurements of surface and groundwater samples. Contouring of the conductivity data showed the precise location of contaminant migration pathways in the subsurface. A complex contaminant plume was defined by the conductivity survey. Conductivity values obtained reflected anisotropic characteristics related to local bedrock structure. Anisotropy characteristics and the use of different instrument configurations indicated semiquantitatively the depth of the high conductivity zone and the direction of flow

Detection and mapping of buried waste

International Nuclear Information System (INIS)

Stahl, G.; Odenweller, J.; Huff, D.

1996-01-01

A major environmental concern today is the characterization, remediation, and monitoring of Federal waste sites, such as those operated by the Department of Energy (DOE). A significant amount of hazardous waste is buried at known sites on DOE reservations. Determining the exact location of buried waste trenches is an important step in the characterization and remediation of these sites. Remotely sensed imagery offers a rich source of information for accomplishing this task. This paper presents a case study conducted at Solid Waste Storage Area 4 (SWSA 4) at Oak Ridge National Laboratory. Historical aerial photography and recently collected multispectral imagery were analyzed to determine the precise locations of the buried trenches. A comparison of the results to recent ground measurements indicates the strengths and weaknesses of the remote sensing approach. Further analysis of these ground data also provides an understanding of the phenomenology that gives rise to the imagery signatures associated with the trenches. Application of these techniques can significantly reduce the costs of site remediation. By knowing the trench locations precisely, rather than the general locations, remediation alternatives to contain and isolate the waste materials can be tailored appropriately

Preliminary geologic map of the Lathrop Wells volcanic center

International Nuclear Information System (INIS)

Crowe, B.; Harrington, C.; McFadden, L.; Perry, F.; Wells, S.; Turrin, B.; Champion, D.

1988-12-01

A preliminary geologic map has been compiled for the bedrock geology of the Lathrop Wells volcanic center. The map was completed through use of a combination of stereo photographic interpretation and field mapping on color aerial photographs. These photographs (scale 1:4000) were obtained from American Aerial Surveys, Inc. They were flown on August 18, 1987, at the request of the Yucca Mountain Project (then Nevada Nuclear Waste Storage Investigations). The photographs are the Lathrop Wells VC-Area 25 series, numbers 1--32. The original negatives for these photographs are on file with American Aerial Surveys, Inc. Copies of the negatives have been archived at the Los Alamos National Laboratory, Group N-5. The preliminary geologic map is a bedrock geologic map. It does not show alluvial deposits, eolian sands, or scoria fall deposits from the youngest eruptive events. The units will be compiled on separate maps when the geomorphic and soils studies are more advanced

Grout Treatment Facility dangerous waste permit application

International Nuclear Information System (INIS)

1988-01-01

This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 14 Appendices. Topics include Engineering Drawings, Maps, Roads, Toxicity Testing, and Pilot-Scale Testing

Hanford Central Waste Complex: Radioactive mixed waste storage facility dangerous waste permit application

International Nuclear Information System (INIS)

1991-10-01

The Hanford Site is owned by the US Government and operated by the US Department of Energy Field Office, Richland. The Hanford Site manages and produces dangerous waste and mixed waste (containing both radioactive and dangerous components). The dangerous waste is regulated in accordance with the Resource Conversation and Recovery Act of 1976 and the State of Washington Hazardous Waste Management Act of 1976. The radioactive component of mixed waste is interpreted by the US Department of Energy to be regulated under the Atomic Energy Act of 1954; the nonradioactive dangerous component of mixed waste is interpreted to be regulated under the Resource Conservation and Recovery Act of 1976 and Washington Administrative Code 173--303. Westinghouse Hanford Company is a major contractor to the US Department of Energy Field Office, Richland and serves as co-operator of the Hanford Central Waste Complex. The Hanford Central Waste Complex is an existing and planned series of treatment, storage, and/or disposal units that will centralize the management of solid waste operations at a single location on the Hanford facility. The Hanford Central Waste Complex units include the Radioactive Mixed Waste Storage Facility, the unit addressed by this permit application, and the Waste Receiving and Processing Facility. The Waste Receiving and Processing Facility is covered in a separate permit application submittal

Experience in the United States with a secondary resource curriculum on ''Science, society and America's nuclear waste''

International Nuclear Information System (INIS)

King, G.P.

1994-01-01

The nuclear power and nuclear waste situation in the Usa, is first reviewed. In order to enhance information concerning these topics among pupils and teachers, a resource curriculum, 'Science, society, and America's Nuclear Waste', was developed by teachers for teachers; it consists of four units: nuclear waste, ionizing radiation, the nuclear waste policy act, and the waste management system. It has been well received by teachers. Within nine months after its national introduction, 350000 teacher and student curriculum documents were requested by teachers from all 50 states. Requests have been also received from 250 foreign colleges and universities

Litter Control, Waste Management, and Recycling Resource Unit, K-6. Bulletin 1722.

Science.gov (United States)

Louisiana State Dept. of Education, Baton Rouge.

This unit provides elementary teachers with ideas for assisting their students in developing an understanding and appreciation of sound resource use. It contains projects and activities that focus on both the litter problem and on waste management solutions. These materials can be adapted and modified to accommodate different grade levels and…

Disposal of radioactive wastes arising in the United Kingdom from the peaceful uses of atomic energy

CERN Document Server

Bryant, P M

1971-01-01

This paper describes United Kingdom policy in relation to radioactive waste and summarises the relevant legislation ad methods of control. Data are given on the amounts of radioactivity discharged as waste from establishments of the United Kingdom Atomic Energy Authority, the nuclear power stations operated by the Electricity Generating Boards and other users of radioactive materials. Studies of the behaviour of radioactivity in the environment are reported with particular reference to food chains and other potential sources of irradiation of the public. The results of environmental monitoring are presented and estimates are made of radiation doses received by individual members of the public and larger population groups as a result of waste disposal. It is concluded that the doses received are all within the appropriate limits recommended by the International Commission on Radiological Protection, and in most cases are trivial.

Development of the geologic waste disposal programme in the United States of America

International Nuclear Information System (INIS)

Coffman, F.E.; Ballard, W.W.; Carbiener, W.A.

1983-01-01

Although alternative concepts are being studied as future options, over at least the next few decades the United States of America is committed to the disposal of commercially generated high-level and transuranic nuclear waste (HLW and TRU) in mined geologic repositories. A 10,000-year minimum isolation period is sought. Responsibility for the management and disposal of United States nuclear waste, in accordance with standards and regulations established, respectively, by the Environmental Protection Agency (EPA) and the Nuclear Regulatory Commission (NRC), resides with the Department of Energy (DOE). The DOE National Waste Terminal Storage (NWTS) Program has been implemented to provide the facilities and develop the requisite technology for the disposal of HLW and TRU. The NWTS Program is highly structured, adequately funded, and realistically scheduled. The timely realization of its objectives is basic to the furtherance of the new national energy policy being defined by President Reagan and the United States Congress. The first NWTS repository is scheduled to be operational as early as 1998. The host-rock formation, selected on the basis of the results of at-depth investigations via exploratory shafts to be sunk in 1983-1985 at three potential sites previously extensively characterized by surface techniques, will be either basalt, volcanic tuff, or domed or bedded salt. Selection of one site in these formations will not necessarily disqualify others. Also, screening studies of granitic formations in the United States for the siting of later, regionally located repositories are currently being conducted. Each NWTS repository will be licensed by the NRC. The first application for a construction authorization will probably be submitted in 1988. The application will be submitted for a site to be selected in 1987

Closure Report for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Tobiason, D. S.

2002-01-01

This Closure Report (CR) has been prepared for the Area 25 Contaminated Waste Dumps (CWD), Corrective Action Unit (CAU) 143 in accordance with the Federal Facility Agreement and Consent Order [FFACO] (FFACO, 1996) and the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 143: Area 25, Contaminated Waste Dumps, Nevada Test Site, Nevada. CAU 143 consists of two Corrective Action Sites (CASs): 25-23-09 CWD No.1, and 25-23-03 CWD No.2. The Area 25 CWDs are historic disposal units within the Area 25 Reactor Maintenance, Assembly, and Disassembly (R-MAD), and Engine Maintenance, Assembly, and Disassembly (E-MAD) compounds located on the Nevada Test Site (NTS). The R-MAD and E-MAD facilities originally supported a portion of the Nuclear Rocket Development Station in Area 25 of the NTS. CWD No.1 CAS 25-23-09 received solid radioactive waste from the R-MAD Compound (East Trestle and West Trench Berms) and 25-23-03 CWD No.2 received solid radioactive waste from the E-MAD Compound (E-MAD Trench)

Some activities in the United States concerning the physics aspects of actinide waste recycling

International Nuclear Information System (INIS)

Raman, S.

1975-01-01

Reactor types being considered in the United States for the purpose of actinide waste recycling are discussed briefly. The reactor types include thermal reactors operating on the 3.3 percent 235 U-- 238 U and the 233 U-- 232 Th fuel cycles, liquid metal fast breeder reactors, reactors fueled entirely by actinide wastes, gaseous fuel reactors, and fusion reactors. Cross section measurements in progress or planned toward providing basic data for testing the recycle concept are also discussed

Mitigation action plan for liquid waste sites in the 100-BC-1, 100-DR-1, and 100-HR-1 units

International Nuclear Information System (INIS)

Weiss, S.G.

1996-05-01

A Record of Decision (ROD) was issued for remediation of waste sites in the 100-BC-1, 100-DR-1, and 100-HR-1 Operable Units in the 100 Area of the Hanford Site. This Mitigation Action Plan (MAP) explains how mitigation measures for these remedial activities will be planned and implemented. The new activities planned in the ROD are not anticipated to result in releases of hazardous substances and will minimize disturbance of currently undisturbed areas. However, certain actions required by the ROD may result in the redisturbance of areas of recovering vegetation. This MAP presents a strategy for limiting disturbances and identifies an opportunity for revegetating a previously disturbed site; the knowledge gained from this demonstration project can be applied to final revegetation of the rest of the remediated sites and sites disturbed during cleanup when remediation of an area is completed. This work will be conducted in coordination with the Natural Resource Trustees Council and Native American Tribes to help minimize impacts to natural resources and cultural resources from project activities and to restore the remediated sites to an appropriate level of habitat

Analisis Waste dalam Aliran Material Internal dengan Value Stream Mapping Pada PT XYZ

Directory of Open Access Journals (Sweden)

Gita Ayu

2012-06-01

Full Text Available The main focus of the research is excess inventory and motion waste which commonly occur in warehouse and production floor. This research is carried out to minimize the average level and eliminate unnecessary motions, with consideration of electronic pull and traceability system characteristics. Product X,the highest-selling product, is the object of this research. To identify the current condition, the current state Value Stream Mapping (VSM is developed as the basis to arrange improvement plan to minimize the wastes. Safety stock is determined through average and maximum consumption difference; and reorder point is determined to comply with pull approach. Average inventory level is calculated using continuous review method. The simulation was conducted and it was shown that 8.29 minutes is the maximum lateness. Thus, safety stock and reorder point are adjusted accordingly to anticipate stockout due to lateness. The improvement of process cycle efficiency is shown to increase from 4.1 % to 5.1 % as projected in future state VSM.

Geochemical landscapes of the conterminous United States; new map presentations for 22 elements

Science.gov (United States)

Gustavsson, N.; Bolviken, B.; Smith, D.B.; Severson, R.C.

2001-01-01

Geochemical maps of the conterminous United States have been prepared for seven major elements (Al, Ca, Fe, K, Mg, Na, and Ti) and 15 trace elements (As, Ba, Cr, Cu, Hg, Li, Mn, Ni, Pb, Se, Sr, V, Y, Zn, and Zr). The maps are based on an ultra low-density geochemical survey consisting of 1,323 samples of soils and other surficial materials collected from approximately 1960-1975. The data were published by Boerngen and Shacklette (1981) and black-and-white point-symbol geochemical maps were published by Shacklette and Boerngen (1984). The data have been reprocessed using weighted-median and Bootstrap procedures for interpolation and smoothing.

Food waste disposal units in UK households: the need for policy intervention.

Science.gov (United States)

Iacovidou, Eleni; Ohandja, Dieudonne-Guy; Voulvoulis, Nikolaos

2012-04-15

The EU Landfill Directive requires Member States to reduce the amount of biodegradable waste disposed of to landfill. This has been a key driver for the establishment of new waste management options, particularly in the UK, which in the past relied heavily on landfill for the disposal of municipal solid waste (MSW). MSW in the UK is managed by Local Authorities, some of which in a less conventional way have been encouraging the installation and use of household food waste disposal units (FWDs) as an option to divert food waste from landfill. This study aimed to evaluate the additional burden to water industry operations in the UK associated with this option, compared with the benefits and related savings from the subsequent reductions in MSW collection and disposal. A simple economic analysis was undertaken for different FWD uptake scenarios, using the Anglian Region as a case study. Results demonstrated that the significant savings from waste collection arising from a large-scale uptake of FWDs would outweigh the costs associated with the impacts to the water industry. However, in the case of a low uptake, such savings would not be enough to cover the increased costs associated with the wastewater provision. As a result, this study highlights the need for policy intervention in terms of regulating the use of FWDs, either promoting them as an alternative to landfill to increase savings from waste management, or banning them as a threat to wastewater operations to reduce potential costs to the water industry. Copyright © 2012 Elsevier B.V. All rights reserved.

Technology and place: A geography of waste-to-energy in the United States

Science.gov (United States)

Howell, Jordan Patterson

The adoption of technologies differs across space, for reasons attributed to economics, politics, and culture, but also due to limitations imposed by both the physical environment and the technology itself. This dissertation considers the case of waste-to-energy (WTE) incinerators in the United States, and asks why this technology is used in some places but rejected in others. The answer to this simple question is remarkably complex, as understandings and arguments about technology and the environment are mobilized differently by various actors to champion, oppose, or in some cases remain ambivalent about the installation and operation of WTE facilities. In this dissertation I explore the geography of WTE incineration in the United States since the 19th century. Informed by the insights of actor-network theory and the social construction of technology school, I employ the tools of discourse analysis to examine published and unpublished statements, papers, project studies, policy briefs, and archival materials generated alongside the development of WTE facilities in the United States, considering the specific case studies discussed below but also WTE technology in general. I look at federal, state, and local environmental agency documents as well as the papers of consulting firms, environmental and industry advocacy groups, and private companies. I also devote significant attention to the analysis of news media outlets in communities where WTE facilities are located or have been considered. In addition to these literal texts, I examine non-written and visual materials associated with WTE facilities, including films, websites, signage and logos, advertising campaigns, facility architecture, and artwork, as well as more abstract `texts' such as industry conferences, trade-show handouts, promotional materials, and academic and industry research programs. I build on this textual analysis with observations of WTE facilities in action. After an introductory chapter, I

Site-specific waste management instruction for the 100-KR-4 Operable Unit drilling. Revision 1

International Nuclear Information System (INIS)

Hadley, J.T.

1996-08-01

This site-specific waste management instruction provides guidance for the management of waste generated as a result of groundwater well installations in the 100-KR-4 Operable Unit (OU). The well installations are necessary to implement the Remedial Action (RA) option (pump-and-treat using ion exchange) to prevent discharge of hexavalent chromium at levels above those considered protective of aquatic life in the Columbia River and riverbed sediments

Some activities in the United States concerning the physics aspects of actinide waste recycling

International Nuclear Information System (INIS)

Raman, S.

1976-01-01

This review paper briefly discusses the reactor types being considered in the United States for the purpose of actinide waste recycling. The reactor types include thermal reactors operating on the 3.3% 235 U- 238 U and the 233 U- 232 Th fuel cycles, liquid metal fast breeder reactors, reactors fueled entirely by actinide wastes, gaseous fuel reactors and fusion reactors. This paper also discusses cross section measurements in progress or planned toward providing basic data for testing the recycle concept. (author)

Radioactive solid waste inventories at United States Department of Energy burial and storage sites

International Nuclear Information System (INIS)

Watanabe, T.

1986-06-01

Radioactive solid waste inventories are given for United States Department of Energy (DOE) burial and storage sites. These data are obtained from the Solid Waste Information Management System (SWIMS) and reflect the inventories as of the end of the calendar year 1985. This report differs from previous issues in that the data cutoff date is December 31, 1985, rather than the fiscal year end. Another difference from previous issues is that data for the TRU categories 1 and 6 have been omitted

High-level radioactive waste management in the United States. Background and status: 1996

International Nuclear Information System (INIS)

Dyer, J.R.

1996-01-01

The US high-level radioactive waste disposal program is investigating a site at Yucca Mountain, Nevada, to determine whether or not it is a suitable location for the development of a deep mined geologic repository. At this time, the US program is investigating a single site, although in the past, the program involved successive screening and comparison of alternate locations. The United States civilian reactor programs do not reprocess spent fuel; the high-level waste repository will be designed for the emplacement or spent fuel and a limited amount of vitrified high-level wastes from previous reprocessing in the US. The legislation enabling the US program also contains provisions for a Monitored Retrievable Storage facility, which could provide temporary storage of spent fuel accepted for disposal, and improve the flexibility of the repository development schedule

Evaluation on radioactive waste disposal amount of Kori Unit 1 reactor vessel considering cutting and packaging methods

International Nuclear Information System (INIS)

Choi, Yu Jong; Lee, Seong Cheol; Kim, Chang Lak

2016-01-01

Decommissioning of nuclear power plants has become a big issue in South Korea as some of the nuclear power plants in operation including Kori unit 1 and Wolsung unit 1 are getting old. Recently, Wolsung unit 1 received permission to continue operation while Kori unit 1 will shut down permanently in June 2017. With the consideration of segmentation method and disposal containers, this paper evaluated final disposal amount of radioactive waste generated from decommissioning of the reactor pressure vessel in Kori unit 1 which will be decommissioned as the first in South Korea. The evaluation results indicated that the final disposal amount from the top and bottom heads of the reactor pressure vessel with hemisphere shape decreased as they were cut in smaller more effectively than the cylindrical part of the reactor pressure vessel. It was also investigated that 200 L and 320 L radioactive waste disposal containers used in Kyung-Ju disposal facility had low payload efficiency because of loading weight limitation

Mapping the world: cartographic and geographic visualization by the United Nations Geospatial Information Section (formerly Cartographic Section)

Science.gov (United States)

Kagawa, Ayako; Le Sourd, Guillaume

2018-05-01

United Nations Secretariat activities, mapping began in 1946, and by 1951, the need for maps increased and an office with a team of cartographers was established. Since then, with the development of technologies including internet, remote sensing, unmanned aerial systems, relationship database management and information systems, geospatial information provides an ever-increasing variation of support to the work of the Organization for planning of operations, decision-making and monitoring of crises. However, the need for maps has remained intact. This presentation aims to highlight some of the cartographic representation styles over the decades by reviewing the evolution of selected maps by the office, and noting the changing cognitive and semiotic aspects of cartographic and geographic visualization required by the United Nations. Through presentation and analysis of these maps, the changing dynamics of the Organization in information management can be reflected, with a reminder of the continuing and expanding deconstructionist role of a cartographer, now geospatial information management experts.

Quaternary Geologic Map of the Lake Superior 4° x 6° Quadrangle, United States and Canada

Data.gov (United States)

Department of the Interior — The Quaternary Geologic Map of the Lake Superior 4° x 6° Quadrangle was mapped as part of the Quaternary Geologic Atlas of the United States. The atlas was begun as...

Geodesy- and geology-based slip-rate models for the Western United States (excluding California) national seismic hazard maps

Science.gov (United States)

Petersen, Mark D.; Zeng, Yuehua; Haller, Kathleen M.; McCaffrey, Robert; Hammond, William C.; Bird, Peter; Moschetti, Morgan; Shen, Zhengkang; Bormann, Jayne; Thatcher, Wayne

2014-01-01

The 2014 National Seismic Hazard Maps for the conterminous United States incorporate additional uncertainty in fault slip-rate parameter that controls the earthquake-activity rates than was applied in previous versions of the hazard maps. This additional uncertainty is accounted for by new geodesy- and geology-based slip-rate models for the Western United States. Models that were considered include an updated geologic model based on expert opinion and four combined inversion models informed by both geologic and geodetic input. The two block models considered indicate significantly higher slip rates than the expert opinion and the two fault-based combined inversion models. For the hazard maps, we apply 20 percent weight with equal weighting for the two fault-based models. Off-fault geodetic-based models were not considered in this version of the maps. Resulting changes to the hazard maps are generally less than 0.05 g (acceleration of gravity). Future research will improve the maps and interpret differences between the new models.

Elaboration Of A Classification Of Geomorphologic Units And The Basis Of A Digital Data-Base For Establishing Geomorphologic Maps In Egypt

International Nuclear Information System (INIS)

EI Gammal, E.A.; Cherif, O.H.; Abdel Aleem, E.

2003-01-01

A database for the classification and description of basic geomorphologic land form units has been prepared for establishing geomorphologic maps in Egyptian terrains. This database includes morpho-structural, lithological, denudational and depositional units. The database.is included in tables with proper coding to be used for establishing automatically the color, symbols and legend of the maps. Also the system includes description of various geomorphic units. The system is designed to be used with the ARC Map software. The AUTOCAD 2000 software has been used to trace the maps. The database has been applied to produce five new geomorphologic maps with a scale of I: 100 000. These are: Wadi Feiran Sheet, Wadi Kid Sheet, Gabal Katherina Sheet in South Sinai, Shelattein area (South Eastern Desert) and Baharia Oasis area (Western Desert)

Applying Value Stream Mapping to reduce food losses and wastes in supply chains: A systematic review.

Science.gov (United States)

De Steur, Hans; Wesana, Joshua; Dora, Manoj K; Pearce, Darian; Gellynck, Xavier

2016-12-01

The interest to reduce food losses and wastes has grown considerably in order to guarantee adequate food for the fast growing population. A systematic review was used to show the potential of Value Stream Mapping (VSM) not only to identify and reduce food losses and wastes, but also as a way to establish links with nutrient retention in supply chains. The review compiled literature from 24 studies that applied VSM in the agri-food industry. Primary production, processing, storage, food service and/or consumption were identified as susceptible hotspots for losses and wastes. Results further revealed discarding and nutrient loss, most especially at the processing level, as the main forms of loss/waste in food, which were adapted to four out of seven lean manufacturing wastes (i.e. defect, unnecessary inventory, overproduction and inappropriate processing). This paper presents the state of the art of applying lean manufacturing practices in the agri-food industry by identifying lead time as the most applicable performance indicator. VSM was also found to be compatible with other lean tools such as Just-In-Time and 5S which are continuous improvement strategies, as well as simulation modelling that enhances adoption. In order to ensure successful application of lean practices aimed at minimizing food or nutrient losses and wastes, multi-stakeholder collaboration along the entire food supply chain is indispensable. Copyright © 2016 Elsevier Ltd. All rights reserved.

Geology Report: Area 3 Radioactive Waste Management Site DOE/Nevada Test Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2006-07-01

Surficial geologic studies near the Area 3 Radioactive Waste Management Site (RWMS) were conducted as part of a site characterization program. Studies included evaluation of the potential for future volcanism and Area 3 fault activity that could impact waste disposal operations at the Area 3 RWMS. Future volcanic activity could lead to disruption of the Area 3 RWMS. Local and regional studies of volcanic risk indicate that major changes in regional volcanic activity within the next 1,000 years are not likely. Mapped basalts of Paiute Ridge, Nye Canyon, and nearby Scarp Canyon are Miocene in age. There is a lack of evidence for post-Miocene volcanism in the subsurface of Yucca Flat, and the hazard of basaltic volcanism at the Area 3 RWMS, within the 1,000-year regulatory period, is very low and not a forseeable future event. Studies included a literature review and data analysis to evaluate unclassified published and unpublished information regarding the Area 3 and East Branch Area 3 faults mapped in Area 3 and southern Area 7. Two trenches were excavated along the Area 3 fault to search for evidence of near-surface movement prior to nuclear testing. Allostratigraphic units and fractures were mapped in Trenches ST02 and ST03. The Area 3 fault is a plane of weakness that has undergone strain resulting from stress imposed by natural events and underground nuclear testing. No major vertical displacement on the Area 3 fault since the Early Holocene, and probably since the Middle Pleistocene, can be demonstrated. The lack of major displacement within this time frame and minimal vertical extent of minor fractures suggest that waste disposal operations at the Area 3 RWMS will not be impacted substantially by the Area 3 fault, within the regulatory compliance period. A geomorphic surface map of Yucca Flat utilizes the recent geomorphology and soil characterization work done in adjacent northern Frenchman Flat. The approach taken was to adopt the map unit boundaries (line

Geology Report: Area 3 Radioactive Waste Management Site DOE/Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

NSTec Environmental Management

2006-01-01

Surficial geologic studies near the Area 3 Radioactive Waste Management Site (RWMS) were conducted as part of a site characterization program. Studies included evaluation of the potential for future volcanism and Area 3 fault activity that could impact waste disposal operations at the Area 3 RWMS. Future volcanic activity could lead to disruption of the Area 3 RWMS. Local and regional studies of volcanic risk indicate that major changes in regional volcanic activity within the next 1,000 years are not likely. Mapped basalts of Paiute Ridge, Nye Canyon, and nearby Scarp Canyon are Miocene in age. There is a lack of evidence for post-Miocene volcanism in the subsurface of Yucca Flat, and the hazard of basaltic volcanism at the Area 3 RWMS, within the 1,000-year regulatory period, is very low and not a forseeable future event. Studies included a literature review and data analysis to evaluate unclassified published and unpublished information regarding the Area 3 and East Branch Area 3 faults mapped in Area 3 and southern Area 7. Two trenches were excavated along the Area 3 fault to search for evidence of near-surface movement prior to nuclear testing. Allostratigraphic units and fractures were mapped in Trenches ST02 and ST03. The Area 3 fault is a plane of weakness that has undergone strain resulting from stress imposed by natural events and underground nuclear testing. No major vertical displacement on the Area 3 fault since the Early Holocene, and probably since the Middle Pleistocene, can be demonstrated. The lack of major displacement within this time frame and minimal vertical extent of minor fractures suggest that waste disposal operations at the Area 3 RWMS will not be impacted substantially by the Area 3 fault, within the regulatory compliance period. A geomorphic surface map of Yucca Flat utilizes the recent geomorphology and soil characterization work done in adjacent northern Frenchman Flat. The approach taken was to adopt the map unit boundaries (line

Application of the Lean Office philosophy and mapping of the value stream in the process of designing the banking units of a financial company

Directory of Open Access Journals (Sweden)

Nelson Antônio Calsavara

2016-09-01

Full Text Available The purpose of this study is to conduct a critical analysis of the effects of Lean Office on the design process of the banking units of a financial company and how the implementation of this philosophy may contribute to productivity, thus reducing implementation time. A literature review of the Toyota Production System was conducted, as well as studies on its methods, with advancement to lean thinking and consistent application of Lean philosophies in services and Office. A bibliographic and documentary survey of the Lean processes and procedures for opening bank branches was taken. A Current State Map was developed, modeling the current operating procedures. Soon after the identification and analysis of waste, proposals were presented for reducing deadlines and eliminating and grouping stages, with consequent development of the Future State Map, implementation and monitoring of stages, and the measurement of estimated time gains in operation, demonstrating an estimated 45% reduction, in days, from start to end of the process, concluding that the implementation of the Lean Office philosophy contributed to the process.

Waste Encapsulation and Storage Facility (WESF) Dangerous Waste Training Plan (DWTP)

International Nuclear Information System (INIS)

SIMMONS, F.M.

2000-01-01

This Waste Encapsulation Storage Facility (WESF) Dangerous Waste Training Plan (DWTP) applies to personnel who perform work at, or in support of WESF. The plan, along with the names of personnel, may be given to a regulatory agency inspector upon request. General workers, subcontractors, or visiting personnel who have not been trained in the management of dangerous wastes must be accompanied by an individual who meets the requirements of this training plan. Dangerous waste management includes handling, treatment, storage, and/or disposal of dangerous and/or mixed waste. Dangerous waste management units covered by this plan include: less-than-90-day accumulation area(s); pool cells 1-8 and 12 storage units; and process cells A-G storage units. This training plan describes general requirements, worker categories, and provides course descriptions for operation of the WESF permitted miscellaneous storage units and the Less-than-90-Day Accumulation Areas

A Global Survey and Interactive Map Suite of Deep Underground Facilities; Examples of Geotechnical and Engineering Capabilities, Achievements, Challenges: (Mines, Shafts, Tunnels, Boreholes, Sites and Underground Facilities for Nuclear Waste and Physics R&D)

Science.gov (United States)

Tynan, M. C.; Russell, G. P.; Perry, F.; Kelley, R.; Champenois, S. T.

2017-12-01

This global survey presents a synthesis of some notable geotechnical and engineering information reflected in four interactive layer maps for selected: 1) deep mines and shafts; 2) existing, considered or planned radioactive waste management deep underground studies, sites, or disposal facilities; 3) deep large diameter boreholes, and 4) physics underground laboratories and facilities from around the world. These data are intended to facilitate user access to basic information and references regarding deep underground "facilities", history, activities, and plans. In general, the interactive maps and database [http://gis.inl.gov/globalsites/] provide each facility's approximate site location, geology, and engineered features (e.g.: access, geometry, depth, diameter, year of operations, groundwater, lithology, host unit name and age, basin; operator, management organization, geographic data, nearby cultural features, other). Although the survey is not all encompassing, it is a comprehensive review of many of the significant existing and historical underground facilities discussed in the literature addressing radioactive waste management and deep mined geologic disposal safety systems. The global survey is intended to support and to inform: 1) interested parties and decision makers; 2) radioactive waste disposal and siting option evaluations, and 3) safety case development as a communication tool applicable to any mined geologic disposal facility as a demonstration of historical and current engineering and geotechnical capabilities available for use in deep underground facility siting, planning, construction, operations and monitoring.

Unit costs of waste management operations

International Nuclear Information System (INIS)

Kisieleski, W.E.; Folga, S.M.; Gillette, J.L.; Buehring, W.A.

1994-04-01

This report provides estimates of generic costs for the management, disposal, and surveillance of various waste types, from the time they are generated to the end of their institutional control. Costs include monitoring and surveillance costs required after waste disposal. Available data on costs for the treatment, storage, disposal, and transportation of spent nuclear fuel and high-level radioactive, low-level radioactive, transuranic radioactive, hazardous, mixed (low-level radioactive plus hazardous), and sanitary wastes are presented. The costs cover all major elements that contribute to the total system life-cycle (i.e., ''cradle to grave'') cost for each waste type. This total cost is the sum of fixed and variable cost components. Variable costs are affected by operating rates and throughput capacities and vary in direct proportion to changes in the level of activity. Fixed costs remain constant regardless of changes in the amount of waste, operating rates, or throughput capacities. Key factors that influence cost, such as the size and throughput capacity of facilities, are identified. In many cases, ranges of values for the key variables are presented. For some waste types, the planned or estimated costs for storage and disposal, projected to the year 2000, are presented as graphics

Chemical health risk assessment for hazardous and mixed waste management units at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

1992-09-01

The Lawrence Livermore National Laboratory (LLNL) operates three Hazardous Waste Management Facilities with 24 associated waste management units for the treatment and storage of hazardous and mixed wastes. These wastes are generated by research programs and support operations. The storage and treatment units are presently operated under interim status in accordance with the requirements of the US Envirorunental Protection Agency (US EPA) and the Department of Toxic Substances Control (DTSC), a division of the California Envirorunental Protection Agency (Cal/EPA). As required by the California Hazardous Waste Control Act and the Resource Conservation and Recovery Act (RCRA), LLNL ha s applied for a Part B permit to continue operating the storage and waste treatment facilities. As part of this permitting process, LLNL is required to conduct a health risk assessment (HRA) to examine the potential health impacts to the surrounding community from continued storage and treatment of hazardous and mixed wastes. analysis document presents the results of this risk assessment. An analysis of maximum credible chemical accidents is also included in Section 7.0. This HRA was prepared in accordance with procedures set forth by the California Air Pollution Control Officers Association (CAPCOA) ''Air Toxics Assessment Manual,'' CAPCOA guidelines for preparing risk assessments under the Air Toxic ''Hot Spots'' Act (AB 2588) and requirements of the US EPA. By following these procedures, this risk assessment presents a conservative analysis of a hypothetical Maximally Exposed Individual (MEI) using many worst-case assumptions that will not apply to an actual individual. As such, the risk estimates presented should be regarded as a worst-case estimate of any actual risk that may be present

Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0

Energy Technology Data Exchange (ETDEWEB)

Wickline, Alfred

2005-12-01

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) 137: Waste Disposal Sites. 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. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting

Tank waste remediation system dangerous waste training plan

International Nuclear Information System (INIS)

POHTO, R.E.

1999-01-01

This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by Lockheed Martin Hanford Corporation (LMHC) Tank Waste Remediation System (TWRS) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units operated by TWRS are: the Double-Shell Tank (DST) System (including 204-AR Waste Transfer Building), the 600 Area Purgewater Storage and the Effluent Treatment Facility. TSD Units undergoing closure are: the Single-Shell Tank (SST) System, 207-A South Retention Basin, and the 216-B-63 Trench

Process engineering design of pathological waste incinerator with an integrated combustion gases treatment unit.

Science.gov (United States)

Shaaban, A F

2007-06-25

Management of medical wastes generated at different hospitals in Egypt is considered a highly serious problem. The sources and quantities of regulated medical wastes have been thoroughly surveyed and estimated (75t/day from governmental hospitals in Cairo). From the collected data it was concluded that the most appropriate incinerator capacity is 150kg/h. The objective of this work is to develop the process engineering design of an integrated unit, which is technically and economically capable for incinerating medical wastes and treatment of combustion gases. Such unit consists of (i) an incineration unit (INC-1) having an operating temperature of 1100 degrees C at 300% excess air, (ii) combustion-gases cooler (HE-1) generating 35m(3)/h hot water at 75 degrees C, (iii) dust filter (DF-1) capable of reducing particulates to 10-20mg/Nm(3), (iv) gas scrubbers (GS-1,2) for removing acidic gases, (v) a multi-tube fixed bed catalytic converter (CC-1) to maintain the level of dioxins and furans below 0.1ng/Nm(3), and (vi) an induced-draft suction fan system (SF-1) that can handle 6500Nm(3)/h at 250 degrees C. The residence time of combustion gases in the ignition, mixing and combustion chambers was found to be 2s, 0.25s and 0.75s, respectively. This will ensure both thorough homogenization of combustion gases and complete destruction of harmful constituents of the refuse. The adequate engineering design of individual process equipment results in competitive fixed and operating investments. The incineration unit has proved its high operating efficiency through the measurements of different pollutant-levels vented to the open atmosphere, which was found to be in conformity with the maximum allowable limits as specified in the law number 4/1994 issued by the Egyptian Environmental Affairs Agency (EEAA) and the European standards.

Dose mapping in working space of KORI unit 1 using MCNPX code

Energy Technology Data Exchange (ETDEWEB)

Lee, C. W.; Shin, C. H.; Kim, J. G. [Hanyang University, Seoul (Korea, Republic of); Kim, S. Y. [Innovative Techonology Center for Radiation Safety, Seoul (Korea, Republic of)

2004-07-01

Radiation field analysis in nuclear power plant mainly depends on actual measurements. In this study, the analysis using computational calculation is performed to overcome the limits of measurement and provide the initial information for unfolding. The radiation field mapping is performed, which makes it possible to analyze the trends of the radiation filed for whole space. By using MCNPX code, containment building inside is modeled for KORI unit 1 cycle 21 under operation. Applying the neutron spectrum from the operating reactor as a radiation source, the ambient doses are calculated in the whole space, containment building inside, for neutron and photon fields. Dose mapping is performed for three spaces, 6{approx}20, 20{approx}44, 44{approx}70 ft from bottom of the containment building. The radiation distribution in dose maps shows the effects from structures and materials of components. With this dose maps, radiation field analysis contained the region near the detect position. The analysis and prediction are possible for radiation field from other radiation source or operating cycle.

Coal combustion waste management study

International Nuclear Information System (INIS)

1993-02-01

Coal-fired generation accounted for almost 55 percent of the production of electricity in the United States in 1990. Coal combustion generates high volumes of ash and flue gas desulfurization (FGD) wastes, estimated at almost 90 million tons. The amount of ash and flue gas desulfurization wastes generated by coal-fired power plants is expected to increase as a result of future demand growth, and as more plants comply with Title IV of the 1990 Clean Air Act Amendments. Nationwide, on average, over 30 percent of coal combustion wastes is currently recycled for use in various applications; the remaining percentage is ultimately disposed in waste management units. There are a significant number of on-site and off-site waste management units that are utilized by the electric utility industry to store or dispose of coal combustion waste. Table ES-1 summarizes the number of disposal units and estimates of waste contained at these unites by disposal unit operating status (i.e, operating or retired). Further, ICF Resources estimates that up to 120 new or replacement units may need to be constructed to service existing and new coal capacity by the year 2000. The two primary types of waste management units used by the industry are landfills and surface impoundments. Utility wastes have been exempted by Congress from RCRA Subtitle C hazardous waste regulation since 1980. As a result of this exemption, coal combustion wastes are currently being regulated under Subtitle D of RCRA. As provided under Subtitle D, wastes not classified as hazardous under Subtitle C are subject to State regulation. At the same time Congress developed this exemption, also known as the ''Bevill Exclusion,'' it directed EPA to prepare a report on coal combustion wastes and make recommendations on how they should be managed

Documentation for the 2014 update of the United States national seismic hazard maps

Science.gov (United States)

Petersen, Mark D.; Moschetti, Morgan P.; Powers, Peter M.; Mueller, Charles S.; Haller, Kathleen M.; Frankel, Arthur D.; Zeng, Yuehua; Rezaeian, Sanaz; Harmsen, Stephen C.; Boyd, Oliver S.; Field, Edward; Chen, Rui; Rukstales, Kenneth S.; Luco, Nico; Wheeler, Russell L.; Williams, Robert A.; Olsen, Anna H.

2014-01-01

The national seismic hazard maps for the conterminous United States have been updated to account for new methods, models, and data that have been obtained since the 2008 maps were released (Petersen and others, 2008). The input models are improved from those implemented in 2008 by using new ground motion models that have incorporated about twice as many earthquake strong ground shaking data and by incorporating many additional scientific studies that indicate broader ranges of earthquake source and ground motion models. These time-independent maps are shown for 2-percent and 10-percent probability of exceedance in 50 years for peak horizontal ground acceleration as well as 5-hertz and 1-hertz spectral accelerations with 5-percent damping on a uniform firm rock site condition (760 meters per second shear wave velocity in the upper 30 m, VS30). In this report, the 2014 updated maps are compared with the 2008 version of the maps and indicate changes of plus or minus 20 percent over wide areas, with larger changes locally, caused by the modifications to the seismic source and ground motion inputs.

PROFILE OF PLASTIC WATER BOTTLES WASTES PROCESSING BUSINESS UNIT FOR WASTE PICKERS

Directory of Open Access Journals (Sweden)

Herijanto P.

2017-09-01

Full Text Available Used plastic water bottles waste pickers can be categorized as one of the informal sector’s component. They work for themselves by picking up used water bottles and selling them to the waste collectors. The problem to be solved in this research is How the Most Appropriate Used Plastic Water Bottles Business Model for Waste Pickers Is that enables them to be categorized as formal sector. From the result of the interview with 120 waste pickers, 96 results were qualified to be analyzed. The interview was located in several waste collectors, which were visited by waste pickers at certain hours. The data were analyzed descriptively based on six business aspects. Specifically for production facilities, Quality Function Deployment (QFD and Value Engineering (VE analysis were performed. The results of the analysis indicate that the business is practicable for waste pickers and has the potential to enable them run a formal business sector.

Lean production design using value stream mapping and ergonomics approach for waste elimination on buffing panel upright process

Science.gov (United States)

Suryoputro, M. R.; Sari, A. D.; Burhanudin, R.; Sugarindra, M.

2017-12-01

This study discussed the implementation of ergonomics and value stream mapping issues to reduce the existing waste in the process of buffing upright panel in the XYZ music manufacturing company. Aimed to identify the 9 waste based on the identification in terms of production processes and ergonomic factors, namely environmental health and safety, defects, overproduction, waiting, not utilizing employee knowledge skill and ability, transportation, inventory, motion, and excess process. In addition, ergonomics factors were identified, for example posture using REBA, job safety analysis, and physical workload. This study results indicated that the process is having 21.4% of the potential dangers that could not be accepted and thus potentially lead to lost time. Continued with the physical workload, the score of % cardiovascular load value is still below 30%, which means that the physical workload is normal and allows the addition of work. Meanwhile, in the calculation of posture investigation, the REBA resulted that there was a motion waste identified on the edge buff machine and ryoto with the score of 10 and 8. In conclusion, the results shown that there were 20 overall waste produced, then thus waste were reduced based on the identification and discussion of proposed improvements.

Healthcare waste management: a case study from the National Health Service in Cornwall, United Kingdom

International Nuclear Information System (INIS)

Tudor, T.L.; Noonan, C.L.; Jenkin, L.E.T.

2005-01-01

This paper looks at steps taken towards the development of a 10-year strategy for the management of healthcare waste from the National Health Service (NHS) in Cornwall, United Kingdom. The major issues and challenges that affect the management of waste by the NHS, including its organisational structure and collection infrastructure, are outlined. The waste flows of the main acute medical site are detailed, using waste audits of domestic and clinical bags, redundant equipment, bulky waste, and special waste. Some of the common barriers to change, such as staff habits and public perceptions, are also identified. Recommendations are made with respect to improvements in the overall organisational infrastructure and increased localised control. The recommendations also centre around the formation of strategic partnerships, within the site, between sites and at the broader level between the NHS and its surrounding community. An important challenge to be overcome is the need to progress from the concept of 'waste management', to one of sustainable decision making regarding resource use, including methods of waste minimisation at the source and recycling. Staff training and awareness underpin several of the short and medium/long term solutions suggested to reduce the waste at the source and recover value from that produced. These measures could potentially reduce disposal quantities by as much as 20-30% (wt.) and costs by around 25-35%

A historical context of municipal solid waste management in the United States.

Science.gov (United States)

Louis, Garrick E

2004-08-01

Municipal solid waste management (MSWM) in the United States is a system comprised of regulatory, administrative, market, technology, and social subcomponents, and can only be understood in the context of its historical evolution. American cities lacked organized public works for street cleaning, refuse collection, water treatment, and human waste removal until the early 1800s. Recurrent epidemics forced efforts to improve public health and the environment. The belief in anticontagionism led to the construction of water treatment and sewerage works during the nineteenth century, by sanitary engineers working for regional public health authorities. This infrastructure was capital intensive and required regional institutions to finance and administer it. By the time attention turned to solid waste management in the 1880s, funding was not available for a regional infrastructure. Thus, solid waste management was established as a local responsibility, centred on nearby municipal dumps. George Waring of New York City organized solid waste management around engineering unit operations; including street sweeping, refuse collection, transportation, resource recovery and disposal. This approach was adopted nationwide, and was managed by City Departments of Sanitation. Innovations such as the introduction of trucks, motorized street sweepers, incineration, and sanitary landfill were developed in the following decades. The Resource Conservation and Recovery Act of 1976 (RCRA), is the defining legislation for MSWM practice in America today. It forced the closure of open dumps nationwide, and required regional planning for MSWM. The closure of municipal dumps caused a 'garbage crisis' in the late 1980s and early 1990s. Private companies assumed an expanded role in MSWM through regional facilities that required the transportation of MSW across state lines. These transboundary movements of MSW created the issue of flow control, in which the US Supreme Court affirmed the protection

High level waste transport and disposal cost calculations for the United Kingdom

International Nuclear Information System (INIS)

Nattress, P.C.; Ward, R.D.

1992-01-01

Commercial nuclear power has been generated in the United Kingdom since 1962, and throughout that time fuel has been reprocessed giving rise to high level waste. This has been managed by storing fission products and related wastes as highly active liquor, and more recently by a program of vitrification and storage of the glass blocks produced. Government policy is that vitrified high level waste should be stored for at least 50 years, which has the technical advantage of allowing the heat output rate of the waste to fall, making disposal easier and cheaper. Thus, there is no immediate requirement to develop a deep geological repository in the UK, but the nuclear companies do have a requirement to make financial provision out of current revenues for high level waste disposal at a future repository. In 1991 the interested organizations undertook a new calculation of costs for such provisions, which is described here. The preliminary work for the calculation included the assumption of host geology characteristics, a compatible repository concept including overpacking, and a range of possible nuclear programs. These have differing numbers of power plants, and differing mixes of high level waste from reprocessing and spent fuel for direct disposal. An algorithm was then developed so that the cost of high level waste disposal could be calculated for any required case within a stated envelope of parameters. An Example Case was then considered in detail leading to the conclusion that a repository to meet the needs of a constant UK nuclear economy up to the middle of the next century would have a cash cost of UK Pounds 1194M (US$2011M). By simple division the cost to a kWh of electricity is UK Pounds 0.00027 (0.45 US mil). (author)

Planning for closures of hazardous waste land disposal units at the Oak Ridge Y-12 plant

International Nuclear Information System (INIS)

Welch, S.H.; Kelly, B.A.; DeLozier, M.F.P.; Manrod, W.E.

1988-01-01

Eight hazardous waste land disposal units at the Oak Ridge Y-12 Plant are being closed in accordance with the Resource Conservation and Recovery Act (RCRA) under an integrated multi-year program. The units, some of which date back to the early 1950s and include five surface impoundments, two landfills and a land treatment unit, have been used for the management of a variety of types of hazardous wastes. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. The units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. Closure of all eight units must be initiated by November 8, 1988. Funding for the eight closures is being provided by a new Department of Energy budget category, the environmental Restoration Budget Category (ERBC), which is intended to allow for a more rapid response to environmental problems and regulatory requirements. A major project, Closure and Post-Closure Activities (CAPCA) has been identified for ERBC funding to close the land disposal units in accordance with RCRA requirements. Establishing the project scope has required the development of a detailed set of assumptions and a confirmation program for each assumption. Other significant activities in the CAPCA project include risk assessments and the preparation of an integrated project schedule

Geophysical investigation of the 116-H-1 liquid waste disposal trench, 100-HR-1 operable unit

International Nuclear Information System (INIS)

Bergstrom, K.A.; Mitchell, T.H.

1996-04-01

A geophysical investigation and data integration were conducted for the 116-H-1 Liquid Waste Disposal Trench, which is located in the 100-HR-1 Operable Unit. The 116-H-1 Liquid Waste Disposal Trench is also known as the 107-H Liquid Waste Disposal Trench, the 107-H Rupture Effluent Trench, and the 107-H Trench (Deford and Einan 1995). The trench was primarily used to hold effluent from the 107-H Retention Basin that had become radioactive from contact with ruptured fuel elements. The effluent may include debris from the ruptured fuel elements (Koop 1964). The 116-H-1 Liquid Waste Disposal Trench was also used to hold water and sludge from the 107-H Retention Basin during the basin's deactivation in 1965

Mapping process and age of Quaternary deposits on Santa Rosa Island, Channel Islands National Park, California

Science.gov (United States)

Schmidt, K. M.; Minor, S. A.; Bedford, D.

2016-12-01

Employing a geomorphic process-age classification scheme, we mapped the Quaternary surficial geology of Santa Rosa (SRI) within the Channel Islands National Park. This detailed (1:12,000 scale) map represents upland erosional transport processes and alluvial, fluvial, eolian, beach, marine terrace, mass wasting, and mixed depositional processes. Mapping was motivated through an agreement with the National Park Service and is intended to aid natural resource assessments, including post-grazing disturbance recovery and identification of mass wasting and tectonic hazards. We obtained numerous detailed geologic field observations, fossils for faunal identification as age control, and materials for numeric dating. This GPS-located field information provides ground truth for delineating map units and faults using GIS-based datasets- high-resolution (sub-meter) aerial imagery, LiDAR-based DEMs and derivative raster products. Mapped geologic units denote surface processes and Quaternary faults constrain deformation kinematics and rates, which inform models of landscape change. Significant findings include: 1) Flights of older Pleistocene (>120 ka) and possibly Pliocene marine terraces were identified beneath younger alluvial and eolian deposits at elevations as much as 275 m above modern sea level. Such elevated terraces suggest that SRI was a smaller, more submerged island in the late Neogene and (or) early Pleistocene prior to tectonic uplift. 2) Structural and geomorphic observations made along the potentially seismogenic SRI fault indicate a protracted slip history during the late Neogene and Quaternary involving early normal slip, later strike slip, and recent reverse slip. These changes in slip mode explain a marked contrast in island physiography across the fault. 3) Many of the steeper slopes are dramatically stripped of regolith, with exposed bedrock and deeply incised gullies, presumably due effects related to past grazing practices. 4) Surface water presence is

Improved predictive mapping of indoor radon concentrations using ensemble regression trees based on automatic clustering of geological units

International Nuclear Information System (INIS)

Kropat, Georg; Bochud, Francois; Jaboyedoff, Michel; Laedermann, Jean-Pascal; Murith, Christophe; Palacios, Martha; Baechler, Sébastien

2015-01-01

Purpose: According to estimations around 230 people die as a result of radon exposure in Switzerland. This public health concern makes reliable indoor radon prediction and mapping methods necessary in order to improve risk communication to the public. The aim of this study was to develop an automated method to classify lithological units according to their radon characteristics and to develop mapping and predictive tools in order to improve local radon prediction. Method: About 240 000 indoor radon concentration (IRC) measurements in about 150 000 buildings were available for our analysis. The automated classification of lithological units was based on k-medoids clustering via pair-wise Kolmogorov distances between IRC distributions of lithological units. For IRC mapping and prediction we used random forests and Bayesian additive regression trees (BART). Results: The automated classification groups lithological units well in terms of their IRC characteristics. Especially the IRC differences in metamorphic rocks like gneiss are well revealed by this method. The maps produced by random forests soundly represent the regional difference of IRCs in Switzerland and improve the spatial detail compared to existing approaches. We could explain 33% of the variations in IRC data with random forests. Additionally, the influence of a variable evaluated by random forests shows that building characteristics are less important predictors for IRCs than spatial/geological influences. BART could explain 29% of IRC variability and produced maps that indicate the prediction uncertainty. Conclusion: Ensemble regression trees are a powerful tool to model and understand the multidimensional influences on IRCs. Automatic clustering of lithological units complements this method by facilitating the interpretation of radon properties of rock types. This study provides an important element for radon risk communication. Future approaches should consider taking into account further variables

Feasibility study and concepts for use of compact process units to treat Hanford tank wastes

Energy Technology Data Exchange (ETDEWEB)

Collins, E.D.; Bond, W.D.; Campbell, D.O.; Harrington, F.E.; Malkemus, D.W.; Peishel, F.L.; Yarbro, O.O.

1994-06-01

A team of experienced radiochemical design engineers and chemists was assembled at Oak Ridge National Laboratory (ORNL) at the request of the Underground Storage Tank Integrated Demonstration (USTID) Program to evaluate the feasibility and perform a conceptual study of options for the use of compact processing units (CPUs), located at the Hanford, Washington, waste tank sites, to accomplish extensive pretreatment of the tank wastes using the clean-option concept. The scope of the ORNL study included an evaluation of the constraints of the various chemical process operations that may be employed and the constraints of necessary supporting operations. The latter include equipment maintenance and replacement, process control methods, product and by-product storage, and waste disposal.

Feasibility study and concepts for use of compact process units to treat Hanford tank wastes

International Nuclear Information System (INIS)

Collins, E.D.; Bond, W.D.; Campbell, D.O.; Harrington, F.E.; Malkemus, D.W.; Peishel, F.L.; Yarbro, O.O.

1994-06-01

A team of experienced radiochemical design engineers and chemists was assembled at Oak Ridge National Laboratory (ORNL) at the request of the Underground Storage Tank Integrated Demonstration (USTID) Program to evaluate the feasibility and perform a conceptual study of options for the use of compact processing units (CPUs), located at the Hanford, Washington, waste tank sites, to accomplish extensive pretreatment of the tank wastes using the clean-option concept. The scope of the ORNL study included an evaluation of the constraints of the various chemical process operations that may be employed and the constraints of necessary supporting operations. The latter include equipment maintenance and replacement, process control methods, product and by-product storage, and waste disposal

Calculation of projected waste loads for transuranic waste management alternatives

International Nuclear Information System (INIS)

Hong, K.; Kotek, T.; Koebnick, B.; Wang, Y.; Kaicher, C.

1995-01-01

The level of treatment and the treatment and interim storage site configurations (decentralized, regional, or centralized) impact transuranic (TRU) waste loads at and en route to sites in the US Department of Energy (DOE) complex. Other elements that impact waste loads are the volume and characteristics of the waste and the unit operation parameters of the technologies used to treat it. Projected annual complexwide TRU waste loads under various TRU waste management alternatives were calculated using the WASTEunderscoreMGMT computational model. WASTEunderscoreMGMT accepts as input three types of data: (1) the waste stream inventory volume, mass, and contaminant characteristics by generating site and waste stream category; (2) unit operation parameters of treatment technologies; and (3) waste management alternative definitions. Results indicate that the designed capacity of the Waste Isolation Pilot Plant, identified under all waste management alternatives as the permanent disposal facility for DOE-generated TRU waste, is sufficient for the projected complexwide TRU waste load under any of the alternatives

Development of the Computer Code to Determine an Individual Radionuclides in the Rad-wastes Container for Ulchin Units 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Kang, D.W.; Chi, J.H.; Goh, E.O. [Korea Electric Power Research Institute, Taejon (Korea)

2001-07-01

A computer program, RASSAY was developed to evaluate accurately the activities of various nuclides in the rad-waste container for Ulchin units 3 and 4. This is the final report of the project, {sup D}evelopment of the Computer Code to Determine an Individual Radionuclides in the Rad-wastes Container for Ulchin Units 3 and 4 and includes the followings; 1) Structure of the computer code, RASSAY 2) An example of surface dose calculation by computer simulation using MCNP code 3) Methods of sampling and activity measurement of various Rad-wastes. (author). 21 refs., 35 figs., 6 tabs.

Food waste disposal units in UK households: The need for policy intervention

International Nuclear Information System (INIS)

Iacovidou, Eleni; Ohandja, Dieudonne-Guy; Voulvoulis, Nikolaos

2012-01-01

The EU Landfill Directive requires Member States to reduce the amount of biodegradable waste disposed of to landfill. This has been a key driver for the establishment of new waste management options, particularly in the UK, which in the past relied heavily on landfill for the disposal of municipal solid waste (MSW). MSW in the UK is managed by Local Authorities, some of which in a less conventional way have been encouraging the installation and use of household food waste disposal units (FWDs) as an option to divert food waste from landfill. This study aimed to evaluate the additional burden to water industry operations in the UK associated with this option, compared with the benefits and related savings from the subsequent reductions in MSW collection and disposal. A simple economic analysis was undertaken for different FWD uptake scenarios, using the Anglian Region as a case study. Results demonstrated that the significant savings from waste collection arising from a large-scale uptake of FWDs would outweigh the costs associated with the impacts to the water industry. However, in the case of a low uptake, such savings would not be enough to cover the increased costs associated with the wastewater provision. As a result, this study highlights the need for policy intervention in terms of regulating the use of FWDs, either promoting them as an alternative to landfill to increase savings from waste management, or banning them as a threat to wastewater operations to reduce potential costs to the water industry. - Highlights: ► FWDs can be a less conventional way for diverting food waste from landfill. ► We compared water industry costs to savings from MSW collection and treatment. ► A large-scale uptake of FWDs would outweigh the costs to the water industry. ► At a low uptake, MSW collection savings are not enough to cover these costs. ► Findings highlight the need for policy intervention, regulating the use of FWDs.

The 1985 United Kingdom radioactive waste inventory

International Nuclear Information System (INIS)

Fletcher, A.M.; Wear, F.J.; Haselden, H.; Shepherd, J.; Tymons, B.J.

1986-07-01

This report provides a compilation of stocks of radioactive wastes in the UK by volume, as at 1 January 1985, and estimates of future arisings to the year 2030. It includes radionuclide contents as available, together with specific activities, notional conditioning factors and disposal routes. In the main the stock volumes are given as unconditioned waste. However for clarity and precision some of the data relates to treated wastes (ie compacted wastes, incinerator ash, etc). These are clearly marked in the Tables. (author)

Non-Markovianity Measure Based on Brukner-Zeilinger Invariant Information for Unital Quantum Dynamical Maps

Science.gov (United States)

He, Zhi; Zhu, Lie-Qiang; Li, Li

2017-03-01

A non-Markovianity measure based on Brukner-Zeilinger invariant information to characterize non-Markovian effect of open systems undergoing unital dynamical maps is proposed. The method takes advantage of non-increasing property of the Brukner-Zeilinger invariant information under completely positive and trace-preserving unital maps. The simplicity of computing the Brukner-Zeilinger invariant information is the advantage of the proposed measure because of mainly depending on the purity of quantum state. The measure effectively captures the characteristics of non-Markovianity of unital dynamical maps. As some concrete application, we consider two typical non-Markovian noise channels, i.e., the phase damping channel and the random unitary channel to show the sensitivity of the proposed measure. By investigation, we find that the conditions of detecting the non-Markovianity for the phase damping channel are consistent with the results of existing measures for non-Markovianity, i.e., information flow, divisibility and quantum mutual information. However, for the random unitary channel non-Markovian conditions are same to that of the information flow, but is different from that of the divisibility and quantum mutual information. Supported by the National Natural Science Foundation of China under Grant No. 61505053, the Natural Science Foundation of Hunan Province under Grant No. 2015JJ3092, the Research Foundation of Education Bureau of Hunan Province, China under Grant No. 16B177, the School Foundation from the Hunan University of Arts and Science under Grant No. 14ZD01

United States regulations for institutional controls at high-level waste repositories

International Nuclear Information System (INIS)

Piccone, Josephine

2015-01-01

The United States regulations for disposal of spent nuclear fuel and high-level radioactive waste are found at Title 10 of the Code of Federal Regulations (10 CFR) Parts 60 and 63, which cover deep geologic disposal at a generic site and at Yucca Mountain, Nevada, respectively. As an independent regulator, the US Nuclear Regulatory Commission (NRC) is responsible for licensing and oversight of a high-level waste repository in the United States. The licensing approach for disposal has discreet decisions, made by the NRC, that include approval of construction authorisation, approval to receive and possess high-level radioactive waste, and approval for permanent closure. For construction authorisation approval, the applicant must provide a description of the programme to be used to maintain the records. The NRC will have an active oversight role during the construction and operation period, which can be on the order of 100 years for the facility before permanent closure. The oversight activities are part of the active institutional controls, and serve as a means of conveying knowledge for that initial period, given that this will likely involve multiple generations of workers for both the implementer and the regulator. Additionally, the NRC provides requirements for the physical protection of stored spent nuclear fuel and high-level radioactive waste at 10 CFR Chap. 73.51. For permanent closure approval, the applicant must provide a detailed description of the measures to be employed-such as land use controls, construction of monuments, and preservation of records. The NRC's regulatory role in any licensing action is to apply the applicable regulations and guidance, and to review applications for proposed actions to determine if compliance with regulations has been achieved. The burden of proof is on the applicant or licensee to show that the proposed action is safe, to demonstrate that regulations are met, and to ensure continued compliance with the regulations

Integrated Waste Treatment Unit GFSI Risk Management Plan

International Nuclear Information System (INIS)

W. A. Owca

2007-01-01

This GFSI Risk Management Plan (RMP) describes the strategy for assessing and managing project risks for the Integrated Waste Treatment Unit (IWTU) that are specifically within the control and purview of the U.S. Department of Energy (DOE), and identifies the risks that formed the basis for the DOE contingency included in the performance baseline. DOE-held contingency is required to cover cost and schedule impacts of DOE activities. Prior to approval of the performance baseline (Critical Decision-2) project cost contingency was evaluated during a joint meeting of the Contractor Management Team and the Integrated Project Team for both contractor and DOE risks to schedule and cost. At that time, the contractor cost and schedule risk value was $41.3M and the DOE cost and schedule risk contingency value is $39.0M. The contractor cost and schedule risk value of $41.3M was retained in the performance baseline as the contractor's management reserve for risk contingency. The DOE cost and schedule risk value of $39.0M has been retained in the performance baseline as the DOE Contingency. The performance baseline for the project was approved in December 2006 (Garman 2006). The project will continue to manage to the performance baseline and change control thresholds identified in PLN-1963, ''Idaho Cleanup Project Sodium-Bearing Waste Treatment Project Execution Plan'' (PEP)

Geologic map of the Paintbrush Canyon Area, Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Dickerson, R.P.; Drake, R.M. II

1998-01-01

This geologic map is produced to support site characterization studies of Yucca Mountain, Nevada, site of a potential nuclear waste storage facility. The area encompassed by this map lies between Yucca Wash and Fortymile Canyon, northeast of Yucca Mountain. It is on the southern flank of the Timber Mountain caldera complex within the southwest Nevada volcanic field. Miocene tuffs and lavas of the Calico Hills Formation, the Paintbrush Group, and the Timber Mountain Group crop out in the area of this map. The source vents of the tuff cones and lava domes commonly are located beneath the thickest deposits of pyroclastic ejecta and lava flows. The rocks within the mapped area have been deformed by north- and northwest-striking, dominantly west-dipping normal faults and a few east-dipping normal faults. Faults commonly are characterized by well developed fault scarps, thick breccia zones, and hanging-wall grabens. Latest movement as preserved by slickensides on west-dipping fault scarps is oblique down towards the southwest. Two of these faults, the Paintbrush Canyon fault and the Bow Ridge fault, are major block-bounding faults here and to the south at Yucca Mountain. Offset of stratigraphic units across faults indicates that faulting occurred throughout the time these volcanic units were deposited

Geologic map of the Paintbrush Canyon Area, Yucca Mountain, Nevada

Energy Technology Data Exchange (ETDEWEB)

Dickerson, R.P. [Geological Survey, Denver, CO (United States); Drake, R.M. II [Pacific Western Technologies, Ltd., Lakewood, CO (United States)

1998-11-01

This geologic map is produced to support site characterization studies of Yucca Mountain, Nevada, site of a potential nuclear waste storage facility. The area encompassed by this map lies between Yucca Wash and Fortymile Canyon, northeast of Yucca Mountain. It is on the southern flank of the Timber Mountain caldera complex within the southwest Nevada volcanic field. Miocene tuffs and lavas of the Calico Hills Formation, the Paintbrush Group, and the Timber Mountain Group crop out in the area of this map. The source vents of the tuff cones and lava domes commonly are located beneath the thickest deposits of pyroclastic ejecta and lava flows. The rocks within the mapped area have been deformed by north- and northwest-striking, dominantly west-dipping normal faults and a few east-dipping normal faults. Faults commonly are characterized by well developed fault scarps, thick breccia zones, and hanging-wall grabens. Latest movement as preserved by slickensides on west-dipping fault scarps is oblique down towards the southwest. Two of these faults, the Paintbrush Canyon fault and the Bow Ridge fault, are major block-bounding faults here and to the south at Yucca Mountain. Offset of stratigraphic units across faults indicates that faulting occurred throughout the time these volcanic units were deposited.

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

International Nuclear Information System (INIS)

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

1994-01-01

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

Sampling and analysis plan for remediation of Operable Unit 100-IU-3 waste site 600-104

International Nuclear Information System (INIS)

1997-08-01

This sampling and analysis plan (SAP) presents the rationale and strategy for the sampling and analysis activities to support remediation of 100-IU-3 Operable Unit waste site 600-104. The purpose of the proposed sampling and analysis activities is to demonstrate that time-critical remediation of the waste site for soil containing 2,4-Dichlorophonoxyacetic acid salts and esters (2,4-D) and dioxin/furan isomers at concentrations that exceed cleanup levels has been effective. This shall be accomplished by sampling various locations of the waste site before and after remediation, analyzing the samples, and comparing the results to action levels set by the Washington State Department of Ecology

Cementation unit for radioactive wastes

International Nuclear Information System (INIS)

Dellamano, Jose Claudio; Vicente, Roberto; Lima, Jose Rodrigues de

2001-01-01

This communication describes the waste cementation process and facility developed at Instituto de Pesquisas Energeticas e Nucleares - IPEN. The process is based on 200 litres batch operation, in drum mixing, with continuous cement feeding. The equipment is a single recoverable helicoidal mixer and a turning table that allows the drum to rotate during the mixing operation, simulating a planetary mixer. The facility was designed to treat contact handled liquids and wet solid wastes, but can be adapted for shielded equipment and remote operation. (author)

United States Program on Spent Nuclear Fuel and High-Level Radioactive Waste Management

International Nuclear Information System (INIS)

Stewart, L.

2004-01-01

The President signed the Congressional Joint Resolution on July 23, 2002, that designated the Yucca Mountain site for a proposed geologic repository to dispose of the nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The United States (U.S.) Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is currently focusing its efforts on submitting a license application to the U.S. Nuclear Regulatory Commission (NRC) in December 2004 for construction of the proposed repository. The legislative framework underpinning the U.S. repository program is the basis for its continuity and success. The repository development program has significantly benefited from international collaborations with other nations in the Americas

A preliminary investigation of vertical crustal movements in the United Kingdom in the context of subsurface nuclear waste isolation

International Nuclear Information System (INIS)

1981-03-01

Two types of change will influence the environment of a subsurface nuclear waste isolation facility: natural geological changes and changes caused by the construction of the waste repository and introduction of the waste. This report is concerned with vertical crustal movements, which are an expression of natural geological changes. Vertical crustal movements observed outside the United Kingdom are reviewed, and vertical movements in a test region of the UK investigated by comparison of geodetic levellings. The implications of vertical crustal movement to waste isolation facilities and some potentially valuable lines of research are discussed. (author)

Institutional aspects of siting nuclear waste disposal facilities in the United States

International Nuclear Information System (INIS)

Stewart, John Cameron.; Prichard, Clark. W.

1987-01-01

This chapter deals with the institutional issues associated with the disposal of nuclear waste in the United States of America. These include socio-economic, financial, land use and especially, political factors. Institutional issues must, however, be resolved, as well as the technological problems of engineering and geology. The general issues are first examined, then the organisation and financing, land use, community acceptance, transport problems and finally, local economic impacts. (UK)

WIPP Facility Work Plan for Solid Waste Management Units

Energy Technology Data Exchange (ETDEWEB)

Washington TRU Solutions LLC

2001-02-25

This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.

Analysis of the use of waste heat obtained from coal-fired units in Organic Rankine Cycles and for brown coal drying

International Nuclear Information System (INIS)

Łukowicz, Henryk; Kochaniewicz, Andrzej

2012-01-01

The ever-increasing restrictions on greenhouse gas emissions have created a need for new energy technologies. One way to meet these new requirements is to optimise the efficiency of power units. This paper presents two energy technologies that, if used, will increase the efficiency of electricity generation. One of the most effective ways to improve the efficiency of brown coal-fired units is by drying the coal that is fed into the boiler. Here, we describe a technology that uses the waste heat obtained from exhaust gases. This paper also presents an analysis of the feasibility of and potential for using waste heat obtained from exhaust gases to feed Organic Rankine Cycles (ORCs). Several low-temperature working fluids were considered, which were selected based on properties that were best suited for these types of cycles. The impact of these working fluids on the efficiency and capacity of the ORC was also examined. The calculations for ORCs fed with waste heat obtained from exhaust gases from hard coal- and brown coal-fired boilers were compared. -- Highlights: ► We describe a technology that uses the waste heat obtained from exhaust gases. ► The impact of using different working fluids with a low boiling point is examined. ► We describe integrating the ORC with the power unit. ► The use of waste heat from boiler exhaust gases to dry brown coal is proposed. ► We demonstrate a possible increase in power unit efficiency.

Management of solid wastes during decommissioning of research reactors. Evaluation of gross clearance levels and mathematical simulation of solid waste assay techniques

International Nuclear Information System (INIS)

Gopalakrishnan, R.K.; Sobhan Babu, K.; Sharma, D.N.

2008-01-01

Full text: Decommissioning of nuclear facilities constitute a challenge mainly due to the huge and complex nature of radioactive waste generated during this process. In the context of management and disposal of waste and reuse/recycle of usable materials during decommissioning of reactors, clearance levels for relevant radio nuclides are of vital importance. Radionuclide specific clearance levels are developed by IAEA and such levels allow the facility for free release of materials to the environment without further regulatory consideration. An effort has been made in this paper to establish clearance levels for radionuclides associated with various system and structural components of a research reactor and rather than radionuclide specific clearance levels, these values are derived for gross activity concentration, which is more practical for radioactive waste categorization, disposal and reuse or recycle of usable materials. The first step towards the derivation of clearance levels is the calculation of annual doses relating to unit activity concentration for each nuclide using various enveloping scenarios. After the estimation of doses, the limiting enveloping scenario (the one that gives the highest dose) is identified. The clearance levels are then derived by dividing the reference dose level (10 μSv/y) by the annual dose calculated per unit activity concentration for the limiting enveloping scenario The clearance level for gross beta-gamma activity concentration is then evaluated as the product of the limiting clearance level and the number of radionuclides characterized for the structural components. Simulation studies were also carried out for the design of a monitoring system for estimation of activity concentration of the decommissioned materials, especially rubbles/ concrete, using mathematical models. Conventional solid waste assay techniques would not suffice to the requirement of decommissioning waste categorization since very low level activity

Waste indicators

Energy Technology Data Exchange (ETDEWEB)

Dall, O.; Lassen, C.; Hansen, E. [Cowi A/S, Lyngby (Denmark)

2003-07-01

The Waste Indicator Project focuses on methods to evaluate the efficiency of waste management. The project proposes the use of three indicators for resource consumption, primary energy and landfill requirements, based on the life-cycle principles applied in the EDIP Project. Trial runs are made With the indicators on paper, glass packaging and aluminium, and two models are identified for mapping the Danish waste management, of which the least extensive focuses on real and potential savings. (au)

Waste indicators

International Nuclear Information System (INIS)

Dall, O.; Lassen, C.; Hansen, E.

2003-01-01

The Waste Indicator Project focuses on methods to evaluate the efficiency of waste management. The project proposes the use of three indicators for resource consumption, primary energy and landfill requirements, based on the life-cycle principles applied in the EDIP Project. Trial runs are made With the indicators on paper, glass packaging and aluminium, and two models are identified for mapping the Danish waste management, of which the least extensive focuses on real and potential savings. (au)

Quantitative analysis of terrain units mapped in the northern quarter of Venus from Venera 15/16 data

Science.gov (United States)

Schaber, G. G.

1991-01-01

The contacts between 34 geological/geomorphic terrain units in the northern quarter of Venus mapped from Venera 15/16 data were digitized and converted to a Sinusoidal Equal-Area projection. The result was then registered with a merged Pioneer Venus/Venera 15/16 altimetric database, root mean square (rms) slope values, and radar reflectivity values derived from Pioneer Venus. The resulting information includes comparisons among individual terrain units and terrain groups to which they are assigned in regard to percentage of map area covered, elevation, rms slopes, distribution of suspected craters greater than 10 km in diameter.

Listed waste history at Hanford facility TSD units

International Nuclear Information System (INIS)

Miskho, A.G.

1996-01-01

This document was prepared to close out an occurrence report that Westinghouse Hanford Company issued on December 29, 1994. Occurrence Report RL-WHC-GENERAL-1994-0020 was issued because knowledge became available that could have impacted start up of a Hanford Site facility. The knowledge pertained to how certain wastes on the Hanford Site were treated, stored, or disposed of. This document consolidates the research performed by Westinghouse Hanford Company regarding listed waste management at onsite laboratories that transfer waste to the Double-Shell Tank System. Liquid and solid (non-liquid) dangerous wastes and mixed wastes at the Hanford Site are generated from various Site operations. These wastes may be sampled and characterized at onsite laboratories to meet waste management requirements. In some cases, the wastes that are generated in the field or in the laboratory from the analysis of samples require further management on the Hanford Site and are aggregated together in centralized tank storage facilities. The process knowledge presented herein documents the basis for designation and management of 242-A Evaporator Process Condensate, a waste stream derived from the treatment of the centralized tank storage facility waste (the Double-Shell Tank System). This document will not be updated as clean up of the Hanford Site progresses

Hanford Site solid waste acceptance criteria

International Nuclear Information System (INIS)

Ellefson, M.D.

1998-01-01

Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities

Inventories of woody residues and solid wood waste in the United States, 2002

Science.gov (United States)

David B. McKeever

2004-01-01

Large amounts of woody residues and wood waste are generated annually in the United States. In 2002, an estimated 240 million metric tons was generated during the extraction of timber from the Nation’s forests, from forestry cultural operations, in the conversion of forest land to nonforest uses, in the initial processing of roundwood timber into usable products, in...

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

International Nuclear Information System (INIS)

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

1997-09-01

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

A literature review of methods of analysis of organic analytes in radioactive wastes with an emphasis on sources from the United Kingdom

International Nuclear Information System (INIS)

Clauss, S.A.; Bean, R.M.

1993-09-01

This report, compiled by Pacific Northwest Laboratory (PNL), examines literature originating through the United Kingdom (UK) nuclear industry relating to the analyses of organic constituents of radioactive waste. Additionally, secondary references from the UK and other counties, including the United States, have been reviewed. The purpose of this literature review was to find analytical methods that would apply to the mixed-waste matrices found at Hanford

Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2 radioactive waste and laundry shipments

International Nuclear Information System (INIS)

Doerge, D.H.; Haffner, D.R.

1988-06-01

This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order

Search and mapping of the old buried tailings with radioactive wastes at the urban territory

International Nuclear Information System (INIS)

Molchanov, O. I.; Soroka, Y. N.; Podrezov, A. A.; Soroka, M. N.

2017-01-01

The article presents results of investigation on search and mapping of the old buried tailings with radioactive wastes on the territory of Kamianske City. For solving the problem used complex of methods. These methods are as follows: soil-gas 222 Rn measurement and measurement of 222 Rn flux density from the ground surface, gamma-radiation survey, prospecting drilling, gamma-ray logging and laboratory analysis of radionuclides. The leading method in this complex was the method of soil-gas 222 Rn measurement. Using this method location of the tailings has been precisely defined. The tailings boundaries have been contoured in the plan. Other methods permitted to define such parameters as thickness of the wastes, their volume (∼330 000 m 3 ), radionuclide and chemical composition. It was found that radioactive residues occur at a depth from 2 to 11 m and contain in its composition 226 Ra, 210 Pb and 210 Po in the range from 8370 to 37270 Bq kg -1 .(authors)

Low-level radioactive waste, mixed low-level radioactive waste, and biomedical mixed waste

International Nuclear Information System (INIS)

Anon.

1994-01-01

This document describes the proceedings of a workshop entitled: Low-Level Radioactive Waste, Mixed Low-Level Radioactive Waste, and Biomedical Mixed Waste presented by the National Low-Level Waste Management Program at the University of Florida, October 17-19, 1994. The topics covered during the workshop include technical data and practical information regarding the generation, handling, storage and disposal of low-level radioactive and mixed wastes. A description of low-level radioactive waste activities in the United States and the regional compacts is presented

HPLC mapping of second generation ethanol production with lignocelluloses wastes and diluted sulfuric hydrolysis

Directory of Open Access Journals (Sweden)

Diogo José Horst

2014-09-01

Full Text Available Wood wastes are potential material for second generation ethanol production within the concept of residual forest bio-refinery. Current paper reports on ethanol production employing an HPLC method for monitoring the chemical content dispersed in the hydrolysate liquor after fermented. The proton-exchange technique was the analytical method employed. Twelve types of wood chips were used as biomass, including Hymenolobium petraeum, Tabebuia cassinoides, Myroxylon peruiferum, Nectandra lanceolata, Ocotea catharinensis, Cedrelinga catenaeformis, Cedrela fissilis Vell, Ocotea porosa, Laurus nobilis, Balfourodendron riedelianum, Pinus Elliotti and Brosimum spp. The influence of diluted sulfuric hydrolysis on the yeast Saccharomyces cerevisiae during the fermentation assay was also investigated. Standard compounds mapped in the analysis comprised fructose, lactic acid, acetic acid, glycerol, glucose and ethanol. The yeast showed ethanol productivity between 0.75 and 1.91 g L-1 h-1, respectively, without the addition of supplementary nutrients or detoxification. The use of these materials for the bioconversion of cellulose into ethanol has been proved. Current analysis contributes towards the production of biofuels by wastes recovery and by process monitoring and optimization.

Shale: an overlooked option for US nuclear waste disposal

Science.gov (United States)

Neuzil, Christopher E.

2014-01-01

Toss a dart at a map of the United States and, more often than not, it will land where shale can be found underground. A drab, relatively featureless sedimentary rock that historically attracted little interest, shale (as used here, the term includes clay and a range of clay-rich rocks) is entering Americans’ consciousness as a new source of gas and oil. But shale may also offer something entirely different—the ability to safely and permanently house high-level nuclear waste.

Development of low-level radioactive waste disposal capacity in the United States - progress or stalemate?

International Nuclear Information System (INIS)

Devgun, J.S.; Larson, G.S.

1995-01-01

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The U.S. nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW - industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW - face the same storage and cost uncertainties. This paper will summarize the current status of U.S. low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

Development of low-level radioactive waste disposal capacity in the United States -- Progress or stalemate?

International Nuclear Information System (INIS)

Devgun, J.S.

1995-01-01

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The US nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW -- industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW -- face the same storage and cost uncertainties. This paper will summarize the current status of US low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

A mitotically inheritable unit containing a MAP kinase module.

Science.gov (United States)

Kicka, Sébastien; Bonnet, Crystel; Sobering, Andrew K; Ganesan, Latha P; Silar, Philippe

2006-09-05

Prions are novel kinds of hereditary units, relying solely on proteins, that are infectious and inherited in a non-Mendelian fashion. To date, they are either based on autocatalytic modification of a 3D conformation or on autocatalytic cleavage. Here, we provide further evidence that in the filamentous fungus Podospora anserina, a MAP kinase cascade is probably able to self-activate and generate C, a hereditary unit that bears many similarities to prions and triggers cell degeneration. We show that in addition to the MAPKKK gene, both the MAPKK and MAPK genes are necessary for the propagation of C, and that overexpression of MAPK as that of MAPKKK facilitates the appearance of C. We also show that a correlation exists between the presence of C and localization of the MAPK inside nuclei. These data emphasize the resemblance between prions and a self-positively regulated cascade in terms of their transmission. This thus further expands the concept of protein-base inheritance to regulatory networks that have the ability to self-activate.

Demonstration Testing of a Thermal Desorption Unit to Receive and Treat Waste with Unlimited Concentration of PCBs - 13437

Energy Technology Data Exchange (ETDEWEB)

Orton, Timothy L. [EnergySolutions, 423 West 300 South, Salt Lake City, UT 84101 (United States); Palmer, Carl R. [TD.X Associates LP, 148 South Dowlen Road, PMB 700, Beaumont, TX 77707 (United States)

2013-07-01

For the last nine years, EnergySolutions and TD*X Associates LP have teamed up to provide the most comprehensive organic removal treatment process in the radioactive waste industry. The high performance thermal desorption unit (HP-TDU) located at the EnergySolutions Clive facility in Utah has successfully processed over 1,850 tons of organically contaminated radioactive mixed waste. Products from the HP-TDU system include a radioactively contaminated dry solid material that can be disposed in the on-site landfill and an organic condensate with high thermal energy content that is generally below background radiation and capable of free-release to a non-radioactive incinerator. Over the years, Permits and approvals have been obtained through the state of Utah, United States Environmental Protection Agency (USEPA) Region 8, and USEPA headquarters that enable the treatment of several waste categories including volatile and semi-volatile organic compounds, combustion-coded (CMBST) compounds, volatile metals, and polychlorinated biphenyls (PCBs). The unit has recently successfully completed Demonstration Testing for PCB concentrations up to 660,000 ppm (parts per million). Solid processed material from this Demonstration Testing was less than two ppm PCBs in three separate treatment runs; reprocessing or additional treatment was not needed to meet this limit. Through post-demonstration permitting, the system is unlimited in scope as approval has been given to receive and solidify up to pure PCBs down to this processing limit concentration to complete treatment of mixed waste. (authors)

Closure Report for Corrective Action Unit 562: Waste Systems, Nevada National Security Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2012-08-15

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 562, Waste Systems, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 562 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 562 consists of the following 13 Corrective Action Sites (CASs), located in Areas 2, 23, and 25 of the Nevada National Security Site: · CAS 02-26-11, Lead Shot · CAS 02-44-02, Paint Spills and French Drain · CAS 02-59-01, Septic System · CAS 02-60-01, Concrete Drain · CAS 02-60-02, French Drain · CAS 02-60-03, Steam Cleaning Drain · CAS 02-60-04, French Drain · CAS 02-60-05, French Drain · CAS 02-60-06, French Drain · CAS 02-60-07, French Drain · CAS 23-60-01, Mud Trap Drain and Outfall · CAS 23-99-06, Grease Trap · CAS 25-60-04, Building 3123 Outfalls Closure activities began in October 2011 and were completed in April 2012. Activities were conducted according to the Corrective Action Plan for CAU 562 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The corrective actions included No Further Action and Clean Closure. Closure activities generated sanitary waste and hazardous waste. Some wastes exceeded land disposal limits and required offsite treatment prior to disposal. Other wastes met land disposal restrictions and were disposed in appropriate onsite or offsite landfills. NNSA/NSO requests the following: · A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 562 · The transfer of CAU 562 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO

SRNL Phase 1 Assessment Of The WAC/DQO And Unit Operations For The WTP Waste Qualification Program

International Nuclear Information System (INIS)

Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

2012-01-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap identification

SRNL PHASE 1 ASSESSMENT OF THE WAC/DQO AND UNIT OPERATIONS FOR THE WTP WASTE QUALIFICATION PROGRAM

Energy Technology Data Exchange (ETDEWEB)

Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

2012-05-16

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap

Development of a new USDA plant hardiness zone map for the United States

Science.gov (United States)

C. Daly; M.P. Widrlechner; M.D. Halbleib; J.I. Smith; W.P. Gibson

2012-01-01

In many regions of the world, the extremes of winter cold are a major determinant of the geographic distribution of perennial plant species and of their successful cultivation. In the United States, the U.S. Department of Agriculture (USDA) Plant Hardiness Zone Map (PHZM) is the primary reference for defining geospatial patterns of extreme winter cold for the...

Use of combustible wastes as fuel

Energy Technology Data Exchange (ETDEWEB)

Kotler, V.R.; Salamov, A.A.

1983-01-01

Achievements of science and technology in creating and using units for combustion of wastes with recovery of heat of the escaping gases has been systematized and generalized. Scales and outlooks are examined for the use of general, industrial and agricultural waste as fuel, composition of the waste, questions of planning and operating units for combustion of solid refuse, settling of waste water and industrial and agricultural waste. Questions are covered for preparing them for combustion use in special units with recovery of heat and at ES, aspects of environmental protection during combustion of waste, cost indicators of the employed methods of recovering the combustible waste.

Space-time mapping of wasting among children under the age of five years in Somalia from 2007 to 2010.

Science.gov (United States)

Kinyoki, Damaris K; Berkley, James A; Moloney, Grainne M; Odundo, Elijah O; Kandala, Ngianga-Bakwin; Noor, Abdisalan M

2016-02-01

To determine the sub-national seasonal prevalence and trends in wasting from 2007 to 2010 among children aged 6-59 months in Somalia using remote sensing and household survey data from nutritional surveys. Bayesian hierarchical space-time model was implemented using a stochastic partial differential equation (SPDE) approach in integrated nested Laplace approximations (INLA) to produce risk maps of wasting at 1 × 1 km(2) spatial resolution and predict to seasons in each year of study from 2007 to 2010. The prevalence of wasting was generally at critical levels throughout the country, with most of the areas remaining in the upper classes of critical and very critical levels. There was minimal variation in wasting from year-to-year, but a well-defined seasonal variation was observed. The mean difference of the prevalence of wasting between the dry and wet season ranges from 0% to 5%. The risks of wasting in the South Central zone were highest in the Gedo (37%) and Bay (32%) regions. In North East zone the risk was highest in Nugaal (25%) and in the North West zone the risk was high in Awdal and Woqooyi Galbeed regions with 23%. There was a clear seasonal variation in wasting with minimal year-to-year variability from 2007 to 2010 in Somalia. The prevalence was high during the long dry season, which affects the prevalence in the preceding long rainy season. Understanding the seasonal fluctuations of wasting in different locations and at different times is important to inform timely interventions. Copyright © 2016. Published by Elsevier Ltd.

Space–time mapping of wasting among children under the age of five years in Somalia from 2007 to 2010

Science.gov (United States)

Kinyoki, Damaris K; Berkley, James A; Moloney, Grainne M; Odundo, Elijah O; Kandala, Ngianga-Bakwin; Noor, Abdisalan M

2016-01-01

Objective To determine the sub-national seasonal prevalence and trends in wasting from 2007 to 2010 among children aged 6–59 months in Somalia using remote sensing and household survey data from nutritional surveys. Methods Bayesian hierarchical space–time model was implemented using a stochastic partial differential equation (SPDE) approach in integrated nested Laplace approximations (INLA) to produce risk maps of wasting at 1 × 1 km2 spatial resolution and predict to seasons in each year of study from 2007 to 2010. Results The prevalence of wasting was generally at critical levels throughout the country, with most of the areas remaining in the upper classes of critical and very critical levels. There was minimal variation in wasting from year-to-year, but a well-defined seasonal variation was observed. The mean difference of the prevalence of wasting between the dry and wet season ranges from 0% to 5%. The risks of wasting in the South Central zone were highest in the Gedo (37%) and Bay (32%) regions. In North East zone the risk was highest in Nugaal (25%) and in the North West zone the risk was high in Awdal and Woqooyi Galbeed regions with 23%. Conclusion There was a clear seasonal variation in wasting with minimal year-to-year variability from 2007 to 2010 in Somalia. The prevalence was high during the long dry season, which affects the prevalence in the preceding long rainy season. Understanding the seasonal fluctuations of wasting in different locations and at different times is important to inform timely interventions. PMID:26919757

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

International Nuclear Information System (INIS)

Hladek, K.L.

1997-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Hladek, K.L.

1997-10-07

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

Bedrock Geologic Map of Vermont - Units

Data.gov (United States)

Vermont Center for Geographic Information — The bedrock geology was last mapped at a statewide scale 50 years ago at a scale of 1:250,000 (Doll and others, 1961). The 1961 map was compiled from 1:62,500-scale...

A geomorphic approach to 100-year floodplain mapping for the Conterminous United States

Science.gov (United States)

Jafarzadegan, Keighobad; Merwade, Venkatesh; Saksena, Siddharth

2018-06-01

Floodplain mapping using hydrodynamic models is difficult in data scarce regions. Additionally, using hydrodynamic models to map floodplain over large stream network can be computationally challenging. Some of these limitations of floodplain mapping using hydrodynamic modeling can be overcome by developing computationally efficient statistical methods to identify floodplains in large and ungauged watersheds using publicly available data. This paper proposes a geomorphic model to generate probabilistic 100-year floodplain maps for the Conterminous United States (CONUS). The proposed model first categorizes the watersheds in the CONUS into three classes based on the height of the water surface corresponding to the 100-year flood from the streambed. Next, the probability that any watershed in the CONUS belongs to one of these three classes is computed through supervised classification using watershed characteristics related to topography, hydrography, land use and climate. The result of this classification is then fed into a probabilistic threshold binary classifier (PTBC) to generate the probabilistic 100-year floodplain maps. The supervised classification algorithm is trained by using the 100-year Flood Insurance Rated Maps (FIRM) from the U.S. Federal Emergency Management Agency (FEMA). FEMA FIRMs are also used to validate the performance of the proposed model in areas not included in the training. Additionally, HEC-RAS model generated flood inundation extents are used to validate the model performance at fifteen sites that lack FEMA maps. Validation results show that the probabilistic 100-year floodplain maps, generated by proposed model, match well with both FEMA and HEC-RAS generated maps. On average, the error of predicted flood extents is around 14% across the CONUS. The high accuracy of the validation results shows the reliability of the geomorphic model as an alternative approach for fast and cost effective delineation of 100-year floodplains for the CONUS.

Woody residues and solid waste wood available for recovery in the United States, 2002

Science.gov (United States)

David B. McKeever; Robert H. Falk

2004-01-01

Large amounts of woody residues and solid wood waste are generated annually in the United States from the extraction of timber from forests, from forestry cultural operations, in the conversion of forest land to nonforest uses, in the initial processing of roundwood timber into usable products, in the construction and demolition of buildings and structures, and in the...

Closure Report for Corrective Action Unit 537: Waste Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2007-01-01

Corrective Action Unit (CAU) 537 is identified in the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 as Waste Sites. CAU 537 is located in Areas 3 and 19 of the Nevada Test Site, approximately 65 miles northwest of Las Vegas, Nevada, and consists of the following two Corrective Action Sites (CASs): CAS 03-23-06, Bucket; Yellow Tagged Bags; and CAS 19-19-01, Trash Pit. CAU 537 closure activities were conducted in April 2007 according to the FFACO and Revision 3 of the Sectored Clean-up Work Plan for Housekeeping Category Waste Sites (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2003). At CAS 03-23-06, closure activities included removal and disposal of a 15-foot (ft) by 15-ft by 8-ft tall wooden shed containing wood and metal debris and a 5-gallon plastic bucket containing deteriorated plastic bags with yellow radioactive contamination tape. The debris was transported to the Area 9 U10c Landfill for disposal after being screened for radiological contamination according to the ''NV/YMP Radiological Control Manual'' (NNSA/NSO, 2004). At CAS 19-19-01, closure activities included segregation, removal, and disposal of non-friable, non-regulated asbestos-containing material (ACM) and construction debris. The ACM was determined to be non-friable by waste characterization samples collected prior to closure activities. The ACM was removed and double-bagged by licensed, trained asbestos workers and transported to the Area 9 U10c Landfill for disposal. Construction debris was transported in end-dump trucks to the Area 9 U10c Landfill for disposal. Closure activities generated sanitary waste/construction debris and ACM. Waste generated during closure activities was appropriately managed and disposed. Waste characterization sample results are included as Appendix A of this report, and waste disposition documentation is included as Appendix B of this report. Copies of the Sectored Housekeeping Site Closure

Combining forest inventory, satellite remote sensing, and geospatial data for mapping forest attributes of the conterminous United States

Science.gov (United States)

Mark Nelson; Greg Liknes; Charles H. Perry

2009-01-01

Analysis and display of forest composition, structure, and pattern provides information for a variety of assessments and management decision support. The objective of this study was to produce geospatial datasets and maps of conterminous United States forest land ownership, forest site productivity, timberland, and reserved forest land. Satellite image-based maps of...

Economic impacts of the total nuclear waste management program envisioned for the United States

International Nuclear Information System (INIS)

Busch, L.; Zielen, A.J.; Parry, S.J.S.

1978-01-01

This paper presents information on the costs of nuclear waste management and on the impacts of those costs on the price of power and on the capital and labor markets. It is assumed that the LWR would be the sole commercial reactor used through the year 2000. Two fuel cycle options are considered: the throwaway mode (spent fuel is waste), and the full recycle for comparison. Total costs are calculated for all facilities needed to store, package, and reposit all the spent fuel through the lifetime of 380 GW capacity installed by 2000 and operating for 30 y. The economic impact is: the price of power produced by the reactors would be increased by 1.4%; the capital for nuclear plants would apply to waste management; the average annual labor effort needed over the next 50 to 75 years is 3000 to 5000 man years; and the unit cost of spent fuel disposal is $129/kg ($119/kg for full recycle). 7 tables

Thermodynamic investigation of waste heat driven desalination unit based on humidification dehumidification (HDH) processes

International Nuclear Information System (INIS)

He, W.F.; Xu, L.N.; Han, D.; Gao, L.; Yue, C.; Pu, W.H.

2016-01-01

Highlights: • HDH desalination system powered by waste heat is proposed. • Performance of the desalination unit and the relevant heat recovery effect is calculated. • Sensitive analysis of the performance for the HDH desalination system is investigated. • Mathematical model based on the first and second laws of thermodynamics is established. - Abstract: Humidification dehumidification (HDH) technology is an effective pattern to separate freshwater from seawater or brackish water. In this paper, a closed-air open-water (CAOW) desalination unit coupled with plate heat exchangers (PHEs) is applied to recover the waste heat from the gas exhaust. Sensitivity analysis for the HDH desalination unit as well as the PHEs from the key parameters including the top and initial temperature of the seawater, operation pressure, and the terminal temperature difference (TTD) of the PHEs are accomplished, and the corresponding performance of the whole HDH desalination system is calculated and presented. The simulation results show that the balance condition of the dehumidifier is allowed by the basic thermodynamic laws, followed by a peak value of gained-output-ratio (GOR) and a bottom value of total specific entropy generation. It is concluded that excellent results including the system performance, heat recovery effect and investment of the PHEs can be simultaneously obtained with a low top temperature, while the obtained desalination performance and the heat recovery effect from other measures are always conflicting. Different from other parameters of the desalination unit, the terminal temperature difference of the PHEs has little influences on the final value of GOR.

Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Birk, Sandra M.

1997-01-01

Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2009-07-31

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed

Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2009-01-01

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was

United States high-level radioactive waste management program: Current status and plans

International Nuclear Information System (INIS)

Williams, J.

1992-01-01

The inventory of spent fuel in storage at reactor sites in the United States is approximately 20,000 metric tons heavy metal (MTHM). It is increasing at a rate of 1700 to 2100 MTHM per year. According to current projections, by the time the last license for the current generation of nuclear reactors expires, there will be an estimated total of 84,000 MTHm. No commercial reprocessing capacity exists or is planned in the US. Therefore, the continued storage of spent fuel is required. The majority of spent fuel remains in the spent fuel pools of the utilities that generated it. Three utilities are presently supplementing pool capacity with on-site dry storage technologies, and four others are planning dry storage. Commercial utilities are responsible for managing their spent fuel until the Federal waste management system, now under development, accepts spent fuel for storage and disposal. Federal legislation charges the Office of Civilian Radioactive Waste Management (OCRWM) within the US Department of Energy (DOE) with responsibility for developing a system to permanently dispose of spent fuel and high level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. We are developing a waste management system consisting for three components: a mined geologic repository, with a projected start date of 2010; a monitored retrievable storage facility (MRS), scheduled to begin waste acceptance in 1998; and a transportation system to support MRS and repository operations. This paper discusses the background and framework for the program, as well as the current status and plans for management of spent nuclear fuel at commercial utilities; the OCRWM's development of a permanent geologic repository, an MRS, and a transportation system; the OCRWM's safety approach; the OCRWM's program management initiatives; and the OCRWM's external relations activities

Radioactive wastes and their disposal

International Nuclear Information System (INIS)

Neumann, L.

1984-01-01

The classification of radioactive wastes is given and the achievements evaluated in the disposal of radioactive wastes from nuclear power plants. An experimental pilot unit was installed at the Jaslovske Bohunice nuclear power plant for the bituminization of liquid radioactive wastes. UJV has developed a mobile automated high-output unit for cementation. In 1985 the unit will be tested at the Jaslovske Bohunice and the Dukovany nuclear power plants. A prototype press for processing solid wastes was manufactured which is in operation at the Jaslovske Bohunice plant. A solidification process for atypical wastes from long-term storage of spent fuel elements has been developed to be used for the period of nuclear power plant decommissioning. (E.S.)

MAPPING GLAUCONITE UNITES WITH USING REMOTE SENSING TECHNIQUES IN NORTH EAST OF IRAN

Directory of Open Access Journals (Sweden)

R. Ahmadirouhani

2014-10-01

Full Text Available Glauconite is a greenish ferric-iron silicate mineral with micaceous structure, characteristically formed in shallow marine environments. Glauconite has been used as a pigmentation agent for oil paint, contaminants remover in environmental studies and a source of potassium in plant fertilizers, and other industries. Koppeh-dagh basin is extended in Iran, Afghanistan and Turkmenistan countries and Glauconite units exist in this basin. In this research for enhancing and mapping glauconitic units in Koppeh-dagh structural zone in north east of Iran, remote sensing techniques such as Spectral Angle Mapper classification (SAM, band ratio and band composition methods on SPOT, ASTER and Landsat data in 3 steps were applied.

SEARCH AND MAPPING OF THE OLD BURIED TAILINGS WITH RADIOACTIVE WASTES AT THE URBAN TERRITORY.

Science.gov (United States)

Molchanov, O I; Soroka, Y N; Podrezov, A A; Soroka, M N

2017-11-01

The article presents results of investigation on search and mapping of the old buried tailings with radioactive wastes on the territory of Kamianske City. For solving the problem used complex of methods. These methods are as follows: soil-gas 222Rn measurement and measurement of 222Rn flux density from the ground surface, gamma-radiation survey, prospecting drilling, gamma-ray logging and laboratory analysis of radionuclides. The leading method in this complex was the method of soil-gas 222Rn measurement. Using this method location of the tailings has been precisely defined. The tailings boundaries have been contoured in the plan. Other methods permitted to define such parameters as thickness of the wastes, their volume (~330 000 m3), radionuclide and chemical composition. It was found that radioactive residues occur at a depth from 2 to 11 m and contain in its composition 226Ra, 210Pb and 210Po in the range from 8370 to 37 270 Bq kg-1. © The Author 2017. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Unit cell modeling in support of interim performance assessment for low level tank waste disposal

International Nuclear Information System (INIS)

Kline, N.W.

1996-01-01

A unit cell model is used to simulate the base analysis case and related sensitivity cases for the interim performance assessment of low level tank waste disposal. Simulation case results are summarized in terms of fractional contaminant release rates to the vadose zone and to the water table at the unconfined aquifer. Results suggest that the crushed glass water conditioning layer at the top of the facility and the chemical retardation pad at the bottom of the facility can be important components of the facility. Results also suggest that the release rates to the water table are dominated by the release rate from the waste form

Sorption-reagent treatment of brines produced by reverse osmosis unit for liquid radioactive waste management

International Nuclear Information System (INIS)

Avramenko, V. A.; Zheleznov, V. V.; Sergienko, V. I.; Chizhevsky, I. Yu

2003-01-01

The results of the pilot plant tests (2002-2003) of the sorption-reagent decontamination of high salinity radioactive waste (brines) remaining after the low-salinity liquid radioactive waste (LRW) treatment in the reverse-osmosis unit from long-lived radionuclides are presented. The sorption-reagent materials used in this work were developed in the Institute of Chemistry FEDRAS. They enable one to decontaminate brines with total salt content up to 50 g/l from long-lived radionuclides of Cs, Sr and Co. At joint application of the reverse-osmosis and sorption-reagent technologies total volume of solid radioactive waste (SRW) decreases up to 100-fold as compared to the technology of cementation of reverse osmosis brines. In this case total cost of LRW treatment and SRW disposal decreases more than 10-fold. Brines decontaminated from radionuclides are then diluted down to the ecologically safe total salts content in water to be disposed of. Tests were performed to compare the efficiency of technologies including evaporation of brines remaining after reverse osmosis process and their decontamination by means of the sorption-reagent method. It was shown that, as compared to evaporation, the sorption-reagent technology provides substantial advantages as in regard to radioactive waste total volume reduction as in view of total cost of the waste management

Development of solid radionuclide waste forms in the United States

International Nuclear Information System (INIS)

Crandall, J.L.

1979-01-01

New ways of reworking the wastes require a new classification in terms of the final waste forms. This paper surveys the candidate forms: encapsulation binders, in-place solidification waste forms, glass and ceramic waste forms, mineral waste forms, matrix waste forms, gaseous waste forms (fixation), and canisters and engineered barriers. Participants in the US-high-level waste form development program are listed. Requirements and selection of waste forms are also discussed. 26 references

Commercial processing and disposal alternatives for very low levels of radioactive waste in the United States

International Nuclear Information System (INIS)

Benda, G.A.

2005-01-01

The United States has several options available in the commercial processing and disposal of very low levels of radioactive waste. These range from NRC licensed low level radioactive sites for Class A, B and C waste to conditional disposal or free release of very low concentrations of material. Throughout the development of disposal alternatives, the US promoted a graded disposal approach based on risk of the material hazards. The US still promotes this approach and is renewing the emphasis on risk based disposal for very low levels of radioactive waste. One state in the US, Tennessee, has had a long and successful history of disposal of very low levels of radioactive material. This paper describes that approach and the continuing commercial options for safe, long term processing and disposal. (author)

Material Units, Structures/Landforms, and Stratigraphy for the Global Geologic Map of Ganymede (1:15M)

Science.gov (United States)

Patterson, G. Wesley; Head, James W.; Collins, Geoffrey C.; Pappalardo, Robert T.; Prockter, Louis M.; Lucchitta, Baerbel K.

2008-01-01

In the coming year a global geological map of Ganymede will be completed that represents the most recent understanding of the satellite on the basis of Galileo mission results. This contribution builds on important previous accomplishments in the study of Ganymede utilizing Voyager data and incorporates the many new discoveries that were brought about by examination of Galileo data. Material units have been defined, structural landforms have been identified, and an approximate stratigraphy has been determined utilizing a global mosaic of the surface with a nominal resolution of 1 km/pixel assembled by the USGS. This mosaic incorporates the best available Voyager and Galileo regional coverage and high resolution imagery (100-200 m/pixel) of characteristic features and terrain types obtained by the Galileo spacecraft. This map has given us a more complete understanding of: 1) the major geological processes operating on Ganymede, 2) the characteristics of the geological units making up its surface, 3) the stratigraphic relationships of geological units and structures, and 4) the geological history inferred from these relationships. A summary of these efforts is provided here.

Siting the high level radioactive waste repository in the United States

International Nuclear Information System (INIS)

Tourtellotte, J.

1992-01-01

For more than twenty-five years after the National Academy of Science issued its 1957 report recommending a Mined Geologic Disposal System (''MGDS'') for high level radioactive waste, no substantial progress was made in selecting and siting a repository. The United States Congress attempted to give substantive and procedural direction to the program in the Nuclear Waste Policy Act of 1982. Seeing that very little had been accomplished some five years later, Congress gave further direction and tentatively selected a single site, Yucca Mountain in Nevada, in the Nuclear Waste Policy Act Amendments of 1987. Selection of the Yucca Mountain site created a political conflict between federal and state authorities. Until recently, that conflict stalled the site characterization and evaluation program. Standards development under a polycentric regulatory regime has also been slow and has created a number of technical, legal and policy controversies. The Environmental Protection Agency (EPA), charged with setting radiation protection rules, may be developing regulatory standards which are technically unachievable and, therefore, legally unprovable in a licensing proceeding. The Nuclear Regulatory Commission (NRC), having the responsibility for licensing and setting performance objectives, may be taking an overly conservative approach. This approach could seriously impact the cost and may preclude the ability to reach an affirmative finding on license issuance. The Department of Energy (DOE) has responsibility for siting, construction and operation of the repository. In so doing, DOE must apply both EPA and NRC standards. To the extent that EPA and NRC standards are untimely, poorly defined, unrealistic, inconsistent, and technically or legally unsound, DOE may be forestalled from fulfilling its responsibilities. The US must rethink its approach to siting the high level radioactive waste repository and take realistic, timely action to preserve the nuclear option. (Author)

Sampling and analysis plan for remediation of Operable Unit 100-IU-3 waste site 600-104. Revision 1

International Nuclear Information System (INIS)

1997-08-01

This sampling and analysis plan presents the rationale and strategy for the sampling and analysis activities to support remediation of 100-IU-3 Operable Unit waste site 600-104. The purpose of the proposed sampling and analysis activities is to demonstrate that time-critical remediation of the waste site for soil containing 2,4-Dichlorophenoxyacetic acid salts and esters (2,4-D) and dioxin/furan isomers at concentrations that exceed cleanup levels has been effective. This shall be accomplished by sampling various locations of the waste site before and after remediation, analyzing the samples, and comparing the results to action levels set by the Washington State Department of Ecology

Molecular Monte Carlo Simulations Using Graphics Processing Units: To Waste Recycle or Not?

Science.gov (United States)

Kim, Jihan; Rodgers, Jocelyn M; Athènes, Manuel; Smit, Berend

2011-10-11

In the waste recycling Monte Carlo (WRMC) algorithm, (1) multiple trial states may be simultaneously generated and utilized during Monte Carlo moves to improve the statistical accuracy of the simulations, suggesting that such an algorithm may be well posed for implementation in parallel on graphics processing units (GPUs). In this paper, we implement two waste recycling Monte Carlo algorithms in CUDA (Compute Unified Device Architecture) using uniformly distributed random trial states and trial states based on displacement random-walk steps, and we test the methods on a methane-zeolite MFI framework system to evaluate their utility. We discuss the specific implementation details of the waste recycling GPU algorithm and compare the methods to other parallel algorithms optimized for the framework system. We analyze the relationship between the statistical accuracy of our simulations and the CUDA block size to determine the efficient allocation of the GPU hardware resources. We make comparisons between the GPU and the serial CPU Monte Carlo implementations to assess speedup over conventional microprocessors. Finally, we apply our optimized GPU algorithms to the important problem of determining free energy landscapes, in this case for molecular motion through the zeolite LTA.

Value Chain Development as Alternative Method For Mapping Waste Management

Directory of Open Access Journals (Sweden)

Muhammad Saiful Hakim

2017-06-01

Full Text Available Solid Waste management begin at the household as waste of consumption and ended as a new form of waste product or recycling. Based on its value chain the subsequent process will have distict differences with manufacturing product. Value chain of manufacturing product will characterize as value added chain along the chain, where every side of the chain will generate positive chain. In the other hand, some parties of waste management value chain will negative value existed. Some parties in this chain will generate negative value solely because they must establish some cost for wipe the waste. Dissimilarities between value chain on product and waste will contribute to discrepancy between parties. Main purpose of this research is to identify value chain from solid waste management using value chain development. Another purpose to accomplished is to resolve discrepancy in value chain.  Research results shown that household is the parties that experiences negative value. To minimize the discrepancies there should be an action towards household

Low- and intermediate level radioactive waste from Risoe, Denmark. Location studies for potential disposal areas. Report no. 1. Data, maps, models and methods used for selection of potential areas

Energy Technology Data Exchange (ETDEWEB)

Gravesen, P.; Nilsson, B.; Schack Pedersen, S.A.; Binderup, M.

2011-07-01

The low and intermediate level radioactive waste from Risoe (the nuclear reactor buildings plus different types of material from the research periods) and radioactive waste from hospitals and research institutes have to be stored in a final disposal in Denmark for at least 300 years. The Minister for Health and Prevention presented the background and decision plan for the Danish Parliament in January 2009. All political parties agreed on the plan. The investigation of geological deposits as potential waste disposals for high radioactive waste from nuclear power plants has earlier focused on deep seated salt deposits and basement rocks. Nevertheless, the Tertiary clays were mapped as well. In the present study, the salt diapirs and the salt deposits are not included. The present report briefly describes the existing data collections (including databases, maps and models), that are used during the work of selection of ca. 20 potentially suitable areas. Most of the information is stored in GEUS databases: Location of boreholes, borehole data, rock sediment and ground water compounds, maps, geophysical data and much more, but information is also collected from other institutions. The methods are described in more details (chapter 6) and this description is the direct background for the selection process, the characterisation of the 20 areas and for the final selection of the 2 or 3 most potential sites. (LN)

Low- and intermediate level radioactive waste from Risoe, Denmark. Location studies for potential disposal areas. Report no. 1. Data, maps, models and methods used for selection of potential areas

International Nuclear Information System (INIS)

Gravesen, P.; Nilsson, B.; Schack Pedersen, S.A.; Binderup, M.

2011-01-01

The low and intermediate level radioactive waste from Risoe (the nuclear reactor buildings plus different types of material from the research periods) and radioactive waste from hospitals and research institutes have to be stored in a final disposal in Denmark for at least 300 years. The Minister for Health and Prevention presented the background and decision plan for the Danish Parliament in January 2009. All political parties agreed on the plan. The investigation of geological deposits as potential waste disposals for high radioactive waste from nuclear power plants has earlier focused on deep seated salt deposits and basement rocks. Nevertheless, the Tertiary clays were mapped as well. In the present study, the salt diapirs and the salt deposits are not included. The present report briefly describes the existing data collections (including databases, maps and models), that are used during the work of selection of ca. 20 potentially suitable areas. Most of the information is stored in GEUS databases: Location of boreholes, borehole data, rock sediment and ground water compounds, maps, geophysical data and much more, but information is also collected from other institutions. The methods are described in more details (chapter 6) and this description is the direct background for the selection process, the characterisation of the 20 areas and for the final selection of the 2 or 3 most potential sites. (LN)

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2. Radioactive waste and laundry shipments. Volume 9. Summary status report

International Nuclear Information System (INIS)

Doerge, D.H.; Miller, R.L.; Scotti, K.S.

1986-05-01

This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 to May 5, 1985. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order

Broadening GHG accounting with LCA: application to a waste management business unit.

Science.gov (United States)

Fallaha, Sophie; Martineau, Geneviève; Bécaert, Valérie; Margni, Manuele; Deschênes, Louise; Samson, Réjean; Aoustin, Emmanuelle

2009-11-01

In an effort to obtain the most accurate climate change impact assessment, greenhouse gas (GHG) accounting is evolving to include life-cycle thinking. This study (1) identifies similarities and key differences between GHG accounting and life-cycle assessment (LCA), (2) compares them on a consistent basis through a case study on a waste management business unit. First, GHG accounting is performed. According to the GHG Protocol, annual emissions are categorized into three scopes: direct GHG emissions (scope 1), indirect emissions related to electricity, heat and steam production (scope 2) and other indirect emissions (scope 3). The LCA is then structured into a comparable framework: each LCA process is disaggregated into these three scopes, the annual operating activities are assessed, and the environmental impacts are determined using the IMPACT2002+ method. By comparing these two approaches it is concluded that both LCA and GHG accounting provide similar climate change impact results as the same major GHG contributors are determined for scope 1 emissions. The emissions from scope 2 appear negligible whereas emissions from scope 3 cannot be neglected since they contribute to around 10% of the climate change impact of the waste management business unit. This statement is strengthened by the fact that scope 3 generates 75% of the resource use damage and 30% of the ecosystem quality damage categories. The study also shows that LCA can help in setting up the framework for a annual GHG accounting by determining the major climate change contributors.

Acute and chronic environmental effects of clandestine methamphetamine waste.

Science.gov (United States)

Kates, Lisa N; Knapp, Charles W; Keenan, Helen E

2014-09-15

The illicit manufacture of methamphetamine (MAP) produces substantial amounts of hazardous waste that is dumped illegally. This study presents the first environmental evaluation of waste produced from illicit MAP manufacture. Chemical oxygen demand (COD) was measured to assess immediate oxygen depletion effects. A mixture of five waste components (10mg/L/chemical) was found to have a COD (130 mg/L) higher than the European Union wastewater discharge regulations (125 mg/L). Two environmental partition coefficients, K(OW) and K(OC), were measured for several chemicals identified in MAP waste. Experimental values were input into a computer fugacity model (EPI Suite™) to estimate environmental fate. Experimental log K(OW) values ranged from -0.98 to 4.91, which were in accordance with computer estimated values. Experimental K(OC) values ranged from 11 to 72, which were much lower than the default computer values. The experimental fugacity model for discharge to water estimates that waste components will remain in the water compartment for 15 to 37 days. Using a combination of laboratory experimentation and computer modelling, the environmental fate of MAP waste products was estimated. While fugacity models using experimental and computational values were very similar, default computer models should not take the place of laboratory experimentation. Copyright © 2014 Elsevier B.V. All rights reserved.

Mapping landscape units in Galicia (Spain: A first step for assessment and management?

Directory of Open Access Journals (Sweden)

Corbelle-Rico Eduardo

2017-12-01

Full Text Available In the beginning of 2015, the Regional Administration of Galicia (NW Spain set the requirements for a map of landscape units: it had to be produced in less than 3 months, it should cover the whole territory of the region (29,574 km², and it should be useful for management at a scale of 1:25,000. With these objectives in mind, we pro- posed a semiautomatic mapping methodology entirely based on the use of free software (GRASS GIS and already available cartographic information. Semi-automatic classification of different land-use patterns was at the heart of the proposed process. Consultation with experts of different academic background took place along the project. This consultation process allowed to identify both problems and opportunities. As it could be expected, the diverse epistemic community represented by the expert panel implied that one of the main challenges was to reach consensus on the understanding of the concept of landscape and the decisions leading to the mapping methodology proposed in this paper. This initiated a very interesting debate that, in our view, was centred around three main issues: the approach to the landscape, the purpose of the mapping exercise, and the ability to include subjectivity into the analysis.

Environmental performance evaluation of waste management system of Uranium Concentrated Unit in Caetite city, Bahia State - Brazil

International Nuclear Information System (INIS)

Araujo, Valeska P.; Fernandes, Horst M.; Gomiero, Luis Alberto

2005-01-01

The mining/milling activities have the potential to cause risks to the human health and to the environment. In uranium mining, besides inherent damages due to any mining activities there are radiological risks, that may be incurred even in short as in long terms. The large volumes of low activity mining/milling residues produced, are the great challenge in the waste management. Nowadays, the whole Brazilian uranium production come from Uranium Concentrated Unit (URA), a facility operated by Brazilian Nuclear Industry and located at a semi-arid region, in the Caetite city, Bahia state. This Unit is composed by a open pit mine and a milling facility. The present work assess the URA waste management system, the procedures adopted, focused on its environmental performance. It was observed that the waste management system is efficient in the control of the environmental impacts, however improvement chances are detected and a better performance may be reached. Concerning the liquids wastes, it was observed that the storage systems were not projected adequately. The storage capacity was not enough to support a intense rainfall period causing a overflow to the environment. In URA activities there is no radiological risk to the public, but its necessary to improve long term actions, constraints for the post-closure phase, e.g., appropriate institutional controls, restrictions on land use. Finally, it is advisable to introduce a Environmental Management System (EMS) for the whole facility. (author)

A Global Survey of Deep Underground Facilities; Examples of Geotechnical and Engineering Capabilities, Achievements, Challenges (Mines, Shafts, Tunnels, Boreholes, Sites and Underground Facilities for Nuclear Waste and Physics R&D): A Guide to Interactive Global Map Layers, Table Database, References and Notes

International Nuclear Information System (INIS)

Tynan, Mark C.; Russell, Glenn P.; Perry, Frank V.; Kelley, Richard E.; Champenois, Sean T.

2017-01-01

These associated tables, references, notes, and report present a synthesis of some notable geotechnical and engineering information used to create four interactive layer maps for selected: 1) deep mines and shafts; 2) existing, considered or planned radioactive waste management deep underground studies or disposal facilities 3) deep large diameter boreholes, and 4) physics underground laboratories and facilities from around the world. These data are intended to facilitate user access to basic information and references regarding “deep underground” facilities, history, activities, and plans. In general, the interactive maps and database provide each facility’s approximate site location, geology, and engineered features (e.g.: access, geometry, depth, diameter, year of operations, groundwater, lithology, host unit name and age, basin; operator, management organization, geographic data, nearby cultural features, other). Although the survey is not comprehensive, it is representative of many of the significant existing and historical underground facilities discussed in the literature addressing radioactive waste management and deep mined geologic disposal safety systems. The global survey is intended to support and to inform: 1) interested parties and decision makers; 2) radioactive waste disposal and siting option evaluations, and 3) safety case development applicable to any mined geologic disposal facility as a demonstration of historical and current engineering and geotechnical capabilities available for use in deep underground facility siting, planning, construction, operations and monitoring.

A Global Survey of Deep Underground Facilities; Examples of Geotechnical and Engineering Capabilities, Achievements, Challenges (Mines, Shafts, Tunnels, Boreholes, Sites and Underground Facilities for Nuclear Waste and Physics R&D): A Guide to Interactive Global Map Layers, Table Database, References and Notes

Energy Technology Data Exchange (ETDEWEB)

Tynan, Mark C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Russell, Glenn P. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Perry, Frank V. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kelley, Richard E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Champenois, Sean T. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-06-13

These associated tables, references, notes, and report present a synthesis of some notable geotechnical and engineering information used to create four interactive layer maps for selected: 1) deep mines and shafts; 2) existing, considered or planned radioactive waste management deep underground studies or disposal facilities 3) deep large diameter boreholes, and 4) physics underground laboratories and facilities from around the world. These data are intended to facilitate user access to basic information and references regarding “deep underground” facilities, history, activities, and plans. In general, the interactive maps and database provide each facility’s approximate site location, geology, and engineered features (e.g.: access, geometry, depth, diameter, year of operations, groundwater, lithology, host unit name and age, basin; operator, management organization, geographic data, nearby cultural features, other). Although the survey is not comprehensive, it is representative of many of the significant existing and historical underground facilities discussed in the literature addressing radioactive waste management and deep mined geologic disposal safety systems. The global survey is intended to support and to inform: 1) interested parties and decision makers; 2) radioactive waste disposal and siting option evaluations, and 3) safety case development applicable to any mined geologic disposal facility as a demonstration of historical and current engineering and geotechnical capabilities available for use in deep underground facility siting, planning, construction, operations and monitoring.

WIPP Facility Work Plan for Solid Waste Management Units

International Nuclear Information System (INIS)

2000-01-01

This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility's's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA. A

WIPP Facility Work Plan for Solid Waste Management Units

Energy Technology Data Exchange (ETDEWEB)

Washington TRU Solutions LLC

2000-02-25

This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED’s guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA

Closure Report for Corrective Action Unit 426: Cactus Spring Waste Trenches, Tonopah Test Range, Nevada

Energy Technology Data Exchange (ETDEWEB)

Dave Madsen

1998-08-01

This Closure Report provides the documentation for closure of the Cactus Spring Waste Trenches Corrective Action Unit (CAU) 426. The site is located on the Tonopah Test Range, approximately 225 kilometers northwest of Las Vegas, NV. CAU 426 consists of one corrective action site (CAS) which is comprised of four waste trenches. The trenches were excavated to receive solid waste generated in support of Operation Roller Coaster, primary the Double Tracks Test in 1963, and were subsequently backfilled. The Double Tracks Test involved use of live animals to assess the biological hazards associated with the nonnuclear detonation of plutonium-bearing devices. The Nevada Division of Environmental Protection approved Corrective Action Plan (CAP)which proposed ''capping'' methodology. The closure activities were completed in accordance with the approved CAP and consisted of constructing an engineered cover in the area of the trenches, constructing/planting a vegetative cover, installing a perimeter fence and signs, implementing restrictions on future use, and preparing a Post-Closure Monitoring Plan.

Predicting routes of radioactive wastes moved on the US railroad system

International Nuclear Information System (INIS)

Hillsman, E.L.; Johnson, P.E.; Peterson, B.E.

1980-01-01

One of the issues to be considered in the analysis of alternative repository sites for nuclear wastes is the pattern of shipments from reactors and other waste sources to the repository. In the United States, regulations and costs make rail shipments the preferred mode for high-level radioactive waste. The railroad network of the United States is owned by approximately 100 corporations that simultaneously compete for traffic and cooperate to move shipments that require carriage by more than one company. Because changing companies usually delays a shipment, there is a tendency to minimize the number of carriers involved in moving it. Moreover, when several carriers are required, the originating company (specified by the shipper) tends to retain the shipment on its portion of the network. These characteristics are nearly unique among the world's rail systems, and they must be recognized in any model of paths of future shipments through the network. This paper describes the development of a rail routing program that can be applied to the movement of radioactive materials throughout the United States. Shipments can be initiated at a specific location on a specific railroad. A route can be generated and displayed on a map of the United States. The particular route generated depends upon the emphasis placed on various classes of rail lines. Demonstration routings illustrate predicted routes of normal freight shipments, the effect of blocking passage through selected cities, and the effect that the existence of independent railroad companies can have on the patterns of shipments

Mixed waste treatment model: Basis and analysis

International Nuclear Information System (INIS)

Palmer, B.A.

1995-09-01

The Department of Energy's Programmatic Environmental Impact Statement (PEIS) required treatment system capacities for risk and cost calculation. Los Alamos was tasked with providing these capacities to the PEIS team. This involved understanding the Department of Energy (DOE) Complex waste, making the necessary changes to correct for problems, categorizing the waste for treatment, and determining the treatment system requirements. The treatment system requirements depended on the incoming waste, which varied for each PEIS case. The treatment system requirements also depended on the type of treatment that was desired. Because different groups contributing to the PEIS needed specific types of results, we provided the treatment system requirements in a variety of forms. In total, some 40 data files were created for the TRU cases, and for the MLLW case, there were 105 separate data files. Each data file represents one treatment case consisting of the selected waste from various sites, a selected treatment system, and the reporting requirements for such a case. The treatment system requirements in their most basic form are the treatment process rates for unit operations in the desired treatment system, based on a 10-year working life and 20-year accumulation of the waste. These results were reported in cubic meters and for the MLLW case, in kilograms as well. The treatment system model consisted of unit operations that are linked together. Each unit operation's function depended on the input waste streams, waste matrix, and contaminants. Each unit operation outputs one or more waste streams whose matrix, contaminants, and volume/mass may have changed as a result of the treatment. These output streams are then routed to the appropriate unit operation for additional treatment until the output waste stream meets the treatment requirements for disposal. The total waste for each unit operation was calculated as well as the waste for each matrix treated by the unit

Handling and treatment of low-level radioactive wastes from gaseous diffusion plants in the United States of America

International Nuclear Information System (INIS)

Wing, J.F.; Behrend, J.E.

1984-01-01

Gaseous diffusion plants in the United States of America currently generate very small quantities of low-level radioactive wastes. These wastes consist primarily of airborne effluent solid trapping media and liquid scrubber solutions, liquid effluent treatment sludges, waste oils and solvents, scrap metals and conventional combustible wastes such as floor sweepings, cleaning rags and shoe covers. In addition to waste emanating from current operations, large quantities of scrap metal generated during the Cascade Improvement Program are stored above ground at each of the diffusion plants. The radionuclides of primary concern are uranium and 99 Tc. Current radioactive waste treatment consists of uranium dissolution in weak acids followed by chemical precipitation and/or solvent extraction for uranium recovery. Current disposal operations consist of above ground storage of scrap metals, shallow land burial of inorganic solids and incineration of combustible wastes. With increased emphasis on reducing the potential for off-site radiological dose, several new treatment and disposal options are being studied and new projects are being planned. One project of particular interest involves the installation of a high temperature incinerator to thermally degrade hazardous organic wastes contaminated with low-level radioactive wastes. Other technologies being studied include fixation of uranium-bearing sludges in concrete before burial, decontamination of scrap metals by smelting and use of specially engineered centralized burial grounds. (author)

Biomass Maps | Geospatial Data Science | NREL

Science.gov (United States)

Biomass Maps Biomass Maps These maps illustrate the biomass resource in the United States by county . Biomass feedstock data are analyzed both statistically and graphically using a geographic information Data Science Team. Solid Biomass Resources Map of Total Biomass Resources in the United States Solid

An updated stress map of the continental United States reveals heterogeneous intraplate stress

Science.gov (United States)

Levandowski, Will; Herrmann, Robert B.; Briggs, Rich; Boyd, Oliver; Gold, Ryan

2018-06-01

Knowledge of the state of stress in Earth's crust is key to understanding the forces and processes responsible for earthquakes. Historically, low rates of natural seismicity in the central and eastern United States have complicated efforts to understand intraplate stress, but recent improvements in seismic networks and the spread of human-induced seismicity have greatly improved data coverage. Here, we compile a nationwide stress map based on formal inversions of focal mechanisms that challenges the idea that deformation in continental interiors is driven primarily by broad, uniform stress fields derived from distant plate boundaries. Despite plate-boundary compression, extension dominates roughly half of the continent, and second-order forces related to lithospheric structure appear to control extension directions. We also show that the states of stress in several active eastern United States seismic zones differ significantly from those of surrounding areas and that these anomalies cannot be explained by transient processes, suggesting that earthquakes are focused by persistent, locally derived sources of stress. Such spatially variable intraplate stress appears to justify the current, spatially variable estimates of seismic hazard. Future work to quantify sources of stress, stressing-rate magnitudes and their relationship with strain and earthquake rates could allow prospective mapping of intraplate hazard.

Mine waste management

International Nuclear Information System (INIS)

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

1992-01-01

This book reports on mine waste management. Topics covered include: Performance review of modern mine waste management units; Mine waste management requirements; Prediction of acid generation potential; Attenuation of chemical constituents; Climatic considerations; Liner system design; Closure requirements; Heap leaching; Ground water monitoring; and Economic impact evaluation

A remote characterization system for subsurface mapping of buried waste sites

International Nuclear Information System (INIS)

Sandness, G.A.; Bennett, D.W.

1992-10-01

Mapping of buried objects and regions of chemical and radiological contamination is required at US Department of Energy (DOE) buried waste sites. The DOE Office of Technology Development Robotics Integrated Program has initiated a project to develop and demonstrate a remotely controlled subsurface sensing system, called the Remote Characterization System (RCS). This project, a collaborative effort by five of the National Laboratories, involves the development of a unique low-signature survey vehicle, a base station, radio telemetry data links, satellite-based vehicle tracking, stereo vision, and sensors for non-invasive inspection of the surface and subsurface. To minimize interference with on-board sensors, the survey vehicle has been constructed predominatantly of non-metallic materials. The vehicle is self-propelled and will be guided by an operator located at a remote base station. The RCS sensors will be environmentally sealed and internally cooled to preclude contamination during use. Ground-penetrating radar, magnetometers, and conductivity devices are planned for geophysical surveys. Chemical and radiological sensors will be provided to locate hot spots and to provide isotopic concentration data

A Fire Severity Mapping System (FSMS) for real-time management applications and long term planning: Developing a map of the landscape potential for severe fire in the western United States

Science.gov (United States)

Gregory K. Dillon; Zachary A. Holden; Penny Morgan; Bob Keane

2009-01-01

The Fire Severity Mapping System project is geared toward providing fire managers across the western United States with critical information for dealing with and planning for the ecological effects of wildfire at multiple levels of thematic, spatial, and temporal detail. For this project, we are developing a comprehensive, west-wide map of the landscape potential for...

On palaeogeographic map

Directory of Open Access Journals (Sweden)

Zeng-Zhao Feng

2016-01-01

Full Text Available The palaeogeographic map is a graphic representation of physical geographical characteristics in geological history periods and human history periods. It is the most important result of palaeogeographic study. The author, as the Editor-in-Chief of Journal of Palaeogeography, Chinese Edition and English Edition, aimed at the problems of the articles submitted to and published in the Journal of Palaeogeography in recent years and the relevant papers and books of others, and integrated with his practice of palaeogeographic study and mapping, wrote this paper. The content mainly includes the data of palaeogeographic mapping, the problems of palaeogeographic mapping method, the “Single factor analysis and multifactor comprehensive mapping method —— Methodology of quantitative lithofacies palaeogeography”, i.e., the “4 steps mapping method”, the nomenclature of each palaeogeographic unit in palaeogeographic map, the explanation of each palaeogeographic unit in palaeogeographic map, the explanation of significance of palaeogeographic map and palaeogeographic article, the evaluative standards of palaeogeographic map and palaeogeographic article, and the self-evaluation. Criticisms and corrections are welcome.

Draft postclosure permit application for Bear Creek Hydrogeologic Regime at the Oak Ridge Y-12 Plant Oil Landform Hazardous Waste Disposal Unit

International Nuclear Information System (INIS)

1991-08-01

The Oil Landfarm Hazardous-Waste Disposal Unit (HWDU) is located approximately one and one-half miles west of the Department of Energy's (DOE) Y-12 Plant in Oak Ridge, Tennessee. The Oil Landfarm HWDU consists of three disposal plots and along with the Bear Creek Burial Grounds and the S-3 Site comprise the Bear Creek Valley Waste Disposal Area (BCVWDA). The facility was used for the biological degradation of waste oil and machine coolants via landfarming, a process involving the application of waste oils and coolants to nutrient-adjusted soil during the dry months of the year (April to October). The Oil Landfarm HWDU has been closed as a hazardous-waste disposal unit and therefore will be subject to post-closure care. The closure plan for the Oil Landfarm HWDU is provided in Appendix A.1. A post-closure plan for the Oil Landfarm HWDU is presented in Appendix A.2. The purpose of this plan is to identify and describe the activities that will be performed during the post-closure care period. This plan will be implemented and will continue throughout the post-closure care period

WIPP Sampling and Analysis Plan for Solid Waste Management Units and Areas of Concern

International Nuclear Information System (INIS)

2000-01-01

This Sampling and Analysis Plan (SAP) has been prepared to fulfill requirements of Module VII, Section VII.M.2 and Table VII.1, requirement 4 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED [New Mexico Environment Department], 1999a). This SAP describes the approach for investigation of the Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. This SAP addresses the current Permit requirements for a RCRA Facility Investigation(RFI) investigation of SWMUs and AOCs. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the RFI specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI work plan and report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can beentered either before or after a RFI work plan. According to NMED's guidance, a facility can prepare a RFI work plan or SAP for any SWMU or AOC (NMED, 1998).

The radioactive waste debate in the United States and nuclear technology for peaceful purposes

Science.gov (United States)

Tehan, Terrence Norbert

Many ethical, cultural, and economic concerns have accompanied the rapid growth of Western technology. Nuclear technology in particular has experienced considerable opposition because of its perceived dangers, especially disposal of atomic waste. While this field of science remains in its infancy, many legal, political and ecological groups oppose any further application of nuclear technology--including the significant medical, environmental, and economic benefits possible from a safe and responsible application of nuclear energy. Complete and objective knowledge of this technology is needed to balance a healthy respect for the danger of atomic power with its many advantages. This study focuses on one aspect of nuclear technology that has particularly aroused political and social controversy: nuclear waste. Finding ways of disposing safely of nuclear waste has become an extremely volatile issue because of the popular misconception that there is no permanent solution to this problem. This investigation will demonstrate that the supposedly enduring waste problem has been resolved in several industrial countries that now outstrip the United States in safe commercial applications of nuclear science. This dissertation offers a reasoned and objective contribution to the continuing national debate on the peaceful uses of nuclear technology. This debate becomes more crucial as the nation seeks a dependable substitute for the non-renewable sources of energy now rapidly being exhausted.

X/Qs and unit dose calculations for Central Waste Complex interim safety basis effort

International Nuclear Information System (INIS)

Huang, C.H.

1996-01-01

The objective for this problem is to calculate the ground-level release dispersion factors (X/Q) and unit doses for onsite facility and offsite receptors at the site boundary and at Highway 240 for plume meander, building wake effect, plume rise, and the combined effect. The release location is at Central Waste Complex Building P4 in the 200 West Area. The onsite facility is located at Building P7. Acute ground level release 99.5 percentile dispersion factors (X/Q) were generated using the GXQ. The unit doses were calculated using the GENII code. The dimensions of Building P4 are 15 m in W x 24 m in L x 6 m in H

Geologic Map of the Hellas Region of Mars

Science.gov (United States)

Leonard, Gregory J.; Tanaka, Kenneth L.

2001-01-01

and mapped (table 1). The new classification scheme includes broad, geographically related categories and local, geologically and geomorphically related subgroups. Because of our mapping at larger scale, many of our map units were incorporated within larger units of the global-scale mapping (see table 1). Available Viking images of the Hellas region vary greatly in several aspects, which has complicated the task of producing a consistent photogeologic map. Best available image resolution ranges from about 30 to 300 m/pixel from place to place. Many images contain haze caused by dust clouds, and contrast and shading vary among images because of dramatic seasonal changes in surface albedo, opposing sun azimuths, and solar inclination. Enhancement of selected images on a computer-display system has greatly improved our ability to observe key geologic relations in several areas. Determination of the geologic history of the region includes reconstruction of the origin and sequence of formation, deformation, and modification of geologic units constituting (1) the impact-basin rim and surrounding highlands, (2) volcanic and channel assemblages on the northeast and south sides of the basin, (3) interior basin deposits, and (4) slope and surficial materials throughout the map area. Various surface modifications are attributed to volcanic, fluvial, eolian, mass-wasting, and possibly glacial and periglacial processes. Structures include basin faults (mostly inferred), wrinkle ridges occurring mainly in volcanic terrains and interior plains, volcanic collapse craters, and impact craters. Our interpretations in some cases rely on previous work, but in many significant cases we have offered new interpretations that we believe are more consistent with the observations documented by our mapping. Our primary intent for this mapping has been to elucidate the history of emplacement and modification of Hellas Planitia materials, which form the basis for analysis of their r

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

International Nuclear Information System (INIS)

Grant Evenson

2008-01-01

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: (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. 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: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct

PENERAPAN LEAN MANUFACTURING UNTUK MEREDUKSI WASTE DI INDUSTRI SKALA UKM

Directory of Open Access Journals (Sweden)

Darminto Pujotomo

2012-08-01

Full Text Available Lean Manufacturing merupakan konsep manufaktur untuk menghasilkan produk yang efisien dengan mengurangi biaya produksi melalui efisiensi. Dalam konsep Lean, dikenal 7 macam pemborosan yang meliputi produksi berlebih, transportasi material yang berlebihan, menunggu, proses yang tidak perlu, persediaan, pergerakan dan cacat produk. Penelitian ini menggunakan value stream mapping dalam mengidentifikasi pemborosan dan menelusuri potensi terjadinya pemborosan. Potensi pemborosan yang terjadi akan direduksi dengan menggunakan instrumen yang sesuai berdasarkan indikator terpilih. Penelitian diharapkan dapat menghasilkan proses produksi yang lebih efisiensi sehingga mampu mereduksi biaya produksi. Pada akhirnya akan menghasilkan profit yang lebih besar. Kata kunci : lean manufacturing, value stream mapping, waste   Lean Manufacturing is a manufacturing concepts to produce products that are efficient by reducing production costs through efficiencies. In the Lean concept, known seven kinds of waste, including overproduction, excessive material transportation, waiting, unnecessary processes, inventory, motion and product defects. This study uses value stream mapping to identify waste and exploring the potential for waste. Potential waste that occurs will be reduced by using appropriate instruments based on selected indicators. The study is expected to produce a more efficient production processes so as to reduce production costs.Will ultimately result in greater profits. Keywords: lean manufacturing, value stream mapping, waste

Corrective action investigation plan for Corrective Action Unit Number 427: Area 3 septic waste system numbers 2 and 6, Tonopah Test Range, Nevada

International Nuclear Information System (INIS)

1997-01-01

This Corrective Action Investigation Plan (CAIP) contains the environmental sample collection objectives and the criteria for conducting site investigation activities at the Area 3 Compound, specifically Corrective Action Unit (CAU) Number 427, which is located at the Tonopah Test Range (TTR). The TTR, included in the Nellis Air Force Range, is approximately 255 kilometers (140 miles) northwest of Las Vegas, Nevada. The Corrective Action Unit Work Plan, Tonopah Test Range, Nevada divides investigative activities at TTR into Source Groups. The Septic Tanks and Lagoons Group consists of seven CAUs. Corrective Action Unit Number 427 is one of three septic waste system CAUs in TTR Area 3. Corrective Action Unit Numbers 405 and 428 will be investigated at a future data. Corrective Action Unit Number 427 is comprised of Septic Waste Systems Number 2 and 6 with respective CAS Numbers 03-05-002-SW02 and 03-05-002-SW06

Restoration of pyritic colliery waste with sewage sludge in the Midlands coalfield, England, United Kingdom

International Nuclear Information System (INIS)

Humphries, R.N.; McQuire, G.E.; Sly, M.

1994-01-01

A trial was set up in 1990 in the Midlands coalfield in the United Kingdom (UK) to evaluate the use of sewage sludge to revegetate colliery waste tips containing 1--2% sulfur as iron pyrites. The rate of sewage sludge application is currently restricted by legislation and codes of practice to maximum concentrations of potentially toxic elements (copper, nickel, zinc, etc.) in the soil or waste after application. Following this guidance, an application rate of 250 mt/ha dry solids was applied at the trial site. At this rate, the colliery waste became extremely acidic pH <4.0. From experience elsewhere, much higher levels have been found to be necessary to control acidification in the absence of other measures or treatments. In view of the restriction on the amount of sewage sludge that can be applied, it is recommended that the current practice of covering fresh colliery wastes with soil or low sulfur spoil to a minimum depth of 0.45m is continued in the UK. Where this is not possible, the sludge must always be applied with sufficient neutralizing agent to control the potential acidity. If the acidity cannot be maintained above pH 5.0, the guidelines do not permit the application of sewage sludge

Technology transfer and radioactive waste management at TMI-2 [Three Mile Island Unit 2

International Nuclear Information System (INIS)

Saunders, J.R.

1988-01-01

The accident that occurred on March 28, 1979, at the Three Mile Island Unit 2 (TMI-2) nuclear generating station caused extensive damage to the reactor core and created high radiation contamination levels throughout the facility. The electric power industry, regulators, and government agencies were faced with one of the most technically challenging recovery situations ever encountered in this country. But it was also realized that this adversity presented opportunities for the advancement of state-of-the-art technologies as well as the potential to produce information that could enhance nuclear power plant safety and reliability. Perhaps one of the more significant aspects of the TMI-2 recovery has been the advancement of radioactive waste management technology. The high levels and unusual nature of the TMI-2 radioactive waste necessitated the development of innovative techniques for processing, packaging, shipping, and disposal. The investment in research was rewarded with large volume reductions and associated cost savings. It is anticipated that the TMI-2 radioactive waste management technology will make major contributions to the design of new systems to meet this growing need. The following areas appear particularly suited for this purpose: volume reduction, high-integrity containers, and selective isotope removal

Integration of formal and informal sector (waste bank in waste management system in Yogyakarta, Indonesia

Directory of Open Access Journals (Sweden)

Purnama Putra Hijrah

2018-01-01

Full Text Available The change of waste management paradigm becomes an important thing to do, as a step adaptation to the increasing rate of waste generation every year in Indonesia. 100% management target has been divided into two parts, namely the reduction (30% and waste handling (70%. Reductions focus on source limitation and 3R program optimization, whereas handling involves collecting and final processing activities. However, the current level of waste reduction is still very low (12%, the government made various efforts to increase it, one of its with the waste bank program. DIY province as a pioneer in the concept of waste bank continues to develop to increase the participation of the community, from 166 locations in 2013, increased to 792 locations in 2017 and 495 of its as the waste bank (62.5%. Average waste bank with 43 customers, able to manage the waste up to 2,078,064 kg/month, with the data can be estimated the amount of waste that can be managed in the city of Yogyakarta, Sleman and Bantul Regency. The city of Yogyakarta has 433 units of the waste bank, capable of managing waste up to 899,801.8 kg/month, Sleman Regency has 34 units of the waste bank (78.966,4 kg/month and Bantul has 24 units of the waste bank (49.873,5 kg/month. The integration of formal and informal sectors through waste banks can increase the percentage of waste management services. The level of service in Yogyakarta City increased from 85% to 95.5%, Sleman District from 30.71 to 31%, and Bantul Regency from 7.49 to 7.7%

Waste Encapsulation and Storage Facility (WESF) Waste Analysis Plan

International Nuclear Information System (INIS)

SIMMONS, F.M.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Waste Encapsulation and Storage Facility (WESF) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (3), (4), (5), and (6). WESF is an interim status other storage-miscellaneous storage unit. WESF stores mixed waste consisting of radioactive cesium and strontium salts. WESF is located in the 200 East Area on the Hanford Facility. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

Combined landslide inventory and susceptibility assessment based on different mapping units: an example from the Flemish Ardennes, Belgium

Directory of Open Access Journals (Sweden)

M. Van Den Eeckhaut

2009-03-01

Full Text Available For a 277 km² study area in the Flemish Ardennes, Belgium, a landslide inventory and two landslide susceptibility zonations were combined to obtain an optimal landslide susceptibility assessment, in five classes. For the experiment, a regional landslide inventory, a 10 m × 10 m digital representation of topography, and lithological and soil hydrological information obtained from 1:50 000 scale maps, were exploited. In the study area, the regional inventory shows 192 landslides of the slide type, including 158 slope failures occurred before 1992 (model calibration set, and 34 failures occurred after 1992 (model validation set. The study area was partitioned in 2.78×10⁶ grid cells and in 1927 topographic units. The latter are hydro-morphological units obtained by subdividing slope units based on terrain gradient. Independent models were prepared for the two terrain subdivisions using discriminant analysis. For grid cells, a single pixel was identified as representative of the landslide depletion area, and geo-environmental information for the pixel was obtained from the thematic maps. The landslide and geo-environmental information was used to model the propensity of the terrain to host landslide source areas. For topographic units, morphologic and hydrologic information and the proportion of lithologic and soil hydrological types in each unit, were used to evaluate landslide susceptibility, including the depletion and depositional areas. Uncertainty associated with the two susceptibility models was evaluated, and the model performance was tested using the independent landslide validation set. An heuristic procedure was adopted to combine the landslide inventory and the susceptibility zonations. The procedure makes optimal use of the available landslide and susceptibility information, minimizing the limitations inherent in the inventory and the susceptibility maps. For the established susceptibility classes, regulations to

Combined landslide inventory and susceptibility assessment based on different mapping units: an example from the Flemish Ardennes, Belgium

Science.gov (United States)

van den Eeckhaut, M.; Reichenbach, P.; Guzzetti, F.; Rossi, M.; Poesen, J.

2009-03-01

For a 277 km2 study area in the Flemish Ardennes, Belgium, a landslide inventory and two landslide susceptibility zonations were combined to obtain an optimal landslide susceptibility assessment, in five classes. For the experiment, a regional landslide inventory, a 10 m × 10 m digital representation of topography, and lithological and soil hydrological information obtained from 1:50 000 scale maps, were exploited. In the study area, the regional inventory shows 192 landslides of the slide type, including 158 slope failures occurred before 1992 (model calibration set), and 34 failures occurred after 1992 (model validation set). The study area was partitioned in 2.78×106 grid cells and in 1927 topographic units. The latter are hydro-morphological units obtained by subdividing slope units based on terrain gradient. Independent models were prepared for the two terrain subdivisions using discriminant analysis. For grid cells, a single pixel was identified as representative of the landslide depletion area, and geo-environmental information for the pixel was obtained from the thematic maps. The landslide and geo-environmental information was used to model the propensity of the terrain to host landslide source areas. For topographic units, morphologic and hydrologic information and the proportion of lithologic and soil hydrological types in each unit, were used to evaluate landslide susceptibility, including the depletion and depositional areas. Uncertainty associated with the two susceptibility models was evaluated, and the model performance was tested using the independent landslide validation set. An heuristic procedure was adopted to combine the landslide inventory and the susceptibility zonations. The procedure makes optimal use of the available landslide and susceptibility information, minimizing the limitations inherent in the inventory and the susceptibility maps. For the established susceptibility classes, regulations to link terrain domains to appropriate land

Radioactive Wastes. Revised.

Science.gov (United States)

Fox, Charles H.

This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. This booklet deals with the handling, processing and disposal of radioactive wastes. Among the topics discussed are: The Nature of Radioactive Wastes; Waste Management; and Research and Development. There are…

Community Solutions for Solid Waste Pollution, Level 6. Teacher Guide. Operation Waste Watch.

Science.gov (United States)

Virginia State Dept. of Waste Management, Richmond. Div. of Litter & Recycling.

Operation Waste Watch is a series of seven sequential learning units which addresses the subject of litter control and solid waste management. Each unit may be used in a variety of ways, depending on the needs and schedules of individual schools, and may be incorporated into various social studies, science, language arts, health, mathematics, and…

Development of a high integrity container for storage, transportation, and disposal of radioactive wastes from Three Mile Island unit II

International Nuclear Information System (INIS)

Holzworth, R.E.; Chapman, R.L.; Burton, H.M.; Bixby, W.W.

1981-01-01

The EPICOR II ion exchange system used to decontaminate approximately 1900 m 3 of contaminated water in the Auxiliary and Fuel Handling Building (AFHB) generated 50 highly loaded and 22 lesser loaded organic resin liners. The 22 lesser loaded resins were shipped to a commercial disposal site, but the highly loaded liners have been stored on the island since their generation. One highly loaded liner, or prefilter, was shipped to Battelle Columbus Laboratories (BCL) in May, 1981 as part of the United States Department of Energy (DOE) Three Mile Island Information and Examination Program. The prefilter is being characterized to determine the behavior of the waste form with respect to time and the internal environment and to provide an information base for use in management and regulatory decisions relative to the storage, processing, and disposal of these wastes. Due to the unique characteristics of these wastes, the US DOE is sponsoring programs, such as the BCL Sorbent Experiments Program, to evaluate their characteristics and to provide a High Integrity Container (HIC) Development Program which would improve waste suitability for disposal at a land burial facility. This paper addresses regulatory considerations, establishment of design criteria, proposed design concepts, system demonstration, and status of the HIC Development Program for storage, transportation, and disposal of high specific activity, low level radioactive wastes from Three Mile Island Unit II as typified by EPICOR II ion exchange media and liners

Data layer integration for the national map of the united states

Science.gov (United States)

Usery, E.L.; Finn, M.P.; Starbuck, M.

2009-01-01

The integration of geographic data layers in multiple raster and vector formats, from many different organizations and at a variety of resolutions and scales, is a significant problem for The National Map of the United States being developed by the U.S. Geological Survey. Our research has examined data integration from a layer-based approach for five of The National Map data layers: digital orthoimages, elevation, land cover, hydrography, and transportation. An empirical approach has included visual assessment by a set of respondents with statistical analysis to establish the meaning of various types of integration. A separate theoretical approach with established hypotheses tested against actual data sets has resulted in an automated procedure for integration of specific layers and is being tested. The empirical analysis has established resolution bounds on meanings of integration with raster datasets and distance bounds for vector data. The theoretical approach has used a combination of theories on cartographic transformation and generalization, such as T??pfer's radical law, and additional research concerning optimum viewing scales for digital images to establish a set of guiding principles for integrating data of different resolutions.

Guidelines for mixed waste minimization

International Nuclear Information System (INIS)

Owens, C.

1992-02-01

Currently, there is no commercial mixed waste disposal available in the United States. Storage and treatment for commercial mixed waste is limited. Host States and compacts region officials are encouraging their mixed waste generators to minimize their mixed wastes because of management limitations. This document provides a guide to mixed waste minimization

Mapping Changes in a Recovering Mine Site with Hyperspectral Airborne HyMap Imagery (Sotiel, SW Spain

Directory of Open Access Journals (Sweden)

Jorge Buzzi

2014-04-01

Full Text Available Hyperspectral high spatial resolution HyMap data are used to map mine waste from massive sulfide ore deposits, mostly abandoned, on the Iberian Pyrite Belt (southwest Spain. Mine dams, mill tailings and mine dumps in variable states of pyrite oxidation are recognizable. The interpretation of hyperspectral remote sensing requires specific algorithms able to manage high dimensional data compared to multispectral data. The routine of image processing methods used to extract information from hyperspectral data to map geological features is explained, as well as the sequence of algorithms used to produce maps of the mine sites. The mineralogical identification capability of algorithms to produce maps based on archive spectral libraries is discussed. Trends of mineral growth differ spectrally over time according to the geological setting and the recovery state of the mine site. Subtle mineralogical changes are enhanced using the spectral response as indicators of pyrite oxidation intensity of the mine waste piles and pyrite mud tailings. The changes in the surface of the mill tailings deserve a detailed description, as the surfaces are inaccessible to direct observation. Such mineralogical changes respond faithfully to industrial activities or the influence of climate when undisturbed by human influence.

WIPP Sampling and Analysis Plan for Solid Waste Management Units and Areas of Concern

Energy Technology Data Exchange (ETDEWEB)

None, None

2000-05-23

This Sampling and Analysis Plan (SAP) has been prepared to fulfill requirements of Module VII, Section VII.M.2 and Table VII.1, requirement 4 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED [New Mexico Environment Department], 1999a). This SAP describes the approach for investigation of the Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. This SAP addresses the current Permit requirements for a RCRA Facility Investigation(RFI) investigation of SWMUs and AOCs. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the RFI specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI work plan and report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can beentered either before or after a RFI work plan. According to NMED's guidance, a facility can prepare a RFI work plan or SAP for any SWMU or AOC (NMED, 1998).

Use of a tangential filtration unit for processing liquid waste from nuclear laundries

International Nuclear Information System (INIS)

Augustin, X.; Buzonniere, A. de; Barnier, H.

1993-01-01

Nuclear laundries produce large quantities of weakly contaminated effluents charged with insoluble and soluble products. In collaboration with CEA, TECHNICATOME has developed an ultrafiltration process for liquid waste from nuclear laundries, associated with prior in-solubilization of the radiochemical activity. This process 'seeded ultrafiltration' is based on the use of decloggable mineral filter media and combines very high separation efficiency with long membrane life. The efficiency of the tangential filtration unit which has been processing effluents from the Cadarache Nuclear Research Center (CEA-France) nuclear laundry since mid-1988, has been confirmed on several sites

Road-map to successful implementation of geological disposal in the EU

International Nuclear Information System (INIS)

Patrakka, Eero

2010-01-01

In the conclusions from its first meeting in Bratislava (2007), the European Nuclear Energy Forum (ENEF) identified the management of spent fuel and radioactive waste as an important subject to be looked into with the objective 'to encourage Member States and industry to swiftly implement adequate nuclear waste disposal facilities, in particular deep geological repositories for high level waste'. To this end the Sub-Working Group 'Waste Management' (SWG-WM) was created in the context of the ENEF Working Group 'Risks'. As a first task, the SWG-WM was requested to compile a road-map that includes the essential elements of what is required at national level to foster the implementation of geological disposal for high level waste and spent fuel. In October 2009, a 'Road-map to Successful Implementation of Geological Disposal in the EU' was endorsed. The aim of this document is to provide guidance to EU Member States that are starting out or are at an early stage on the decades-long process leading towards the implementation of geological repositories for high level radioactive wastes or spent nuclear fuel, if this is deemed to be a waste. The guidance is based to a large extent on the positive progress that has been made in a number of Member States. Small and new nuclear states may take a long time to reach such a position - but a strong message of this Road-map is that the process should be initiated as soon as possible. The Road-map is intended to be generic enough to be applicable to all Member States, independently of their current position; the national Road-maps to be developed should be compatible with this, but will differ in the specifics of approach and of timing. (authors)

SOLID WASTE MANAGEMENT IN TABRIZ PETROCHEMICAL COMPLEX

OpenAIRE

M. A. Abduli, M. Abbasi, T. Nasrabadi, H. Hoveidi, N. Razmkhah

2006-01-01

Tabriz petrochemical complex is located in the northwest of Iran. Major products of this industry include raw plastics like, polyethylene, polystyrene, acrylonitrile, butadiene, styrene, etc. Sources of waste generation include service units, health and cure units, water, power, steam and industrial processes units. In this study, different types of solid waste including hazardous and non hazardous solid wastes were investigated separately. The aim of the study was to focus on the management ...

Data analytics approach to create waste generation profiles for waste management and collection.

Science.gov (United States)

Niska, Harri; Serkkola, Ari

2018-04-30

Extensive monitoring data on waste generation is increasingly collected in order to implement cost-efficient and sustainable waste management operations. In addition, geospatial data from different registries of the society are opening for free usage. Novel data analytics approaches can be built on the top of the data to produce more detailed, and in-time waste generation information for the basis of waste management and collection. In this paper, a data-based approach based on the self-organizing map (SOM) and the k-means algorithm is developed for creating a set of waste generation type profiles. The approach is demonstrated using the extensive container-level waste weighting data collected in the metropolitan area of Helsinki, Finland. The results obtained highlight the potential of advanced data analytic approaches in producing more detailed waste generation information e.g. for the basis of tailored feedback services for waste producers and the planning and optimization of waste collection and recycling. Copyright © 2018 Elsevier Ltd. All rights reserved.

Status of United States civilian waste management program

International Nuclear Information System (INIS)

Lawrence, M.J.

1984-01-01

The Nuclear Waste Policy Act of 1982 confirms the Federal responsibility for nuclear waste management and provides for unprecedented involvement by States, Indian tribes and the public. The Act provides a comprehensive framework for disposing of spent nuclear fuel and high-level radioactive wastes of domestic origin generated by civilian nuclear power reactors. It establishes detailed schedules and procedures for selecting and developing geologic repositories; provides a mechanism for financing the cost of disposal; and sets forth other provisions relating to nuclear waste disposal. The other provisions of the Act include provision for a user-financed federal interim storage facility with time and quantity limitations, as well as strict Nuclear Regulatory Commission-prescribed eligibility criteria; a proposal for a Federally-owned and operated monitored retrievable storage (MRS) facility for the interim period prior to operation of a permanent repository; and provision for a Test and Evaluation Facility (TEF). This paper centers on the schedule and current status and siting of the first two geologic repositories

Chemicals, metals, and pesticide pits waste unit low induction number electromagnetic survey

Energy Technology Data Exchange (ETDEWEB)

Cumbest, R.J.; Mohon, D.

1995-06-01

An electromagnetic survey was conducted at the Chemicals, Metals, and Pesticide Waste Unit to identify any buried metallic objects that may be present in the materials used to fill and cover the pits after removal of pit debris. The survey was conducted with a Geonics EM-31 Terrain Conductivity Meter along north - south oriented traverses with 5-ft station intervals to produce a 5-ft by 5-ft square grid node pattern. Both conductivity and in-phase components were measured at each station for vertical dipole orientation with the common axis of the dipoles in the north - south and east - west orientations. The conductivity data clearly show elevated conductivities (2.1 to 7.0 mS/m) associated with the material over the pits, as compared with the surrounding area that is characterized by lower conductivities (1 to 2 mS/m). This is probably the result of the higher clay content of the fill material relative to the surrounding area, which has a higher sand to clay ratio and the presence of a plastic cover beneath the fill that has probably trapped water. Many metal objects are present in the survey area including manhole covers, monitoring well heads, metal, signs, drain culverts, abandoned wells, and BP waste unit marker balls. AU of these exhibit associated conductivity and in-phase anomalies of various magnitude. In addition to these anomalies that can be definitely associated with surface sources, conductivity and in-phase anomalies are also present with no obvious surface source. These anomalies are probably indicative of subsurface buried metallic objects. A high concentration of these objects appears to be present in the southwest corner of the survey area.

Waste Area Group 10, Operable Unit 10-08, Remedial Investigation/Feasibility Study Annual Status Report for Fiscal Year 2006

Energy Technology Data Exchange (ETDEWEB)

R. P. Wells

2007-05-09

This report provides a status of the progress made in Fiscal Year 2006 on tasks identified in the Waste Area Group 10, Operable Unit 10-08, Remedial Investigation/Feasibility Study Work Plan. Major accomplishments include: (1) groundwater sampling and review of the groundwater monitoring data, (2) installation of a Sitewide groundwater-level monitoring network, (3) update of the Groundwater Monitoring and Field Sampling Plan of Operable Unit 10-08, (4) re-evaluation of the risk at Site TSF-08, (5) progress on the Operable Unit 10-08 Sitewide Groundwater Model.

Demonstration of volumetric analysis using the topographical mapping system at Hanford

International Nuclear Information System (INIS)

Armstrong, G.A.; Burks, B.L.; Carteret, B.A.; Pardini, A.F.; Samuel, T.J.

1997-07-01

During the spring of 1997, the Topographical Mapping System (TMS) for hazardous and radiological environments was used to perform volumetric measurements of simulated waste in the cold test cell in the Fuel Materials and Examination Facility at the Hanford site. The TMS was used to measure the volume of five simulated waste mounds. Custom software designed by Oak Ridge National Laboratory was used to calculate the volume of waste from the surface maps supplied by the TMS. The results of the measurements were analyzed using the Interactive Computer-Enhanced Remote-Viewing System (ICERVS) and were documented. Development of the TMS and ICERVS was initiated by the US Department of Energy (DOE) for the purpose of characterization and remediation of underground storage tanks (USTs) at DOE sites across the country. DOE required a three-dimensional TMS suitable for use in hazardous and radiological environments. The intended application is the mapping of the interior of USTs as part of DOE's waste characterization and remediation efforts to obtain baseline data on the content of storage tank interiors as well as on changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford site, the TMS was designed to be a self-contained, compact, and reconfigurable system that is capable of providing rapid, variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention. An appendix contains the source code for calculating the volume from two surface maps

Waste volume reduction by acid digestion

International Nuclear Information System (INIS)

Lerch, R.E.; Divine, J.R.

1975-06-01

Acid digestion is a process being developed at the Hanford Engineering Development Laboratory (HEDL) in Richland, Washington, to reduce the volume of alpha-contaminated combustible waste by converting it into a non-combustible residue. Typical waste materials such as polyvinylchloride (PVC), polyethylene, paper and other cellulosic materials, ion exchange resin, all types of rubber, etc., are digested in hot (230 0 C--270 0 C) concentrated sulfuric acid containing nitric acid oxidant to form inert residues generally having less than four percent of their original volume and less than twenty-five percent of their original mass. The process is currently being tested using non-radioactive waste in an Acid Digestion Test Unit (ADTU) with all glass equipment. Engineering tests to date have shown acid digestion to be a potentially attractive method for treating combustible waste materials. Based on results of the engineering tests, an acid digestion pilot unit capable of treating radioactive wastes is being designed and constructed. Design capacity of the pilot unit for radioactive waste will be 100 kg of waste per day. (U.S.)

224-T Transuranic Waste Storage and Assay Facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-01-01

Westinghouse Hanford Company is a major contractor to the US Department of Energy Richland Field Office and serves as cooperator of the 224-T Transuranic Waste Storage and Assay Facility, the storage unit addressed in this permit application. At the time of submission of this portion of the Hanford Facility. Dangerous Waste Permit Application covering the 224-T Transuranic Waste Storage and Assay Facility, many issues identified in comments to the draft Hanford Facility Dangerous Waste Permit remain unresolved. This permit application reflects the positions taken by the US Department of Energy, Company on the draft Hanford Facility Dangerous Waste Permit and may not be read to conflict with those comments. The 224-T Transuranic Waste Storage and Assay Facility Dangerous Waste Permit Application (Revision 0) consists of both a Part A and Part B permit application. An explanation of the Part A revisions associated with this unit, including the Part A revision currently in effect, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987). The 224-T Transuranic Waste Storage and Assay Facility Dangerous Waste Permit Application contains information current as of March 1, 1992

SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT

Energy Technology Data Exchange (ETDEWEB)

TW, CRAWFORD

2008-07-17

This study evaluates parameters relevant to River Protection Project secondary waste streams generated during Early Low Activity Waste operations and recommends a strategy for secondary waste management that considers groundwater impact, cost, and programmatic risk. The recommended strategy for managing River Protection Project secondary waste is focused on improvements in the Effiuent Treatment Facility. Baseline plans to build a Solidification Treatment Unit adjacent to Effluent Treatment Facility should be enhanced to improve solid waste performance and mitigate corrosion of tanks and piping supporting the Effiuent Treatment Facility evaporator. This approach provides a life-cycle benefit to solid waste performance and reduction of groundwater contaminants.

Transient electromagnetic mapping of clay units in the San Luis Valley, Colorado

Science.gov (United States)

Fitterman, David V.; Grauch, V.J.S.

2010-01-01

Transient electromagnetic soundings were used to obtain information needed to refine hydrologic models of the San Luis Valley, Colorado. The soundings were able to map an aquitard called the blue clay that separates an unconfined surface aquifer from a deeper confined aquifer. The blue clay forms a conductor with an average resistivity of 6.9 ohm‐m. Above the conductor are found a mixture of gray clay and sand. The gray clay has an average resistivity of 21 ohm‐m, while the sand has a resistivity of greater than 100 ohm‐m. The large difference in resistivity of these units makes mapping them with a surface geophysical method relatively easy. The blue clay was deposited at the bottom of Lake Alamosa which filled most of the San Luis Valley during the Pleistocene. The geometry of the blue clay is influenced by a graben on the eastern side of the valley. The depth to the blue clay is greater over the graben. Along the eastern edge of valley the blue clay appears to be truncated by faults.

The First Global Geological Map of Mercury

Science.gov (United States)

Prockter, L. M.; Head, J. W., III; Byrne, P. K.; Denevi, B. W.; Kinczyk, M. J.; Fassett, C.; Whitten, J. L.; Thomas, R.; Ernst, C. M.

2015-12-01

Geological maps are tools with which to understand the distribution and age relationships of surface geological units and structural features on planetary surfaces. Regional and limited global mapping of Mercury has already yielded valuable science results, elucidating the history and distribution of several types of units and features, such as regional plains, tectonic structures, and pyroclastic deposits. To date, however, no global geological map of Mercury exists, and there is currently no commonly accepted set of standardized unit descriptions and nomenclature. With MESSENGER monochrome image data, we are undertaking the global geological mapping of Mercury at the 1:15M scale applying standard U.S. Geological Survey mapping guidelines. This map will enable the development of the first global stratigraphic column of Mercury, will facilitate comparisons among surface units distributed discontinuously across the planet, and will provide guidelines for mappers so that future mapping efforts will be consistent and broadly interpretable by the scientific community. To date we have incorporated three major datasets into the global geological map: smooth plains units, tectonic structures, and impact craters and basins >20 km in diameter. We have classified most of these craters by relative age on the basis of the state of preservation of morphological features and standard classification schemes first applied to Mercury by the Mariner 10 imaging team. Additional datasets to be incorporated include intercrater plains units and crater ejecta deposits. In some regions MESSENGER color data is used to supplement the monochrome data, to help elucidate different plains units. The final map will be published online, together with a peer-reviewed publication. Further, a digital version of the map, containing individual map layers, will be made publicly available for use within geographic information systems (GISs).

Utilizing Multi-Sensor Fire Detections to Map Fires in the United States

Science.gov (United States)

Howard, S. M.; Picotte, J. J.; Coan, M. J.

2014-11-01

In 2006, the Monitoring Trends in Burn Severity (MTBS) project began a cooperative effort between the US Forest Service (USFS) and the U.S.Geological Survey (USGS) to map and assess burn severity all large fires that have occurred in the United States since 1984. Using Landsat imagery, MTBS is mandated to map wildfire and prescribed fire that meet specific size criteria: greater than 1000 acres in the west and 500 acres in the east, regardless of ownership. Relying mostly on federal and state fire occurrence records, over 15,300 individual fires have been mapped. While mapping recorded fires, an additional 2,700 "unknown" or undocumented fires were discovered and assessed. It has become apparent that there are perhaps thousands of undocumented fires in the US that are yet to be mapped. Fire occurrence records alone are inadequate if MTBS is to provide a comprehensive accounting of fire across the US. Additionally, the sheer number of fires to assess has overwhelmed current manual procedures. To address these problems, the National Aeronautics and Space Administration (NASA) Applied Sciences Program is helping to fund the efforts of the USGS and its MTBS partners (USFS, National Park Service) to develop, and implement a system to automatically identify fires using satellite data. In near real time, USGS will combine active fire satellite detections from MODIS, AVHRR and GOES satellites with Landsat acquisitions. Newly acquired Landsat imagery will be routinely scanned to identify freshly burned area pixels, derive an initial perimeter and tag the burned area with the satellite date and time of detection. Landsat imagery from the early archive will be scanned to identify undocumented fires. Additional automated fire assessment processes will be developed. The USGS will develop these processes using open source software packages in order to provide freely available tools to local land managers providing them with the capability to assess fires at the local level.

Review of radioactive waste management programs in the United Kingdom

International Nuclear Information System (INIS)

Keen, N.J.; Duncan, A.G.

1982-01-01

The paper reports progress by the Department of Environment and the nuclear industry in developing and implementing a strategy for the management of radioactive waste in the UK. It outlines the range of possible disposal facilities required to deal with all classes of waste arising from nuclear power generation. The present practices for waste management and the main lines of development by the main waste producers of the plant needed in future are outlined, together with a summary of some of the more generic R and D devoted to treatment, packaging and transport of wastes

Current Status of the United Kingdom Programme for Long-Term Radioactive Waste Management

International Nuclear Information System (INIS)

Murray, C. H.; Hooper, A. J.; Mathieson, J.

2002-01-01

In 1997, the UK programme for the deep disposal of radioactive waste was ''stopped dead in its tracks'' with the refusal by the Secretary of State for the Environment to allow Nirex to go ahead with its plans for an underground Rock Characterisation Facility at Sellafield in north-west England. Since that time a House of Lords' Select Committee has held an inquiry into what went wrong and what the way ahead should be. In addition, Nirex and the nuclear industry players have also been analyzing the past with a view to learning from the experience in taking things forward. In Nirex's view this is essentially an ethical issue; the waste exists and we should deal with it in this generation. Three areas need to be better addressed if a successful program of management of the nation's radioactive waste is to be achieved: the process of how policy development and implementation can be achieved; the structure of the nuclear industry and its relationship to the waste management organization; and the behavior of the players in their interaction with stakeholders. All three are underpinned by the need for transparency. In recognition that developing a policy for managing radioactive waste has to be achieved with the support of all stakeholders, the Government instigated a consultation exercise in September 2001. The initial phase of this initiative is essentially a consultation about consultation and is intended to decide on how the next stages of a six year policy development program should be addressed. In addition to this exercise, the Government is undertaking a fundamental review of the structuring of the United Kingdom Atomic Energy Authority (UKAEA) and British Nuclear Fuels plc (BNFL). They are both shareholders in Nirex and in November 2001 the Government announced the setting up of a Liabilities Management Authority (LMA) to manage the long-term nuclear liabilities that are publicly owned, particularly through those organizations. The future of Nirex will be

Decree from July 1, 2015 approving decision nr 2015-DC-0508 taken by the Nuclear Safety Authority on April 21, 2015 related to the study on waste management and to the assessment of wastes produced in basic nuclear installations

International Nuclear Information System (INIS)

Blanc, P.

2015-01-01

After a definition of the concerned installations, this decree contains the definition of the content of the study of waste management and of assessment of produced wastes which must be performed for each installation. It notably specifies the various definitions and terminology used for this study, defines the study of waste management (objectives, content, elaboration and update modalities, measures related to general exploitation rules), describes the waste zoning map (generalities, elaboration, signalling, prevention of contamination transfers and of material activation, control of the relevance of the waste zoning map and of the compliance of its reference map, downgrading or regrading of waste zoning), and addresses the content of the assessment of waste management (generalities, content, elaboration modalities)

Corrective Action Investigation Plan for Corrective Action Unit 428: Area 3 Septic Waste Systems 1 and 5, Tonopah Test Range, Nevada

International Nuclear Information System (INIS)

ITLV

1999-01-01

The Corrective Action Investigation Plan for Corrective Action Unit 428, Area 3 Septic Waste Systems 1 and 5, has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the U. S. Department of Energy, Nevada Operations Office; the State of Nevada Division of Environmental Protection; and the U. S. Department of Defense. Corrective Action Unit 428 consists of Corrective Action Sites 03- 05- 002- SW01 and 03- 05- 002- SW05, respectively known as Area 3 Septic Waste System 1 and Septic Waste System 5. This Corrective Action Investigation Plan is used in combination with the Work Plan for Leachfield Corrective Action Units: Nevada Test Site and Tonopah Test Range, Nevada , Rev. 1 (DOE/ NV, 1998c). The Leachfield Work Plan was developed to streamline investigations at leachfield Corrective Action Units by incorporating management, technical, quality assurance, health and safety, public involvement, field sampling, and waste management information common to a set of Corrective Action Units with similar site histories and characteristics into a single document that can be referenced. This Corrective Action Investigation Plan provides investigative details specific to Corrective Action Unit 428. A system of leachfields and associated collection systems was used for wastewater disposal at Area 3 of the Tonopah Test Range until a consolidated sewer system was installed in 1990 to replace the discrete septic waste systems. Operations within various buildings at Area 3 generated sanitary and industrial wastewaters potentially contaminated with contaminants of potential concern and disposed of in septic tanks and leachfields. Corrective Action Unit 428 is composed of two leachfield systems in the northern portion of Area 3. Based on site history collected to support the Data Quality Objectives process, contaminants of potential concern for the site include oil/ diesel range total petroleum hydrocarbons, and Resource Conservation

Using the Large Fire Simulator System to map wildland fire potential for the conterminous United States

Science.gov (United States)

LaWen Hollingsworth; James Menakis

2010-01-01

This project mapped wildland fire potential (WFP) for the conterminous United States by using the large fire simulation system developed for Fire Program Analysis (FPA) System. The large fire simulation system, referred to here as LFSim, consists of modules for weather generation, fire occurrence, fire suppression, and fire growth modeling. Weather was generated with...

Floodplain Mapping for the Continental United States Using Machine Learning Techniques and Watershed Characteristics

Science.gov (United States)

Jafarzadegan, K.; Merwade, V.; Saksena, S.

2017-12-01

Using conventional hydrodynamic methods for floodplain mapping in large-scale and data-scarce regions is problematic due to the high cost of these methods, lack of reliable data and uncertainty propagation. In this study a new framework is proposed to generate 100-year floodplains for any gauged or ungauged watershed across the United States (U.S.). This framework uses Flood Insurance Rate Maps (FIRMs), topographic, climatic and land use data which are freely available for entire U.S. for floodplain mapping. The framework consists of three components, including a Random Forest classifier for watershed classification, a Probabilistic Threshold Binary Classifier (PTBC) for generating the floodplains, and a lookup table for linking the Random Forest classifier to the PTBC. The effectiveness and reliability of the proposed framework is tested on 145 watersheds from various geographical locations in the U.S. The validation results show that around 80 percent of total watersheds are predicted well, 14 percent have acceptable fit and less than five percent are predicted poorly compared to FIRMs. Another advantage of this framework is its ability in generating floodplains for all small rivers and tributaries. Due to the high accuracy and efficiency of this framework, it can be used as a preliminary decision making tool to generate 100-year floodplain maps for data-scarce regions and all tributaries where hydrodynamic methods are difficult to use.

Identifikasi Waste Pada Proses Produksi Key Set Clarinet Dengan Pendekatan Lean Manufacturing

Directory of Open Access Journals (Sweden)

Dana Marsetiya Utama

2016-07-01

Full Text Available This study discusses lean manufacturing concept to identify waste in Key Set Clarinet production process at Yamaha Musical Products Indonesia, Ltd. The lean manufacturing concept is done intially by big picture mapping, waste assessment model (WAM, value stream mapping (VSM and cause and effect diagram respectively. The results show that the dominant waste is defect (26.04%, motion (19.34%, inventory (19.22%, and waiting (13.91%.

Geologic Mapping of the Av-11 Pinaria Quadrangle of Asteroid 4 Vesta

Science.gov (United States)

Schenk, P.; Hoogenboom, T.; Williams, D.; Yingst, R. A.; Jaumann, R.; Gaskell, R.; Preusker, F.; Nathues, A.; Roatsch, T.

2012-04-01

As part of the Dawn's orbital mapping investigation of Vesta, the Science Team is conducting geologic mapping of the surface in the form of 15 quadrangle maps, including quadrangle Av-11 (Pinaria). The base map is a monochrome Framing Camera (FC) mosaic at ~70 m/pixel, supplemented by Digital Terrain Models (DTM) and FC color ratio images, both at ~250 m/pixel, slope and contour maps, and Visible and Infrared (VIR) hyperspectral images. Av-11 straddles the 45-degree longitude in the South Polar Region, and is dominated by the rim of the ~505 km south polar topographic feature, Rheasilvia. Sparsely cratered (relatively), Av-11 is dominated by a 20 km high rim scarp (Matronalia Rupes) and by arcuate ridges and troughs forming a radial to spiral pattern across the basin floor. Primary geologic features of Av-11 include the following. Ridge-and-groove terrain radiating arcuately from the central mound unit, interpreted to be structural disruption of the basin floor associated with basin formation. The largest crater in Av-11 is Pinaria (37 km). Mass wasting deposits are observed on its floor. Secondary crater chains and fields are also evident. Mass wasting observed along Rheasilvia rim scarp and in the largest craters indicates scarp failure is a significant process. Parallel fault scarps mark this deposit of slumped debris at the base of 20 km high Matronalia Rupes, which may have formed during or shortly after basin excavation. We interpret most of these deposits as slump material emplaced as a result of the effects of basin formation and collapse. Lobate materials are characterized by lineations and lobate scarps and interpreted as Rheasilvia ejecta deposit outside Rheasilvia rim (the smoothest terrain on Vesta), and are consistent with formation by ejecta. Partial burial of older craters near the edge of these deposits are also observed.

Evapotranspiration Cover for the 92-Acre Area Retired Mixed Waste Pits, Area 5 Waste Management Division, Nevada National Security Site, Final CQA Report

International Nuclear Information System (INIS)

2012-01-01

The report is the Final Construction Quality Assurance (CQA) Report for the 92-Acrew Evapotranspiration Cover, Area 5 Waste Management Division Retired Mixed Waste Pits, Nevada National Security Site, Nevada, for the period of January 20, 2011, to January 31, 2012 The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. The 92-Acre Area encompasses the southern portion of the Area 5 RWMS, which has been designated for the first final closure operations. This area contains 13 Greater Confinement Disposal (GCD) boreholes, 16 narrow trenches, and 9 broader pits. With the exception of two active pits (P03 and P06), all trenches and pits in the 92-Acre Area had operational covers approximately 2.4 meters thick, at a minimum, in most areas when this project began. The units within the 92-Acre Area are grouped into the following six informal categories based on physical location, waste types and regulatory requirements: (1) Pit 3 Mixed Waste Disposal Unit (MWDU); (2) Corrective Action Unit (CAU) 111; (3) CAU 207; (4) Low-level waste disposal units; (5) Asbestiform low-level waste disposal units; and (6) One transuranic (TRU) waste trench.

Membrane Treatment of Liquid Salt Bearing Radioactive Wastes

International Nuclear Information System (INIS)

Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

2003-01-01

The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value

Waste analysis plan for T Plant Complex

International Nuclear Information System (INIS)

Williams, J.F.

1996-01-01

Washington Administration Code 173-303-300 requires that a waste analysis plan (WAP) be provided by a treatment, storage, and/or disposal (TSD) unit to confirm their knowledge about a dangerous and/or mixed waste to ensure that the waste is managed properly. The specific objectives of the WAP are as follows: Ensure safe management of waste during treatment and storage; Ensure that waste generated during operational activities is properly designated in accordance with regulatory requirements; Provide chemical and physical analysis of representative samples of the waste stored for characterization and/or verification before the waste is transferred to another TSD unit; Ensure compliance with land disposal restriction (LDR) requirements for treated waste; and Provide basis for work plans that describes waste analysis for development of new treatment technologies

Commercial and Industrial Solid Waste Incineration Units (CISWI): New Source Performance Standards (NSPS) and Emission Guidelines (EG) for Existing Sources

Science.gov (United States)

Learn about the New Source Performance Standards (NSPS) for commercial and industrial solid waste incineration (CISWI) units including emission guidelines and compliance times for the rule. Read the rule history and summary, and find supporting documents

Value Stream Mapping to Improve Workplace to support Lean Environment

Directory of Open Access Journals (Sweden)

Ahmad Ahmad Nur Aizat

2017-01-01

Full Text Available In recent years, lean manufacturing is being followed by various sectors in order to keep their competitiveness in the global markets. Lean manufacturing plays a vital role in improving the efficiency of operation by eliminating or reducing wastes. Nonetheless, most of small and medium enterprises (SMEs lack sufficient knowledge or information on the benefits of implementing lean manufacturing. The main objective of this study is to apply value stream mapping, one of lean manufacturing tools, for improving the productivity in a SME by eliminating non-value added activities. In this study, lean manufacturing was adopted at a SME, particularly a food industry. Value stream mapping was served as main tool to identify the wastes and improvement opportunities in production line. Subsequently, different lean manufacturing tools such as Kaizen Burst, one piece flow, and 5S were applied to eliminate or reduce identified wastes. Based on the future state value stream mapping, final results showed that the total operation time and non-added value activities time were successfully decreased from 1993 seconds to 1719 seconds, and 234 seconds to 104 seconds, respectively. The findings of this study indicate that value stream mapping is an effective approach to eliminate the wastes and improve the productivity.

Community Solutions to Solid Waste Pollution. Operation Waste Watch: The New Three Rs for Elementary School. Grade 6. [Second Edition.

Science.gov (United States)

Virginia State Dept. of Waste Management, Richmond. Div. of Litter & Recycling.

This publication, the last in a series of seven for elementary schools, is an environmental education curriculum guide with a focus on waste management issues. It contains a unit of exercises selected for sixth grade students focusing on community solutions to solid waste pollution. Waste management activities included in this unit seek to…

Commercial waste treatment R and D needs in the United States

International Nuclear Information System (INIS)

Burkholder, H.C.

1982-05-01

The mission of the commercial waste treatment program is to establish treatment technology for safe and efficient management of high-level and transuranic wastes from reprocessing and fuel fabrication and special wastes from other fuel cycle activities. The four functional objectives that must be achieved to fulfill the mission are: (1) define waste product and treatment process performance requirements; (2) specify adequately safe waste products and verify their performance; (3) specify adequately efficient treatment processes and equipment and verify their performance; (4) solve existing waste treatment problems using verified products and processes. Although commercial waste treatment technology is in many respects highly advanced, there remains a number of areas where significant research and development is needed. These are: (1) technically-based performance requirements for both waste products and treatment processes; (2) pilot-scale radioactive demonstration of liquid-fed ceramic melting process and equipment for borosilicate glass; (3) non-glass TRU waste product and treatment process development; (4) waste product performance testing and predictive modeling; (5) quality verification for treatment processes

Using MCDA and GIS for hazardous waste landfill siting considering land scarcity for waste disposal

International Nuclear Information System (INIS)

Feo, Giovanni De; Gisi, Sabino De

2014-01-01

Highlights: • Wasting land for the siting of hazardous waste landfills must be avoided. • The siting procedure is based on a land use map of potentially suitable areas. • All the waste facilities of the management system are simultaneously considered. • A case study is developed considering two multi-criteria techniques. • An innovative criteria weighting tool (PSW) is used in combination with the AHP. - Abstract: The main aim of this study was to develop a procedure that minimizes the wasting of space for the siting of hazardous waste landfills as part of a solid waste management system. We wanted to tackle the shortage of land for waste disposal that is a serious and growing problem in most large urban regions. The procedure combines a multi-criteria decision analysis (MCDA) approach with a geographical information system (GIS). The GIS was utilised to obtain an initial screening in order to eliminate unsuitable areas, whereas the MCDA was developed to select the most suitable sites. The novelty of the proposed siting procedure is the introduction of a new screening phase before the macro-siting step aimed at producing a “land use map of potentially suitable areas” for the siting of solid waste facilities which simultaneously takes into consideration all plant types. The issue of obtaining sites evaluations of a specific facility was coupled with the issue of not wasting land appropriate to facilitate other types of waste management options. In the developed case study, the use of an innovative criteria weighting tool (the “Priority Scale”) in combination with the Analytic Hierarchy Process was useful to easier define the priorities of the evaluation criteria in comparison with other classic methods such as the Paired Comparison Technique in combination with the Simple Additive Weighting method

Using MCDA and GIS for hazardous waste landfill siting considering land scarcity for waste disposal

Energy Technology Data Exchange (ETDEWEB)

Feo, Giovanni De, E-mail: g.defeo@unisa.it [Department of Industrial Engineering, University of Salerno, via Giovanni Paolo II, 132, 84084 Fisciano, SA (Italy); Gisi, Sabino De [Italian National Agency for New Technologies, Energy and Sustainable Economic Development, ENEA, Water Resource Management Lab., via Martiri di Monte Sole 4, 40129 Bologna, BO (Italy)

2014-11-15

Highlights: • Wasting land for the siting of hazardous waste landfills must be avoided. • The siting procedure is based on a land use map of potentially suitable areas. • All the waste facilities of the management system are simultaneously considered. • A case study is developed considering two multi-criteria techniques. • An innovative criteria weighting tool (PSW) is used in combination with the AHP. - Abstract: The main aim of this study was to develop a procedure that minimizes the wasting of space for the siting of hazardous waste landfills as part of a solid waste management system. We wanted to tackle the shortage of land for waste disposal that is a serious and growing problem in most large urban regions. The procedure combines a multi-criteria decision analysis (MCDA) approach with a geographical information system (GIS). The GIS was utilised to obtain an initial screening in order to eliminate unsuitable areas, whereas the MCDA was developed to select the most suitable sites. The novelty of the proposed siting procedure is the introduction of a new screening phase before the macro-siting step aimed at producing a “land use map of potentially suitable areas” for the siting of solid waste facilities which simultaneously takes into consideration all plant types. The issue of obtaining sites evaluations of a specific facility was coupled with the issue of not wasting land appropriate to facilitate other types of waste management options. In the developed case study, the use of an innovative criteria weighting tool (the “Priority Scale”) in combination with the Analytic Hierarchy Process was useful to easier define the priorities of the evaluation criteria in comparison with other classic methods such as the Paired Comparison Technique in combination with the Simple Additive Weighting method.

Photogeologic study of small-scale linear features near a potential nuclear-waste repository site at Yucca Mountain, southern Nye County, Nevada

International Nuclear Information System (INIS)

Throckmorton, C.K.

1987-01-01

Linear features were mapped from 1:2400-scale aerial photographs of the northern half of the potential underground nuclear-waste repository site at Yucca Mountain by means of a Kern PG 2 stereoplotter. These features were thought to be the expression of fractures at the ground surface (fracture traces), and were mapped in the caprock, upper lithophysal, undifferentiated lower lithophysal and hackly units of the Tiva Canyon Member of the Miocene Paintbrush Tuff. To determine if the linear features corresponded to fracture traces observed in the field, stations (areas) were selected on the map where the traces were both abundant and located solely within one unit. These areas were visited in the field, where fracture-trace bearings and fracture-trace lengths were recorded. Additional data on fracture-trace length and fracture abundance, obtained from ground-based studies of cleared pavements located within the study area were used to help evaluate data collected for this study. 16 refs., 4 figs., 2 tabs

Introduction to Waste Engineering

DEFF Research Database (Denmark)

Christensen, Thomas Højlund

2011-01-01

Solid waste management as introduced in Chapter 1.1 builds in many ways on engineering. Waste engineering here means the skills and ability to understand quantitatively how a waste management system works in such a detail that waste management can be planned, facilities can be designed and sited......) regional plans for waste management, including (3) the selection of main management technologies and siting of facilities, (4) the design of individual technological units and, for example, (5) the operation of recycling schemes within a municipality. This chapter gives an introduction to waste engineering...

Pilot research projects for underground disposal of radioactive wastes in the United States of America

International Nuclear Information System (INIS)

Stein, R.; Collyer, P.L.

1984-01-01

Disposal of commercial radioactive waste in the United States of America in a deep underground formation will ensure permanent isolation from the biosphere with minimal post-closure surveillance and maintenance. The siting, design and development, performance assessment, operation, licensing, certification and decommissioning of an underground repository have stimulated the development of several pilot research projects throughout the country. These pilot tests and projects, along with their resulting data base, are viewed as important steps in the overall location and construction of a repository. Beginning in the 1960s, research at pilot facilities has progressed from underground spent fuel tests in an abandoned salt mine to the production of vitrified nuclear waste in complex borosilicate glass logs. Simulated underground repository experiments have been performed in the dense basalts of Washington State, the volcanic tuffaceous rock of Nevada and both domal and bedded salts of Louisiana and Kansas. In addition to underground pilot in situ tests, other facilities have been constructed or modified to monitor the performance of spent fuel in dry storage wells and self-shielded concrete casks. As the National Waste Terminal Storage (NWTS) programme advances to the next stage of underground site characterization for each of three different geological sites, additional pilot facilities are under consideration. These include a Test and Evaluation Facility (TEF) for site verification and equipment performance and testing, as well as a salt testing facility for verification of in situ simulation equipment. Although not associated with the NWTS programme, the construction of the Waste Isolation Pilot Plant (WIPP) in the bedded salts of New Mexico is well under way for deep testing and experimentation with the defence programme's transuranic nuclear waste. (author)

The radionuclide content of radioactive wastes

International Nuclear Information System (INIS)

1988-06-01

This report presents the radionuclide content of stocks and arisings of radioactive wastes in the United Kingdom. Operational and decommissioning wastes are considered for both committed and prospective plant. Arisings are from power reactors, commercial reprocessing, fuel manufacture, medical and industrial sources and research and development. Data is included from Amersham International, British Nuclear Fuels, Central Electricity Generating Board, South of Scotland Electricity Board, United Kingdom Atomic Energy Authority and minor waste producers. (author)

Factors driving the development of healthcare waste management in the United Kingdom over the past 60 years.

Science.gov (United States)

Townend, William K; Cheeseman, Christopher; Edgar, Jen; Tudor, Terry

2009-06-01

Since the creation of the National Health Service (NHS) in the United Kingdom in 1948 there have been significant changes in the way waste materials produced by healthcare facilities have been managed due to a number of environmental, legal and social drivers. This paper reviews the key changes in legislation and healthcare waste management that have occurred in the UK between 1948 and the present time. It investigates reasons for the changes and how the problems associated with healthcare wastes have been addressed. The reaction of the public to offensive disposal practices taking place locally required political action by the UK government and subsequently by the European legislature. The relatively new UK industry of hazardous healthcare waste management has developed rapidly over the past 25 years in response to significant changes in healthcare practices. The growth in knowledge and appreciation of environmental issues has also been fundamental to the development of this industry. Legislation emanating from Europe is now responsible for driving change to UK healthcare waste management. This paper examines the drivers that have caused the healthcare waste management to move forward in the 60 years since the NHS was formed. It demonstrates that the situation has moved from a position where there was no overall strategy to the current situation where there is a strong regulatory framework but still no national strategy. The reasons for this situation are examined and based upon the experience gained; suggestions are made for the benefit of countries with systems for healthcare waste management still in the early stages of development or without any provisions at all.

Global Geological Map of Venus

Science.gov (United States)

Ivanov, M. A.

2008-09-01

Introduction: The Magellan SAR images provide sufficient data to compile a geological map of nearly the entire surface of Venus. Such a global and selfconsistent map serves as the base to address the key questions of the geologic history of Venus. 1) What is the spectrum of units and structures that makes up the surface of Venus [1-3]? 2) What volcanic/tectonic processes do they characterize [4-7]? 3) Did these processes operated locally, regionally, or globally [8- 11]? 4) What are the relationships of relative time among the units [8]? 5) At which length-scale these relationships appear to be consistent [8-10]? 6) What is the absolute timing of formation of the units [12-14]? 7) What are the histories of volcanism, tectonics and the long-wavelength topography on Venus? 7) What model(s) of heat loss and lithospheric evolution [15-21] do these histories correspond to? The ongoing USGS program of Venus mapping has already resulted in a series of published maps at the scale 1:5M [e.g. 22-30]. These maps have a patch-like distribution, however, and are compiled by authors with different mapping philosophy. This situation not always results in perfect agreement between the neighboring areas and, thus, does not permit testing geological hypotheses that could be addressed with a self-consistent map. Here the results of global geological mapping of Venus at the scale 1:10M is presented. The map represents a contiguous area extending from 82.5oN to 82.5oS and comprises ~99% of the planet. Mapping procedure: The map was compiled on C2- MIDR sheets, the resolution of which permits identifying the basic characteristics of previously defined units. The higher resolution images were used during the mapping to clarify geologic relationships. When the map was completed, its quality was checked using published USGS maps [e.g., 22-30] and the catalogue of impact craters [31]. The results suggest that the mapping on the C2-base provided a highquality map product. Units and

Alpha wastes treatment

International Nuclear Information System (INIS)

Thouvenot, P.

2000-01-01

Alter 2004, the alpha wastes issued from the Commissariat a l'Energie Atomique installations will be sent to the CEDRA plant. The aims of this installation are decontamination and wastes storage. Because of recent environmental regulations concerning ozone layer depletion, the use of CFC 113 in the decontamination unit, as previously planned, is impossible. Two alternatives processes are studied: the AVD process and an aqueous process including surfactants. Best formulations for both processes are defined issuing degreasing kinetics. It is observed that a good degreasing efficiency is linked to a good decontamination efficiency. Best results are obtained with the aqueous process. Furthermore, from the point of view of an existing waste treatment unit, the aqueous process turns out to be more suitable than the AVD process. (author)

Listed waste determination report

International Nuclear Information System (INIS)

1993-06-01

On September 23, 1988, the US Environmental Protection Agency (EPA) published a notice clarifying interim status requirements for the management of radioactive mixed waste thereby subjecting the Idaho National Engineering Laboratory (INEL) and other applicable Department of Energy (DOE) sites to regulation under the Resource Conservation and Recovery Act (RCRA). Therefore, the DOE was required to submit a Part A Permit application for each treatment, storage, and disposal (TSD) unit within the INEL, defining the waste codes and processes to be regulated under RCRA. The September 1990 revised Part A Permit application, that was approved by the State of Idaho identified 101 potential acute and toxic hazardous waste codes (F-, P-, and U- listed wastes according to 40 CFR 261.31 and 40 CFR 261.33) for some TSD units at the Idaho Chemical Processing Plant. Most of these waste were assumed to have been introduced into the High-level Liquid Waste TSD units via laboratory drains connected to the Process Equipment Waste (PEW) evaporator (PEW system). At that time, a detailed and systematic evaluation of hazardous chemical use and disposal practices had not been conducted to determine if F-, P-, or Unlisted waste had been disposed to the PEW system. The purpose of this investigation was to perform a systematic and detailed evaluation of the use and disposal of the 101 F-, P-, and Unlisted chemicals found in the approved September 1990 Part A Permit application. This investigation was aimed at determining which listed wastes, as defined in 40 CFR 261.31 (F-listed) and 261.33 (P ampersand Unlisted) were discharged to the PEW system. Results of this investigation will be used to support revisions to the RCRA Part A Permit application

Bathymetry mapping using a GPS-sonar equipped remote control boat: Application in waste stabilisation ponds

Science.gov (United States)

Coggins, Liah; Ghadouani, Anas; Ghisalberti, Marco

2014-05-01

Traditionally, bathymetry mapping of ponds, lakes and rivers have used techniques which are low in spatial resolution, sometimes subjective in terms of precision and accuracy, labour intensive, and that require a high level of safety precautions. In waste stabilisation ponds (WSP) in particular, sludge heights, and thus sludge volume, are commonly measured using a sludge judge (a clear plastic pipe with length markings). A remote control boat fitted with a GPS-equipped sonar unit can improve the resolution of depth measurements, and reduce safety and labour requirements. Sonar devices equipped with GPS technology, also known as fish finders, are readily available and widely used by people in boating. Through the use of GPS technology in conjunction with sonar, the location and depth can be recorded electronically onto a memory card. However, despite its high applicability to the field, this technology has so far been underutilised. In the case of WSP, the sonar can measure the water depth to the top of the sludge layer, which can then be used to develop contour maps of sludge distribution and to determine sludge volume. The coupling of sonar technology with a remotely operative vehicle has several advantages of traditional measurement techniques, particularly in removing human subjectivity of readings, and the sonar being able to collect more data points in a shorter period of time, and continuously, with a much higher spatial resolution. The GPS-sonar equipped remote control boat has been tested on in excess of 50 WSP within Western Australia, and has shown a very strong correlation (R2 = 0.98) between spot readings taken with the sonar compared to a sludge judge. This has shown that the remote control boat with GPS-sonar device is capable of providing sludge bathymetry with greatly increased spatial resolution, while greatly reducing profiling time. Remotely operated vehicles, such as the one built in this study, are useful for not only determining sludge

Prolixe-prototype reprocessing unit for irradiating wastes contamined with alpha emitters

International Nuclear Information System (INIS)

Madic, C.; Sontag, R.

1987-01-01

A large number of hot cells are employed for research on nuclear fuel reprocessing and the production of isotope of transuranium elements. These activities generate solid wastes highly contaminated with alpha, beta, gamma emitters. The Prolixe hot cell was built in order to: 1/ reprocess the solid wastes contaminated with alpha, beta, gamma emitters produced in the Radiochemistry building: 2/ produce package wastes storable in shallow-ground disposal sites: 3/ develop a process sufficiently flexible to make it applicable to waste produced in other installations. The process is based on waste leaching after grinding. Depending on the type of wastes the leaching reactant will have a different composition 1/ nitric acid solution for cellulose waste: 2/ nitric solutions containing Ag(II) for other material. The complete process should achieve: 1/ a high waste volume reduction factor: 2/ the production of immobilized waste packages storage in shallow-ground disposal sites: 3/ the recycling of transuranium elements: 4/ the generation of a minimal volume of effluents. This process can be considered as an alternative process to incineration for the reprocessing of solid wastes highly contaminated with alpha, beta, gamma emitters

Map Archive Mining: Visual-Analytical Approaches to Explore Large Historical Map Collections

Directory of Open Access Journals (Sweden)

Johannes H. Uhl

2018-04-01

Full Text Available Historical maps are unique sources of retrospective geographical information. Recently, several map archives containing map series covering large spatial and temporal extents have been systematically scanned and made available to the public. The geographical information contained in such data archives makes it possible to extend geospatial analysis retrospectively beyond the era of digital cartography. However, given the large data volumes of such archives (e.g., more than 200,000 map sheets in the United States Geological Survey topographic map archive and the low graphical quality of older, manually-produced map sheets, the process to extract geographical information from these map archives needs to be automated to the highest degree possible. To understand the potential challenges (e.g., salient map characteristics and data quality variations in automating large-scale information extraction tasks for map archives, it is useful to efficiently assess spatio-temporal coverage, approximate map content, and spatial accuracy of georeferenced map sheets at different map scales. Such preliminary analytical steps are often neglected or ignored in the map processing literature but represent critical phases that lay the foundation for any subsequent computational processes including recognition. Exemplified for the United States Geological Survey topographic map and the Sanborn fire insurance map archives, we demonstrate how such preliminary analyses can be systematically conducted using traditional analytical and cartographic techniques, as well as visual-analytical data mining tools originating from machine learning and data science.

Safety assessment and licensing issues of low level radioactive waste disposal facilities in the United Kingdom

Energy Technology Data Exchange (ETDEWEB)

Fearnley, I. G. [British Nuclear Fuels Ltd., Sellafield (United Kingdom)

1997-12-31

More than 90% of radioactive waste generated in the United Kingdom is classified as low level and is disposed of in near surface repositories. BNFL owns and operates the principal facility for the disposal of this material at Drigg in West Cumbria. In order to fully optimise the use of the site and effectively manage this `national` resource a full understanding and assessment of the risks associated with the performance of the repository to safely contain the disposed waste must be achieved to support the application for the site authorization for disposal. This paper describes the approaches adopted by BNFL to reviewing these risks by the use of systematic Safety and Engineering Assessments supported in turn by experimental programmes and computations models. (author). 6 refs., 1 tab., 4 figs.

Safety assessment and licensing issues of low level radioactive waste disposal facilities in the United Kingdom

International Nuclear Information System (INIS)

Fearnley, I. G.

1997-01-01

More than 90% of radioactive waste generated in the United Kingdom is classified as low level and is disposed of in near surface repositories. BNFL owns and operates the principal facility for the disposal of this material at Drigg in West Cumbria. In order to fully optimise the use of the site and effectively manage this 'national' resource a full understanding and assessment of the risks associated with the performance of the repository to safely contain the disposed waste must be achieved to support the application for the site authorization for disposal. This paper describes the approaches adopted by BNFL to reviewing these risks by the use of systematic Safety and Engineering Assessments supported in turn by experimental programmes and computations models. (author). 6 refs., 1 tab., 4 figs

Geologic map of the Nepenthes Planum Region, Mars

Science.gov (United States)

Skinner, James A.; Tanaka, Kenneth L.

2018-03-26

This map product contains a map sheet at 1:1,506,000 scale that shows the geology of the Nepenthes Planum region of Mars, which is located between the cratered highlands that dominate the southern hemisphere and the less-cratered sedimentary plains that dominate the northern hemisphere.  The map region contains cone- and mound-shaped landforms as well as lobate materials that are morphologically similar to terrestrial igneous or mud vents and flows. This map is part of an informal series of small-scale (large-area) maps aimed at refining current understanding of the geologic units and structures that make up the highland-to-lowland transition zone. The map base consists of a controlled Thermal Emission Imaging System (THEMIS) daytime infrared image mosaic (100 meters per pixel resolution) supplemented by a Mars Orbiter Laser Altimeter (MOLA) digital elevation model (463 meters per pixel resolution). The map includes a Description of Map Units and a Correlation of Map Units that describes and correlates units identified across the entire map region. The geologic map was assembled using ArcGIS software by Environmental Systems Research Institute (http://www.esri.com). The ArcGIS project, geodatabase, base map, and all map components are included online as supplemental data.

Performance of USGS one-year earthquake hazard map for natural and induced seismicity in the central and eastern United States

Science.gov (United States)

Brooks, E. M.; Stein, S.; Spencer, B. D.; Salditch, L.; Petersen, M. D.; McNamara, D. E.

2017-12-01

Seismicity in the central United States has dramatically increased since 2008 due to the injection of wastewater produced by oil and gas extraction. In response, the USGS created a one-year probabilistic hazard model and map for 2016 to describe the increased hazard posed to the central and eastern United States. Using the intensity of shaking reported to the "Did You Feel It?" system during 2016, we assess the performance of this model. Assessing the performance of earthquake hazard maps for natural and induced seismicity is conceptually similar but has practical differences. Maps that have return periods of hundreds or thousands of years— as commonly used for natural seismicity— can be assessed using historical intensity data that also span hundreds or thousands of years. Several different features stand out when assessing the USGS 2016 seismic hazard model for the central and eastern United States from induced and natural earthquakes. First, the model can be assessed as a forecast in one year, because event rates are sufficiently high to permit evaluation with one year of data. Second, because these models are projections from the previous year thus implicitly assuming that fluid injection rates remain the same, misfit may reflect changes in human activity. Our results suggest that the model was very successful by the metric implicit in probabilistic hazard seismic assessment: namely, that the fraction of sites at which the maximum shaking exceeded the mapped value is comparable to that expected. The model also did well by a misfit metric that compares the spatial patterns of predicted and maximum observed shaking. This was true for both the central and eastern United States as a whole, and for the region within it with the highest amount of seismicity, Oklahoma and its surrounding area. The model performed least well in northern Texas, over-stating hazard, presumably because lower oil and gas prices and regulatory action reduced the water injection volume

Quantum Programs as Kleisli Maps

Directory of Open Access Journals (Sweden)

Abraham Westerbaan

2017-01-01

Full Text Available Furber and Jacobs have shown in their study of quantum computation that the category of commutative C*-algebras and PU-maps (positive linear maps which preserve the unit is isomorphic to the Kleisli category of a comonad on the category of commutative C*-algebras with MIU-maps (linear maps which preserve multiplication, involution and unit. [Furber and Jacobs, 2013] In this paper, we prove a non-commutative variant of this result: the category of C*-algebras and PU-maps is isomorphic to the Kleisli category of a comonad on the subcategory of MIU-maps. A variation on this result has been used to construct a model of Selinger and Valiron's quantum lambda calculus using von Neumann algebras. [Cho and Westerbaan, 2016

Geostatistical methodology for waste optimization of contaminated premises - 59344

International Nuclear Information System (INIS)

Desnoyers, Yvon; Dubot, Didier

2012-01-01

The presented methodological study illustrates a Geo-statistical approach suitable for radiological evaluation in nuclear premises. The waste characterization is mainly focused on floor concrete surfaces. By modeling the spatial continuity of activities, Geo-statistics provide sound methods to estimate and map radiological activities, together with their uncertainty. The multivariate approach allows the integration of numerous surface radiation measurements in order to improve the estimation of activity levels from concrete samples. This way, a sequential and iterative investigation strategy proves to be relevant to fulfill the different evaluation objectives. Waste characterization is performed on risk maps rather than on direct interpolation maps (due to bias of the selection on kriging results). The use of several estimation supports (punctual, 1 m 2 , room) allows a relevant radiological waste categorization thanks to cost-benefit analysis according to the risk of exceeding a given activity threshold. Global results, mainly total activity, are similarly quantified to precociously lead the waste management for the dismantling and decommissioning project. This paper recalled the geo-statistics principles and demonstrated how this methodology provides innovative tools for the radiological evaluation of contaminated premises. The relevance of this approach relies on the presence of a spatial continuity for radiological contamination. In this case, geo-statistics provides reliable activity estimates, uncertainty quantification and risk analysis, which are essential decision-making tools for decommissioning and dismantling projects of nuclear installations. Waste characterization is then performed taking all relevant information into account: historical knowledge, surface measurements and samples. Thanks to the multivariate processing, the different investigation stages can be rationalized as regards quantity and positioning. Waste characterization is finally

300 Area waste acid treatment system closure plan

International Nuclear Information System (INIS)

LUKE, S.N.

1999-01-01

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999

300 Area waste acid treatment system closure plan

Energy Technology Data Exchange (ETDEWEB)

LUKE, S.N.

1999-05-17

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999.

Application of time domain induced polarization to the mapping of lithotypes in a landfill site

Directory of Open Access Journals (Sweden)

A. Gazoty

2012-06-01

Full Text Available A direct current (DC resistivity and time domain induced polarization (TDIP survey was undertaken at a decommissioned landfill site situated in Hørløkke, Denmark, for the purpose of mapping the waste deposits and to discriminate important geological units that control the hydrology of the surrounding area. It is known that both waste deposits and clay have clear signatures in TDIP data, making it possible to enhance the resolution of geological structures compared to DC surveys alone.

Four DC/TDIP profiles were carried out crossing the landfill, and another seven profiles in the surroundings provide a sufficiently dense coverage of the entire area. The whole dataset was inverted using a 1-D laterally constrained inversion scheme, recently implemented for TDIP data, in order to use the entire decay curves for reconstructing the electrical parameters of the soil in terms of the Cole-Cole polarization model.

Results show that it is possible to resolve both the geometry of the buried waste body and key geological structures. In particular, it was possible to find a silt/clay lens at depth that correlates with the flow direction of the pollution plume spreading out from the landfill and to map a shallow sandy layer rich in clay that likely has a strong influence on the hydrology of the site. This interpretation of the geophysical findings was constrained by borehole data, in terms of geology and gamma ray logging. The results of this study are important for the impact of the resolved geological units on the hydrology of the area, making it possible to construct more realistic scenarios of the variation of the pollution plume as a function of the climate change.

Geomorphologic characteristic of low-intermediate level radioactive waste disposal land candidate at Lemahabang area

International Nuclear Information System (INIS)

Sucipta

1998-01-01

Geomorphological aspect is a factor should be considered on land evaluation for radioactive wastes disposal purpose. The aspect is important because geomorphological factors contribute on hydrological and erosion condition of the land. The objective of the study is to characterize the geomorphological condition of the land, i.e. land form, geomorphological processes, rock type, soil, surface water, ground water, vegetation and land use. The study was conducted by descriptive analyses from literature study and field geomorphological method, with evaluation as well as developed for terrain analyses. The study area can be divided industry for land from units, I.e. tuff undulating unit (land use: plantation), coastal deposits plain unit, silty sand fluvial plain unit (land use: wet rice field) and unconsolidated sand beach deposits plain unit (opened land without vegetation). Hydrologically, the study area can be divided indus tri three small river stream area (RSA). Detailed description of geomorfological condition is showed by table and geomorphological map. (author)

Islands of biogeodiversity in arid lands on a polygons map study: Detecting scale invariance patterns from natural resources maps.

Science.gov (United States)

Ibáñez, J J; Pérez-Gómez, R; Brevik, Eric C; Cerdà, A

2016-12-15

Many maps (geology, hydrology, soil, vegetation, etc.) are created to inventory natural resources. Each of these resources is mapped using a unique set of criteria, including scales and taxonomies. Past research indicates that comparing results of related maps (e.g., soil and geology maps) may aid in identifying mapping deficiencies. Therefore, this study was undertaken in Almeria Province, Spain to (i) compare the underlying map structures of soil and vegetation maps and (ii) investigate if a vegetation map can provide useful soil information that was not shown on a soil map. Soil and vegetation maps were imported into ArcGIS 10.1 for spatial analysis, and results then exported to Microsoft Excel worksheets for statistical analyses to evaluate fits to linear and power law regression models. Vegetative units were grouped according to the driving forces that determined their presence or absence: (i) climatophilous (ii) lithologic-climate; and (iii) edaphophylous. The rank abundance plots for both the soil and vegetation maps conformed to Willis or Hollow Curves, meaning the underlying structures of both maps were the same. Edaphophylous map units, which represent 58.5% of the vegetation units in the study area, did not show a good correlation with the soil map. Further investigation revealed that 87% of the edaphohygrophilous units were found in ramblas, ephemeral riverbeds that are not typically classified and mapped as soils in modern systems, even though they meet the definition of soil given by the most commonly used and most modern soil taxonomic systems. Furthermore, these edaphophylous map units tend to be islands of biodiversity that are threatened by anthropogenic activity in the region. Therefore, this study revealed areas that need to be revisited and studied pedologically. The vegetation mapped in these areas and the soils that support it are key components of the earth's critical zone that must be studied, understood, and preserved. Copyright © 2016