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1

International Solid Waste Association (ISWA) | Open Energy Information  

Open Energy Info (EERE)

Waste Association (ISWA) Waste Association (ISWA) Jump to: navigation, search Name International Solid Waste Association (ISWA) Address ISWA - International Solid Waste Association General Secretariat Auerspergstrasse 15, Top 41 1080 Vienna Austria Place Vienna Austria Website http://www.iswa.org/ Coordinates 48.2088365°, 16.3546602° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":48.2088365,"lon":16.3546602,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

2

Waste and Climate Change ISWA WHITE PAPER  

E-Print Network (OSTI)

recovery 18 Clean Development Mechanism 20 Policy and regulation 26 Greenhouse gas accounting 34 References fuels such as coal, oil and natural gas. Climate change has already had a measurable impact on many-site electrical generation. Landfill gas may also be upgraded to a substitute natural gas or compressed natural

Columbia University

3

Waste Management & Research290 Waste Manage Res 2002: 20: 290301  

E-Print Network (OSTI)

Waste Management & Research290 Waste Manage Res 2002: 20: 290­301 Printed in UK ­ all rights reserved Copyright © ISWA 2002 Waste Management & Research ISSN 0734­242X Introduction Chromated copper of sorting technologies for CCA treated wood waste Monika Blassino Helena Solo-Gabriele University of Miami

Florida, University of

4

Waste Management & Research172 Waste Manage Res 2003: 21: 172177  

E-Print Network (OSTI)

Waste Management & Research172 Waste Manage Res 2003: 21: 172­177 Printed in UK ­ all rights reserved Copyright © ISWA 2003 Waste Management & Research ISSN 0734­242X In many market segments of PVC in Germany increased by 9%, the fastest growth rate of all plastics. The waste stream in Germany

Columbia University

5

Hazardous Waste: Resource Pack for Trainers and Communicators | Open Energy  

Open Energy Info (EERE)

Hazardous Waste: Resource Pack for Trainers and Communicators Hazardous Waste: Resource Pack for Trainers and Communicators Jump to: navigation, search Tool Summary Name: Hazardous Waste: Resource Pack for Trainers and Communicators Agency/Company /Organization: International Solid Waste Association (ISWA), United Nations Development Programme (UNDP), United Nations Industrial Development Organization (UNIDO) Sector: Energy, Land, Water Focus Area: Renewable Energy, - Waste to Energy Phase: Evaluate Options Topics: Adaptation, Implementation, Low emission development planning, -LEDS Resource Type: Guide/manual, Training materials Website: www.trp-training.info/ Cost: Paid Language: English References: Training Resource Pack[1] "The new TRP+ provides a structured package of notes, technical summaries, visual aids and other training material concerning the (hazardous) waste

6

Integrated Waste Services Association National Solid Wastes Management Association  

E-Print Network (OSTI)

Can Help Meet Our Energy Needs October 5, 2006 - WASHINGTON, DC--A broad coalition of government-244-4700 Evan Von Leer, SWANA 240-494-2252 John Varrasi, ASME 212-591-8158 Don't Waste Waste! Waste-Based Energy and utilization of energy produced from waste, or waste-based energy (WBE). The United States Conference of Mayors

Columbia University

7

10/12/2009 www.wtert.gr 1 Waste-to-Energy Research and Technology Council  

E-Print Network (OSTI)

management Conservation of the precious Greek land for future usage Empowerment of the energy balance10/12/2009 www.wtert.gr 1 Waste-to-Energy Research and Technology Council SYNERGIA Dr. Efstratios MANAGEMENT IN GREECE & POTENTIAL FOR WASTE - TO - ENERGY ISWA Beacon Conference - Strategic Waste Management

Columbia University

8

US Integrated Waste Services Association | Open Energy Information  

Open Energy Info (EERE)

to: navigation, search Name US Integrated Waste Services Association Place Washington, DC Product Focussed on promoting integrated solutions to municipal solid waste management...

9

THE ROLE OF WASTE-TO-ENERGY IN SOLID WASTE MANAGEMENT Introduction  

E-Print Network (OSTI)

Quadrennial Congress, Vienna, Austria, May 1 996. The ISWA 25th Anniversary Congress, Yokohama, Japan

Columbia University

10

Thermal impact of waste emplacement and surface cooling associated with geologic disposal of nuclear waste  

Science Conference Proceedings (OSTI)

The thermal effects associated with the emplacement of aged radioactive wastes in a geologic repository were studied, with emphasis on the following subjects: the waste characteristics, repository structure, and rock properties controlling the thermally induced effects; the current knowledge of the thermal, thermomechanical, and thermohydrologic impacts, determined mainly on the basis of previous studies that assume 10-year-old wastes; the thermal criteria used to determine the repository waste loading densities; and the technical advantages and disadvantages of surface cooling of the wastes prior to disposal as a means of mitigating the thermal impacts. The waste loading densities determined by repository designs for 10-year-old wastes are extended to older wastes using the near-field thermomechanical criteria based on room stability considerations. Also discussed are the effects of long surface cooling periods determined on the basis of far-field thermomechanical and thermohydrologic considerations. The extension of the surface cooling period from 10 years to longer periods can lower the near-field thermal impact but have only modest long-term effects for spent fuel. More significant long-term effects can be achieved by surface cooling of reprocessed high-level waste.

Wang, J.S.Y.; Mangold, D.C.; Spencer, R.K.; Tsang, C.F.

1982-08-01T23:59:59.000Z

11

Element associations in ash from waste combustion in fluidized bed  

SciTech Connect

The incineration of MSW in fluidized beds is a commonly applied waste management practice. The composition of the ashes produced in a fluidized bed boiler has important environmental implications as potentially toxic trace elements may be associated with ash particles and it is therefore essential to determine the mechanisms controlling the association of trace elements to ash particles, including the role of major element composition. The research presented here uses micro-analytical techniques to study the distribution of major and trace elements and determine the importance of affinity-based binding mechanisms in separate cyclone ash particles from MSW combustion. Particle size and the occurrence of Ca and Fe were found to be important factors for the binding of trace elements to ash particles, but the binding largely depends on random associations based on the presence of a particle when trace elements condensate in the flue gas.

Karlfeldt Fedje, K., E-mail: karinka@chalmers.s [Department of Chemical and Biological Engineering, Division of Environmental Inorganic Chemistry, Chalmers University of Technology, Kemivaegen 10, 412 96 Goeteborg (Sweden); Rauch, S. [Department of Civil and Environmental Engineering, Division of Water Environment Technology, Chalmers University of Technology, Sven Hultins Gata 8, 412 96 Goeteborg (Sweden); Cho, P.; Steenari, B.-M. [Department of Chemical and Biological Engineering, Division of Environmental Inorganic Chemistry, Chalmers University of Technology, Kemivaegen 10, 412 96 Goeteborg (Sweden)

2010-07-15T23:59:59.000Z

12

Event:World Solid Waste Congress 2012 | Open Energy Information  

Open Energy Info (EERE)

Solid Waste Congress 2012 Solid Waste Congress 2012 Jump to: navigation, search Calendar.png World Solid Waste Congress 2012: on 2012/09/17 During the three days of this Congress you can meet academics presenting cutting edge research; scientists, government administrators and decision makers, representatives of the world's largest companies in the waste sector, and many other practitioners too from small and medium enterprises. Florence 2012: where else in the world can you network with these people in such a short time The Congress location is at the Palazzo dei Congressi adjacent to the Santa Maria Novella mainline railway station in the City center. ATIA-ISWA ITALIA is also organising a series of events in Italy leading to the main Congress this year. This beautiful city will also host

13

Problems associated with solid wastes from energy systems  

Science Conference Proceedings (OSTI)

Waste streams from many energy-related technologies including coal, oil shale, tar sands, geothermal, oil and gas extraction, and nuclear power generation are reviewed with an emphasis on waste streams from coal and oil shale technologies. This study has two objectives. The first objective is to outline the available information on energy-related solid wastes. Data on chemical composition and hazardous biological characteristics are included, supplemented by regulatory reviews and data on legally designated hazardous waste streams. The second objective is to provide disposal and utilization options. Solid waste disposal and recovery requirements specified under the RCRA are emphasized. Information presented herein should be useful for policy, environmental control, and research and development decision making regarding solid and hazardous wastes from energy production.

Chiu, S.Y.; Fradkin, L.; Barisas, S.; Surles, T.; Morris, S.; Crowther, A.; DeCarlo, V.

1980-09-01T23:59:59.000Z

14

Comments of the Integrated Waste Services Association Florida PSC Renewable Portfolio Standard Workshop  

E-Print Network (OSTI)

The following comments are submitted by the Integrated Waste Services Association (IWSA). IWSA is the national trade association representing the nations waste-to-energy industry and municipalities. Waste-to-energy facilities produce clean, renewable energy through the combustion of municipal solid waste in specially designed power plants equipped with the most modern pollution control equipment to clean emissions. Trash volume is reduced by 90 % and the remaining residue is safely reused or disposed in landfills. There are 87 waste-to-energy plants operating in 25 states managing about 13 percent of Americas trash, or about 95,000 tons each day. Waste-toenergy generates about 2,700 megawatts of electricity to meet the power needs of nearly 2.3 million homes while serving the trash disposal needs of more than 36 million people. In Florida, 11 WTE plants process over 18,000 tons per day of municipal solid waste, and 514 megawatts of electricity. Waste to Energy benefits in relation to Greenhouse Gases: In response to recent discussions regarding greenhouse gases at the workshop, IWSA would like to point out that a number of studies have shown that waste-to-energy is better than carbon neutral. Use of waste-to-energy avoids emissions from fossil fuel-fired electric generation, fugitive methane emissions from decomposing trash in landfills and avoidance of emissions from production of new

unknown authors

2007-01-01T23:59:59.000Z

15

2012 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect

This report summarizes radiological monitoring performed of the Idaho National Laboratory Sites Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

Mike Lewis

2013-02-01T23:59:59.000Z

16

2011 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect

This report summarizes radiological monitoring performed of the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

Mike Lewis

2012-02-01T23:59:59.000Z

17

2010 Radiological Monitoring Results Associated with the Advance Test Reactor Complex Cold Waste Pond  

SciTech Connect

This report summarizes radiological monitoring performed of the Idaho National Laboratory Sites Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

mike lewis

2011-02-01T23:59:59.000Z

18

THERMAL IMPACT OF WASTE EMPLACEMENT AND SURFACE COOLING ASSOCIATED WITH GEOLOGIC DISPOSAL OF NUCLEAR WASTE  

E-Print Network (OSTI)

l e of both uranium and plutonium. The overall objective i sthe remaining uranium or plutonium, or both, can be recycledSF) contains both uranium and plutonium as waste components.

Wang, J.S.Y.

2010-01-01T23:59:59.000Z

19

Groundwater Impacts of Radioactive Wastes and Associated Environmental Modeling Assessment  

Science Conference Proceedings (OSTI)

This article provides a review of the major sources of radioactive wastes and their impacts on groundwater contamination. The review discusses the major biogeochemical processes that control the transport and fate of radionuclide contaminants in groundwater, and describe the evolution of mathematical models designed to simulate and assess the transport and transformation of radionuclides in groundwater.

Ma, Rui; Zheng, Chunmiao; Liu, Chongxuan

2012-11-01T23:59:59.000Z

20

THERMAL IMPACT OF WASTE EMPLACEMENT AND SURFACE COOLING ASSOCIATED WITH GEOLOGIC DISPOSAL OF NUCLEAR WASTE  

E-Print Network (OSTI)

emplacement in t u f f s . Sandia National Laboratories,e a r waste in s h a l e . Sandia N a t i o n a l L a b o rof a WIPP mine d r i f t . Sandia N a t i o n a l L a b o r

Wang, J.S.Y.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Elemental characterization of LL-MA radioactive waste packages with the associated particle technique  

Science Conference Proceedings (OSTI)

The French Alternative Energies and Atomic Energy Commission (CEA) and National Radioactive Waste Management Agency (ANDRA) are conducting an R and D program to improve the characterization of long-lived and medium activity (LL-MA) radioactive waste packages with analytical methods and with non-destructive nuclear measurements. This paper concerns fast neutron interrogation with the associated particle technique (APT), which brings 3D information about the waste material composition. The characterization of volume elements filled with iron, water, aluminium, and PVC in bituminized and fibre concrete LL-MA waste packages has been investigated with MCNP [1] and MODAR data analysis software [2]. APT provides usable information about major elements presents in the volumes of interest. However, neutron scattering on hydrogen nuclei spreads the tagged neutron beam out of the targeted volume towards surrounding materials, reducing spatial selectivity. Simulation shows that small less than 1 L targets can be characterised up to the half-radius of a 225 L bituminized drum, the matrix of which is very rich in hydrogen. Deeper characterization in concrete is possible but limited by counting statistics due to photon attenuation in this dense matrix and, unless large inspection volumes are considered, by the lack of spatial selectivity of the tagged neutron beam due to neutron scattering. (authors)

Perot, B.; Carasco, C.; Toure, M.; El Kanawati, W.; Eleon, C. [CEA, DEN, Cadarache, Nuclear Measurement Laboratory, F-13108 Saint-Paul-lez-Durance (France)

2011-07-01T23:59:59.000Z

22

GRR/Elements/14-CA-c.1 to 14-CA-c.2 - Is the Waste Water Associated...  

Open Energy Info (EERE)

Elements14-CA-c.1 to 14-CA-c.2 - Is the Waste Water Associated Only with Geothermal Operations < GRR | Elements Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY...

23

GRR/Elements/18-CA-a.13 to 18-CA-a.16 - Is the Waste Water Associated...  

Open Energy Info (EERE)

8-CA-a.13 to 18-CA-a.16 - Is the Waste Water Associated Only with Geothermal Operations < GRR | Elements Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP...

24

Gunite and associated tanks remediation project recycling and waste minimization effort  

SciTech Connect

The Department of Energy`s Environmental Management Program at Oak Ridge National Laboratory has initiated clean up of legacy waste resulting from the Manhattan Project. The gunite and associated tanks project has taken an active pollution prevention role by successfully recycling eight tons of scrap metal, reusing contaminated soil in the Area of Contamination, using existing water (supernate) to aid in sludge transfer, and by minimizing and reusing personal protective equipment (PPE) and on-site equipment as much as possible. Total cost savings for Fiscal Year 1997 activities from these efforts are estimated at $4.2 million dollars.

Van Hoesen, S.D.; Saunders, A.D.

1998-05-01T23:59:59.000Z

25

MANAGING UNCERTAINTIES ASSOCIATED WITH RADIOACTIVE WASTE DISPOSAL: TASK GROUP 4 OF THE IAEA PRISM PROJECT  

Science Conference Proceedings (OSTI)

It is widely recognized that the results of safety assessment calculations provide an important contribution to the safety arguments for a disposal facility, but cannot in themselves adequately demonstrate the safety of the disposal system. The safety assessment and a broader range of arguments and activities need to be considered holistically to justify radioactive waste disposal at any particular site. Many programs are therefore moving towards the production of what has become known as a Safety Case, which includes all of the different activities that are conducted to demonstrate the safety of a disposal concept. Recognizing the growing interest in the concept of a Safety Case, the International Atomic Energy Agency (IAEA) is undertaking an intercomparison and harmonization project called PRISM (Practical Illustration and use of the Safety Case Concept in the Management of Near-surface Disposal). The PRISM project is organized into four Task Groups that address key aspects of the Safety Case concept: Task Group 1 - Understanding the Safety Case; Task Group 2 - Disposal facility design; Task Group 3 - Managing waste acceptance; and Task Group 4 - Managing uncertainty. This paper addresses the work of Task Group 4, which is investigating approaches for managing the uncertainties associated with near-surface disposal of radioactive waste and their consideration in the context of the Safety Case. Emphasis is placed on identifying a wide variety of approaches that can and have been used to manage different types of uncertainties, especially non-quantitative approaches that have not received as much attention in previous IAEA projects. This paper includes discussions of the current results of work on the task on managing uncertainty, including: the different circumstances being considered, the sources/types of uncertainties being addressed and some initial proposals for approaches that can be used to manage different types of uncertainties.

Seitz, R.

2011-03-02T23:59:59.000Z

26

Complications Associated with Long-Term Disposition of Newly-Generated Transuranic Waste: A National Laboratory Perspective  

SciTech Connect

The Idaho National Laboratory (INL) is a multipurpose national laboratory delivering specialized science and engineering solutions for the U.S. Department of Energy (DOE). Sponsorship of INL was formally transferred to the DOE Office of Nuclear Energy, Science and Technology (NE) by Secretary Spencer Abraham in July 2002. The move to NE, and designation as the DOE lead nuclear energy laboratory for reactor technology, supports the nations expanding nuclear energy initiatives, placing INL at the center of work to develop advanced Generation IV nuclear energy systems; nuclear energy/hydrogen coproduction technology; advanced nuclear energy fuel cycle technologies; and providing national security answers to national infrastructure needs. As a result of the Laboratorys NE mission, INL generates both contact-handled and remote-handled transuranic (TRU) waste from ongoing operations. Generation rates are relatively small and fluctuate based on specific programs and project activities being conducted; however, the Laboratory will continue to generate TRU waste well into the future in association with the NE mission. Currently, plans and capabilities are being established to transfer INLs contact-handled TRU waste to the Advanced Mixed Waste Treatment Plant (AMWTP) for certification and disposal to the Waste Isolation Pilot Plant (WIPP). Remote-handled TRU waste is currently placed in storage at the Materials and Fuels Complex (MFC). In an effort to minimize future liabilities associated with the INL NE mission, INL is evaluating and assessing options for the management and disposition of all its TRU waste on a real-time basis at time of generation. This paper summarizes near-term activities to minimize future re handling of INLs TRU waste, as well as, potential complications associated with the long-term disposition of newly-generated TRU waste. Potential complications impacting the disposition of INL newly-generated TRU waste include, but are not limited to: 1) required remote-handled TRU packaging configuration(s) vs. current facility capabilities, 2) long-term NE mission activities, 3) WIPP certification requirements, and 4) budget considerations.

B.J. Orchard; L.A. Harvego; T.L. Carlson; R.P. Grant

2009-03-01T23:59:59.000Z

27

Gunite and Associated Tanks Waste Conditioning System: Description and Operational Summary  

SciTech Connect

The purpose of this report is to describe and document the function, operational performance, problems encountered, lessons-learned, and overall assessment of the performance of the waste conditioning system (WCS) in the Gunite{trademark} and Associated Tanks (GAAT) remediation project at the Oak Ridge National Laboratory (ORNL). The GAAT are located in the main plant area of ORNL in the North and South Tank Farms. These tanks were constructed in 1943 as part of the Manhattan Project during World War II. Each tank in the South Tank Farm (STF) has a 50-ft inside diameter and a capacity of {approx}170,000 gal. Each Gunite tank in the North Tank Farm (NTF) has a 25-ft inside diameter with a capacity of {approx}44,000 gal. The GAAT were designed to receive radioactive and chemical wastes from ORNL processes. The tanks were constructed of Gunite, which is created by pneumatically spraying concrete over a wire mesh. Following construction, the site was backfilled so the domes of the tanks were covered with {approx}6 ft of earth. The STF tanks (W-5, -6, -7, -8, -9, and -10) are set in a 2 x 3 array with an east-west axis. The two GAAT in the NTF are on the north side of Central Avenue, and the STF is across the street. One additional Gunite tank, TH-4, is located {approx}300 ft east of the STF. TH-4 is a smaller, 20-ft inside diameter tank with a capacity of {approx}14,000 gal. Approximately 90% of the sludge inventory was removed from the STF tanks during a sluicing campaign in 1982-84 (Autry et al., 1990). Over 95% of the residual from the original sluicing was removed during the GAAT Remediation Project of 1997-2000. The NTF and STF tanks, as well as tank TH-4 were remediated under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) with regulatory oversight by the U.S. Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC).

Emison, JA

2002-03-14T23:59:59.000Z

28

The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 1 [of 2  

SciTech Connect

The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. A phased and integrated approach to waste retrieval operations was used for the GAAT Remediation Project. The project promoted safety by obtaining experience from low-risk operations in the North Tank Farm before moving to higher-risk operations in the South Tank Farm. This approach allowed project personnel to become familiar with the tanks and waste, as well as the equipment, processes, procedures, and operations required to perform successful waste retrieval. By using an integrated approach to tank waste retrieval and tank waste management, the project was completed years ahead of the original baseline schedule, which resulted in avoiding millions of dollars in associated costs. This report is organized in two volumes. Volume 1 provides information on the various phases of the GAAT Remediation Project. It also describes the different types of equipment and how they were used. The emphasis of Volume 1 is on the description of the tank waste retrieval performance and the lessons learned during the GAAT Remediation Project. Volume 2 provides the appendixes for the report, which include the following information: (A) Background Information for the Gunite and Associated Tanks Operable Unit; (B) Annotated Bibliography; (C) Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; (D) GAAT Equipment Matrix; and (E) Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed {approx}5.5 years ahead of schedule and {approx}$120,435,000 below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team.

Lewis, BE

2003-10-07T23:59:59.000Z

29

Basis for Selection of a Residual Waste Retrieval System for Gunite and Associated Tank W-9 at the Oak Ridge National Laboratory  

Science Conference Proceedings (OSTI)

Waste retrieval and transfer operations at the Gunite{trademark} and Associated Tanks (GAATs) Remediation Project have been successfully accomplished using the Tank Waste Retrieval System. This system is composed of the Modified Light-Duty Utility Arm, Houdini Vehicle, Waste Dislodging and Conveyance System, Hose Management Arm, and Sludge Conditioning System. GAAT W-9 has been used as a waste-consolidation and batch-transfer tank during the retrieval of sludges and supernatants from the seven Gunite tanks in the North and South tank farms at Oak Ridge National Laboratory. Tank W-9 was used as a staging tank for the transfers to the Melton Valley Storage Tanks (MVSTs). A total of 18 waste transfers from W-9 occurred between May 25, 1999, and March 30, 2000. Most of these transfers were accomplished using the PulsAir Mixer to mobilize and mix the slurry and a submersible retrieval-transfer pump to transfer the slurry through the Sludge Conditioning System and the {approx}1-mile long, 2-in.-diam waste-transfer line to the MVSTs. The transfers from W-9 have consisted of low-solids-content slurries with solids contents ranging from {approx}2.8 to 6.8 mg/L. Of the initial {approx}88,000 gal of wet sludge estimated in the GAATs, a total of {approx}60,451 gal have been transferred to the MVSTs via tank W-9 as of March 30, 2000. Once the waste-consolidation operations and transfers from W-9 to the MVSTs are completed, the remaining material in W-9 will be mobilized and transferred to the active waste system, Bethel Valley Evaporator Service Tank W-23. Tank W-23 will serve as a batch tank for the final waste transfers from tank W-9 to the MVSTs. This report provides a summary of the requirements and recommendations for the final waste retrieval system for tank W-9, a compilation of the sample analysis data for the sludge in W-9, and brief descriptions of the various waste-retrieval system concepts that were considered for this task. The recommended residual waste retrieval system for cleanout of tank W-9 consists primarily of the existing Tank Waste Retrieval System, which, is used in conjunction with a small surge vessel placed in one of the tank risers and a positive displacement pump installed inside the Primary Conditioning System containment box. Final cleanout of tank W-9 was initiated in July and successfully completed in September 2000. The performance of the selected residual waste retrieval system will be described in a follow-on report.

Lewis, B.E

2000-10-23T23:59:59.000Z

30

The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 2 [of 2  

SciTech Connect

The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. Volume 1 provides information on the various phases of the project and describes the types of equipment used. Volume 1 also discusses the tank waste retrieval performance and the lessons learned during the remediation effort. Volume 2 consists of the following appendixes, which are referenced in Vol. 1: A--Background Information for the Gunite and Associated Tanks Operable Unit; B--Annotated Bibliography; C--GAAT Equipment Matrix; D--Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; and E--Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed {approx}5.5 years ahead of schedule and {approx}$120,435K below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team.

Lewis, BE

2003-10-07T23:59:59.000Z

31

Characterization of Waste Tar Associated with Abandoned Wood Chemical Plant Sites in Northwest Pennsylvania, USA  

SciTech Connect

Over 70 wood chemical plants operated in northern Pennsylvania between ca. 1890 and 1950, all located within 72 km of the New York state border. Their original purpose was to salvage the small unwanted hardwood trees left behind by the lumber mills, and to make charcoal, calcium acetate and methanol for a number of industrial uses via destructive distillation. At many old wood chemical plant sites, unknown quantities of wood tar remain as a residual contaminant and pose a pollution threat to aquatic life in nearby streams. Research on the composition and properties of residual wood tars from five abandoned industrial sites in Pennsylvania are described. Weathered wood tars were more viscous and contained fewer volatile and semivolatile organic compounds than did soil-buried tars. Phenol, 2-methylphenol (o-cresol), 4-methylphenol (p-cresol), and 2, 4-dimethylphenol were found in all sampled tars. These water-soluble phenolic compounds were released quasi-instantaneously in aqueous solution, followed by a slower rate of release, consistent with the behavior of similar compounds in other dense non-aqueous liquids. Air-exposed wood tar deposits developed a hard crust, which contained fewer volatiles and semivolatiles and had a higher softening point than other samples. These tars eroded to form a powdered soil colonized by lichens and mosses. Residual wood tar material found at one site was shown to be thermally altered, likely during the historical destruction of the chemical plant by fire. Recovered wood tar wastes have a relatively high heating value and may have use as a potential, but limited, alternate energy source.

Edendorn, H.M.; Severson, D. (Allegheny Institute of Natural History, Bradford, PA)

2007-07-01T23:59:59.000Z

32

A field strategy to monitor radioactivity associated with investigation derived wastes returned from deep drilling sites  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy, Nevada Operations Office, Underground Test Area Operable Unit (UGTA) is drilling deep (>1500m) monitoring wells that penetrate both unsaturated (vadose) and saturated zones potentially contaminated by sub-surface nuclear weapons testing at the Nevada Test Site, Nye County, Nevada. Drill site radiological monitoring returns data on drilling effluents to make informed management decisions concerning fluid management. Because of rapid turn-around required for on-site monitoring, a representative sample will be analyzed simultaneously for {alpha}, {beta} and {gamma} emitters by instrumentation deployed on-site. For the purposes of field survey, accurate and precise data is returned, in many cases, with minimal sample treatment. A 30% efficient high purity germanium detector and a discriminating liquid scintillation detector are being evaluated for {gamma} and {alpha}/{beta} monitoring respectively. Implementation of these detector systems complements a successful on-site tritium monitoring program. Residual radioactivity associated with underground nuclear tests include tritium, activation products, fission products and actinides. Pulse shape discrimination (PSD) is used in {alpha}/{beta} liquid scintillation counting and is a function of the time distribution of photon emission. In particular, we hope to measure {sup 241}Am produced from {sup 241}Pu by {beta} decay. Because {sup 241}Pu is depleted in fissile bomb fuels, maximum PSD resolution will be required. The high purity germanium detector employs a multichannel analyzer to count gamma emitting radionuclides; we will designate specific window configurations to selectively monitor diagnostic fission product radionuclides (i.e., {sup 137}Cs).

Rego, J.H.; Smith, D.K.; Friensehner, A.V.

1995-05-26T23:59:59.000Z

33

Independent Oversight Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes, September 2013  

NLE Websites -- All DOE Office Websites (Extended Search)

Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes May 2011 February 2013 September 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2

34

Independent Oversight Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes, September 2013  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes May 2011 February 2013 September 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2

35

Radiological Monitoring Results for Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2011-October 31, 2012  

SciTech Connect

This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond WRU-I-0160-01, Modification 1 (formerly LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

Mike lewis

2013-02-01T23:59:59.000Z

36

Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: May 1, 2010-October 31, 2010  

SciTech Connect

This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (#LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

David B. Frederick

2011-02-01T23:59:59.000Z

37

Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2010-October 31, 2011  

SciTech Connect

This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (No.LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

David Frederick

2012-02-01T23:59:59.000Z

38

Waste Logic Liquid Waste Manager (WL-LWM) Software, Version 2.0  

Science Conference Proceedings (OSTI)

In response to continuing industry efforts to reduce operating expenditures, EPRI developed the Waste Logic&trade: Liquid Waste Manager code to analyze costs associated with liquid waste processing and the disposition of its resultant solid waste. EPRI's Waste Logic: Liquid Waste Manager software for windows-based PC computers provides a detailed economic and performance view of liquid waste processing activities. The software will help nuclear utilities evaluate the costs associated with liquid radwaste...

2002-06-05T23:59:59.000Z

39

Options for Handling Noncombustion Waste: Third Edition  

Science Conference Proceedings (OSTI)

Utilities produce a wide variety of noncombustion wastes from generating and distributing electricity as well as from associated support operations. This manual addresses the management of 23 utility noncombustion wastes and describes options for managing these wastes.

1995-07-26T23:59:59.000Z

40

Tank Waste Corporate Board | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tank Waste Corporate Board Tank Waste Corporate Board Tank Waste Corporate Board The Tank Waste Corporate Board is a chartered group of senior DOE, contractor, and laboratory managers and staff that meets approximately semi-annually to formulate and coordinate implementation of an effective and efficient national Tank Waste program. August 1, 2012 Tank Waste Corporate Board Meeting 08/01/12 The following documents are associated with the Tank Waste Corporate Board Meeting held on August 1st, 2012. November 18, 2010 Tank Waste Corporate Board Meeting 11/18/10 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 18th, 2010. July 29, 2009 Tank Waste Corporate Board Meeting 07/29/09 The following documents are associated with the Tank Waste Corporate Board

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan  

SciTech Connect

The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented.

Randklev, E.H.

1993-06-01T23:59:59.000Z

42

CLAB Transuranic Waste Spreadsheets  

Science Conference Proceedings (OSTI)

The Building 772-F Far-Field Transuranic (TRU) Waste Counting System is used to measure the radionuclide content of waste packages produced at the Central Laboratory Facilities (CLAB). Data from the instrument are entered into one of two Excel spreadsheets. The waste stream associated with the waste package determines which spreadsheet is actually used. The spreadsheets calculate the necessary information required for completion of the Transuranic Waste Characterization Form (OSR 29-90) and the Radioactive Solid Waste Burial Ground Record (OSR 7-375 or OSR 7-375A). In addition, the spreadsheets calculate the associated Low Level Waste (LLW) stream information that potentially could be useful if the waste container is ever downgraded from TRU to LLW. The spreadsheets also have the capability to sum activities from source material added to a waste container after assay. A validation data set for each spreadsheet along with the appropriate results are also presented in this report for spreadsheet verification prior to each use.

Leyba, J.D.

2000-08-11T23:59:59.000Z

43

The largest radioactive waste glassification  

NLE Websites -- All DOE Office Websites (Extended Search)

largest radioactive waste glassification largest radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for treating liquid nuclear waste. By immobilizing the radioactivity in glass, the DWPF reduces the risks associated with the continued storage of liquid nuclear waste at SRS and prepares the waste for final disposal in a federal repository. About 38 million gallons of liquid nuclear wastes are now stored in 49 underground carbon-steel tanks at SRS. This waste has about 300 million curies of radioactivity, of which the vast majority

44

ZERO WASTE.  

E-Print Network (OSTI)

??The aim of the thesis was to develop a clear vision on better waste management system. The thesis introduced the sustainable waste management along with (more)

Upadhyaya, Luv

2013-01-01T23:59:59.000Z

45

Waste/By-Product Hydrogen  

NLE Websites -- All DOE Office Websites (Extended Search)

WASTE/BY-PRODUCT HYDROGEN WASTE/BY-PRODUCT HYDROGEN Ruth Cox DOE/DOD Workshop January 13, 2011 January 13, 2011 Fuel Cell and Hydrogen Energy Association The Fuel Cell and Hydrogen Energy Association FCHEA ƒ Trade Association for the industry ƒ Member driven - Market focused ƒ Developers, suppliers, customers, nonprofits, government Ad ƒ Advocacy ƒ Safety and standardization ƒ Education ƒ Strategic Alliances Fuel Cell and Hydrogen Energy Association O M b Our Members 5 W t /B d t H d Waste/By-product Hydrogen Overview Overview ƒ Growing populations, rising standards of living, and increased urbanization leads to a escalating volume of waste leads to a escalating volume of waste. ƒ Huge volumes of waste are collected in dumps, creating a major environmental issue. ƒ ƒ Wastewater treatment plants generate noxious gasses that are released in Wastewater treatment plants generate noxious gasses that are released in

46

DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5...

47

High-Level Waste Corporate Board Performance Assessment Subcommittee  

NLE Websites -- All DOE Office Websites (Extended Search)

Level Waste Corporate Board Performance Assessment Community of Practice John E. Marra, Ph.D. Associate Laboratory Director 21 May 2009 Denver, CO Office of Waste Processing...

48

The reduction of packaging waste  

Science Conference Proceedings (OSTI)

Nationwide, packaging waste comprises approximately one third of the waste being sent to our solid waste landfills. These wastes range from product and shipping containers made from plastic, glass, wood, and corrugated cardboard to packaging fillers and wraps made from a variety of plastic materials such as shrink wrap and polystyrene peanuts. The amount of packaging waste generated is becoming an important issue for manufacturers, retailers, and consumers. Elimination of packaging not only conserves precious landfill space, it also reduces consumption of raw materials and energy, all of which result in important economic and environmental benefits. At the US Department of Energy-Richland Field Office's (DOE-RL) Hanford Site as well as other DOE sites the generation of packaging waste has added importance. By reducing the amount of packaging waste, DOE also reduces the costs and liabilities associated with waste handling, treatment, storage, and disposal.

Raney, E.A.; McCollom, M.; Hogan, J.

1993-04-01T23:59:59.000Z

49

The reduction of packaging waste  

Science Conference Proceedings (OSTI)

Nationwide, packaging waste comprises approximately one third of the waste being sent to our solid waste landfills. These wastes range from product and shipping containers made from plastic, glass, wood, and corrugated cardboard to packaging fillers and wraps made from a variety of plastic materials such as shrink wrap and polystyrene peanuts. The amount of packaging waste generated is becoming an important issue for manufacturers, retailers, and consumers. Elimination of packaging not only conserves precious landfill space, it also reduces consumption of raw materials and energy, all of which result in important economic and environmental benefits. At the US Department of Energy-Richland Field Office`s (DOE-RL) Hanford Site as well as other DOE sites the generation of packaging waste has added importance. By reducing the amount of packaging waste, DOE also reduces the costs and liabilities associated with waste handling, treatment, storage, and disposal.

Raney, E.A.; McCollom, M.; Hogan, J.

1993-04-01T23:59:59.000Z

50

Estimating Waste Inventory and Waste Tank Characterization |...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Estimating Waste Inventory and Waste Tank Characterization Estimating Waste Inventory and Waste Tank Characterization Summary Notes from 28 May 2008 Generic Technical Issue...

51

Los Alamos exceeds waste shipping goal  

NLE Websites -- All DOE Office Websites (Extended Search)

Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

52

Los Alamos exceeds waste shipping goal  

NLE Websites -- All DOE Office Websites (Extended Search)

Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

53

Proceedings of the 17th Biennial Waste Processing Conference WASTE SEPARATION-  

E-Print Network (OSTI)

Proceedings of the 17th Biennial Waste Processing Conference ASME 1996 WASTE SEPARATION- DOES IT INFLUENCE MUNICIPAL WASTE COMBUSTOR EMISSIONS? A. John Chandler A.J. Chandler & Associates Ltd. Willowdale that MSW incinerator emissions show significant variations because of the heterogeneous nature of the waste

Columbia University

54

Solid Waste Management (Indiana) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Solid Waste Management (Indiana) Solid Waste Management (Indiana) Solid Waste Management (Indiana) < Back Eligibility Agricultural Commercial Industrial Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative State/Provincial Govt Utility Program Info State Indiana Program Type Environmental Regulations Provider Association of Indiana Solid Wastes Districts Inc. The state supports the implementation of source reduction, recycling, and other alternative solid waste management practices over incineration and land disposal. The Indiana Department of Environmental Management and the Indiana Solid Waste Management Board are tasked with planning and adopting rules and regulations governing solid waste management practices. Provisions pertaining to landfill management and expansion, permitting,

55

Hazardous Waste  

Science Conference Proceedings (OSTI)

Table 6   General refractory disposal options...D landfill (b) Characterized hazardous waste by TCLP

56

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)  

Science Conference Proceedings (OSTI)

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

D'Amico, E. L [Washington TRU Solutions (United States); Edmiston, D. R. [John Hart and Associates (United States); O'Leary, G. A. [CH2M-WG Idaho, LLC (United States); Rivera, M. A. [Aspen Resources Ltd., Inc. (United States); Steward, D. M. [Boulder Research Enterprises, LLC (United States)

2006-07-01T23:59:59.000Z

57

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste  

E-Print Network (OSTI)

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 9500 Gilman Drive La Jolla, CA 92093 (858) 534) and identity of liquid waste Biohazard symbol Address: UCSD 9500 Gilman Drive La Jolla, CA 92093 (858) 534

Russell, Lynn

58

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste  

E-Print Network (OSTI)

2/2009 Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 200 West Arbor Dr. San Diego, CA 92103 (619 (9:1) OR Biohazard symbol (if untreated) and identity of liquid waste Biohazard symbol Address

Firtel, Richard A.

59

Ferrocyanide waste simulant characterization  

Science Conference Proceedings (OSTI)

Ferrocyanide waste simulants were prepared and characterized to help assess safety concerns associated with the ferrocyanide sludges stored in underground single-shell waste tanks at the Hanford Site. Simulants were prepared to represent the variety of ferrocyanide sludges stored in the storage tanks. Physical properties, chemical compositions, and thermodynamic properties of the simulants were determined. The simulants, as produced, were shown to not sustain propagating reactions when subjected to a strong ignition source. Additional testing and evaluations are recommended to assess safety concerns associated with postulated ferrocyanide sludge dry-out and exposure to external ignition sources.

Jeppson, D.W.; Wong, J.J.

1993-01-01T23:59:59.000Z

60

Hazardous Waste Program (Alabama)  

Energy.gov (U.S. Department of Energy (DOE))

This rule states criteria for identifying the characteristics of hazardous waste and for listing hazardous waste, lists of hazardous wastes, standards for the management of hazardous waste and...

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Tank Waste Corporate Board Meeting 07/24/08  

Energy.gov (U.S. Department of Energy (DOE))

The following documents are associated with the Tank Waste Corporate Board Meeting held on July 24th, 2008.

62

Waste Disposition Update by Christine Gelles  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Disposition Update Waste Disposition Update Christine Gelles Associate Deputy Assistant Secretary for Waste Management (EM-30) EM SSAB Chairs Meeting Washington, DC 2 October 2012 www.em.doe.gov 2 o Waste Stream Highlights o DOE Transportation Update o Greater Than Class C (GTCC) Low Level Waste Environmental Impact Statement o Blue Ribbon Commission on America's Nuclear Future o Nuclear Regulatory Commission's LLW Regulatory Initiatives Discussion Topics www.em.doe.gov 3 Waste Stream Highlights www.em.doe.gov 4 o Within current budget outlook, it is especially critical that EM ensures safe, reliable and cost effective disposition paths exist. o The program's refocused organization and the detailed

63

Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2  

Science Conference Proceedings (OSTI)

This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.

NONE

1998-01-23T23:59:59.000Z

64

Waste= Capital.  

E-Print Network (OSTI)

??The evolution of manufacturing practices over the last century has led to the creation of excess waste during the production process, depleting resources and overwhelming (more)

Stidham, Steve P.

2011-01-01T23:59:59.000Z

65

Remaining Sites Verification Package for the 100-F-26:15 Miscellaneous Pipelines Associated with the 132-F-6, 1608-F Waste Water Pumping Station, Waste Site Reclassification Form 2007-031  

SciTech Connect

The 100-F-26:15 waste site consisted of the remnant portions of underground process effluent and floor drain pipelines that originated at the 105-F Reactor. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

L. M. Dittmer

2008-03-18T23:59:59.000Z

66

MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT  

E-Print Network (OSTI)

#12;MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT PHASE I: AUDIT OF CURRENT PRACTICE The Mushroom Waste Management Project (MWMP) was initiated by Environment Canada, the BC Ministry of solid and liquid wastes generated at mushroom producing facilities. Environmental guidelines

67

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network (OSTI)

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL #12;#12;PNNL-SA-69994 Waste Disposal Workshops: Anthrax- Contaminated Waste AM Lesperance JF Upton SL

68

Proceedings: 1994 EPRI International Low Level Waste Conference  

Science Conference Proceedings (OSTI)

EPRI's third annual International Low Level Waste Conference focused on key economic, regulatory, and technical interests associated with low level waste. Topics discussed included advanced wet waste processing and technology, radwaste cost reduction, storage and disposal issues, mixed waste, advanced ion-exchange technology, decontamination, and source term reduction.

1995-06-14T23:59:59.000Z

69

Waste Hoist  

NLE Websites -- All DOE Office Websites (Extended Search)

45-ton Rope-Guide Friction Hoist Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides. With a 45-ton capacity, it...

70

Advanced Electrochemical Waste Forms  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

71

Management of offshore wastes in the United States.  

SciTech Connect

During the process of finding and producing oil and gas in the offshore environment operators generate a variety of liquid and solid wastes. Some of these wastes are directly related to exploration and production activities (e.g., drilling wastes, produced water, treatment workover, and completion fluids) while other types of wastes are associated with human occupation of the offshore platforms (e.g., sanitary and domestic wastes, trash). Still other types of wastes can be considered generic industrial wastes (e.g., scrap metal and wood, wastes paints and chemicals, sand blasting residues). Finally, the offshore platforms themselves can be considered waste materials when their useful life span has been reached. Generally, offshore wastes are managed in one of three ways--onsite discharge, injection, or transportation to shore. This paper describes the regulatory requirements imposed by the government and the approaches used by offshore operators to manage and dispose of wastes in the US.

Veil, J. A.

1998-10-22T23:59:59.000Z

72

Ferrocyanide tank waste stability. Supplement 2  

Science Conference Proceedings (OSTI)

Ferrocyanide wastes were generated at the Hanford Site during the mid to late 1950s as a result of efforts to create more tank space for the storage of high-level nuclear waste. The ferrocyanide process was developed to remove {sup 137}CS from existing waste and newly generated waste that resulted from the recovery of valuable uranium in Hanford Site waste tanks. During the course of research associated with the ferrocyanide process, it was recognized that ferrocyanide materials, when mixed with sodium nitrate and/or sodium nitrite, were capable of violent exothermic reaction. This chemical reactivity became an issue in the 1980s, when safety issues associated with the storage of ferrocyanide wastes in Hanford Site tanks became prominent. These safety issues heightened in the late 1980s and led to the current scrutiny of the safety issues associated with these wastes, as well as current research and waste management programs. Testing to provide information on the nature of possible tank reactions is ongoing. This document supplements the information presented in Summary of Single-Shell Tank Waste Stability, WHC-EP-0347, March 1991 (Borsheim and Kirch 1991), which evaluated several issues. This supplement only considers information particular to ferrocyanide wastes.

Fowler, K.D.

1993-01-01T23:59:59.000Z

73

Understanding Cement Waste Forms  

Science Conference Proceedings (OSTI)

Oct 29, 2009 ... Ongoing nuclear operations, decontamination and decommissioning, salt waste disposal, and closure of liquid waste tanks result in...

74

Waste Minimization Contents  

Science Conference Proceedings (OSTI)

About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes: Waste Minimization Contents...

75

Los Alamos National Laboratory Accelerates Transuranic Waste Shipments:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Los Alamos National Laboratory Accelerates Transuranic Waste Los Alamos National Laboratory Accelerates Transuranic Waste Shipments: Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan Los Alamos National Laboratory Accelerates Transuranic Waste Shipments: Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan July 2, 2012 - 12:00pm Addthis New Mexico Governor Susana Martinez greets Terry Aguilar, governor of San Ildefonso Pueblo, while Frank Marcinowski (lower right), EM deputy assistant secretary of waste management, and Dan Cox, LANL associate deputy director for environmental affairs, look on.

76

WASTE TO WATTS Waste is a Resource!  

E-Print Network (OSTI)

WASTE TO WATTS Waste is a Resource! energy forum Case Studies from Estonia, Switzerland, Germany BREFs and their BATs Next Generation of Waste Fired Power Plants: Getting the most out of your trash Bossart,· ABB Waste-to-Energy Plants Edmund Fleck,· ESWET Marcel van Berlo,· Afval Energie Bedrijf From

Columbia University

77

Waste Heat Recapture from Supermarket Refrigeration Systems  

DOE Green Energy (OSTI)

The objective of this project was to determine the potential energy savings associated with improved utilization of waste heat from supermarket refrigeration systems. Existing and advanced strategies for waste heat recovery in supermarkets were analyzed, including options from advanced sources such as combined heat and power (CHP), micro-turbines and fuel cells.

Fricke, Brian A [ORNL

2011-11-01T23:59:59.000Z

78

Water and Energy Wasted During Residential Shower Events: Findings from a Pilot Field Study of Hot Water Distribution Systems  

E-Print Network (OSTI)

study to determine waste of water and energy in residential30 percent. The average waste of energy in the hot water ispaper examines the waste of water and energy associated with

Lutz, Jim

2012-01-01T23:59:59.000Z

79

Waste Hoist  

NLE Websites -- All DOE Office Websites (Extended Search)

Primary Hoist: 45-ton Rope-Guide Friction Hoist Largest friction hoist in the world when it was built in 1985 Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides (uses a balanced counterweight and tail ropes). With a 45-ton capacity, it was the largest friction hoist in the world when it was built in 1986. Hoist deck footprint: 2.87m wide x 4.67m long Hoist deck height: 2.87m wide x 7.46m high Access height to the waste hoist deck is limited by a high-bay door at 4.14m high Nominal configuration is 2-cage (over/under), with bottom (equipment) cage interior height of 4.52m The photo, at left, shows the 4.14m high-bay doors at the top collar of the waste hoist shaft. The perpendicular cross section of the opening is 3.5m x 4.14m, but the bottom cage cross section is 2.87m x 4.5m (and 4.67m into the plane of the photo).

80

Greenhouse gas emissions, waste and recycling policy Kaylee Acuff  

E-Print Network (OSTI)

Greenhouse gas emissions, waste and recycling policy Kaylee Acuff and Daniel T. Kaffine We thank@mines.edu.) 1 #12;Greenhouse gas emissions, waste and recycling policy Abstract This paper examines least-cost policies for waste reduction, incorporating upstream greenhouse gas externalities associated

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Fire hazards analysis of transuranic waste storage and assay facility  

Science Conference Proceedings (OSTI)

This document analyzes the fire hazards associated with operations at the Central Waste Complex. It provides the analysis and recommendations necessary to ensure compliance with applicable fire codes.

Busching, K.R., Westinghouse Hanford

1996-07-31T23:59:59.000Z

82

Medical School Biomedical Waste  

E-Print Network (OSTI)

Medical School Biomedical Waste Labware, gloves, pipets, pipet tips Stock cultures, bacterial with or without needles, razor blades, scalpel blades) Key: Pathological waste BL1 & BL2 waste (low risk ­ LR) BL2 waste (moderate risk - MR)/BL3 waste Blood Blood Autoclave Needle box Metal Cart Must either bleach

Cooley, Lynn

83

Waste Sorting Activity Introduction  

E-Print Network (OSTI)

Waste Sorting Activity Introduction: This waste sorting game was originally designed to be one have completed the waste sorting activity quickly, no team was able to complete the waste sorting task who were unfamiliar with Dalhousie's waste management system. Goals: The primary goal of the activity

Beaumont, Christopher

84

University of Waste Procedures  

E-Print Network (OSTI)

University of Maryland Hazardous And Regulated Waste Procedures Manual Revised July 2001 #12;Review II. HAZARDOUS WASTE MANAGEMENT III. BIOLOGICAL, PATHOLOGICAL AND MEDICAL WASTE (BPMW) MANAGEMENT IV. LOW-LEVEL RADIOACTIVE WASTE (LLRW) MANAGEMENT V. EMERGENCY PROCEDURES VI. WASTE MINIMIZATION VII

Rubloff, Gary W.

85

EIS-0287: Notice of Preferred Sodium Bearing Waste Treatment Technology |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Preferred Sodium Bearing Waste Treatment Preferred Sodium Bearing Waste Treatment Technology EIS-0287: Notice of Preferred Sodium Bearing Waste Treatment Technology Idaho High-Level Waste (HLW) and Facilities Disposition In October 2002, the U.S. Department of Energy (DOE or the Department) issued the Final Idaho High-Level Waste (HLW) and Facilities Disposition Environmental Impact Statement (DOE/EIS-0287 (Final EIS)). The Final EIS contains an evaluation of reasonable alternatives for the management of mixed transuranic waste/sodium bearing waste (SBW),1 mixed HLW calcine, and associated low-level waste (LLW), as well as disposition alternatives for HLW facilities when their missions are completed. DOE/EIS-0287, Notice of Preferred Sodium Bearing Waste Treatment Technology, Office of Environmental Management, Idaho, 70 FR 44598 (August

86

Characterization of urban solid waste in Chihuahua, Mexico  

Science Conference Proceedings (OSTI)

The characterization of urban solid waste generation is fundamental for adequate decision making in the management strategy of urban solid waste in a city. The objective of this study is to characterize the waste generated in the households of Chihuahua city, and to compare the results obtained in areas of the city with three different socioeconomic levels. In order to identify the different socioeconomic trends in waste generation and characterization, 560 samples of solid waste were collected during 1 week from 80 households in Chihuahua and were hand sorted and classified into 15 weighted fractions. The average waste generation in Chihuahua calculated in this study was 0.676 kg per capita per day in April 2006. The main fractions were: organic (48%), paper (16%) and plastic (12%). Results show an increased waste generation associated with the socioeconomic level. The characterization in amount and composition of urban waste is the first step needed for the successful implementation of an integral waste management system.

Gomez, Guadalupe [Departament d'Enginyeria Quimica, Universitat Rovira i Virgili, 43007 Tarragona (Spain); Facultad de Ciencias Quimicas, Universidad Autonoma de Chihuahua, 31310 Chihuahua (Mexico); Meneses, Montserrat [Departament d'Enginyeria Quimica, Universitat Rovira i Virgili, 43007 Tarragona (Spain); Ballinas, Lourdes [Facultad de Ciencias Quimicas, Universidad Autonoma de Chihuahua, 31310 Chihuahua (Mexico); Castells, Francesc [Departament d'Enginyeria Quimica, Universitat Rovira i Virgili, 43007 Tarragona (Spain)], E-mail: francesc.castells@urv.cat

2008-12-15T23:59:59.000Z

87

The Mixed Waste Management Facility. Preliminary design review  

Science Conference Proceedings (OSTI)

This document presents information about the Mixed Waste Management Facility. Topics discussed include: cost and schedule baseline for the completion of the project; evaluation of alternative options; transportation of radioactive wastes to the facility; capital risk associated with incineration; radioactive waste processing; scaling of the pilot-scale system; waste streams to be processed; molten salt oxidation; feed preparation; initial operation to demonstrate selected technologies; floorplans; baseline revisions; preliminary design baseline; cost reduction; and project mission and milestones.

NONE

1995-12-31T23:59:59.000Z

88

Radioactive Waste Management (Minnesota)  

Energy.gov (U.S. Department of Energy (DOE))

This section regulates the transportation and disposal of high-level radioactive waste in Minnesota, and establishes a Nuclear Waste Council to monitor the federal high-level radioactive waste...

89

Waste Management Program  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste Management Facility ISO 14001 Registered A wide range of wastes are generated during the normal course of business at BNL. These waste streams are common to many businesses...

90

Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer (FBSR) Na-Al-Si (NAS) Waste Form Qualification  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Low Activity Waste (LAW) Fluidized Bed Steam Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer (FBSR) Na-Al-Si (NAS) Waste Form Qualification C.M. Jantzen and E.M. Pierce November 18, 2010 2 Participating Organizations 3 Incentive and Objectives FBSR sodium-aluminosilicate (NAS) waste form has been identified as a promising supplemental treatment technology for Hanford LAW Objectives: Reduce the risk associated with implementing the FBSR NAS waste form as a supplemental treatment technology for Hanford LAW Conduct test with actual tank wastes Use the best science to fill key data gaps Linking previous and new results together 4 Outline FBSR NAS waste form processing scales FBSR NAS waste form data/key assumptions FBSR NAS key data gaps FBSR NAS testing program 5 FBSR NAS Waste Form Processing

91

Waste Logic Decommissioning Waste Manager 2.0 Users Manual  

Science Conference Proceedings (OSTI)

The Decommissioning Waste Manager, part of EPRI's Waste Logic series of computer programs, analyzes decommissioning waste cost and volume reduction strategies with the intent of quantifying the existing waste management program for any given waste generator.

2001-10-29T23:59:59.000Z

92

Solid Waste (New Mexico)  

Energy.gov (U.S. Department of Energy (DOE))

The New Mexico Environment Department's Solid Waste Bureau manages solid waste in the state. The Bureau implements and enforces the rules established by the Environmental Improvement Board.

93

Industrial Waste Generation  

NLE Websites -- All DOE Office Websites (Extended Search)

9) Page 2 of 7 Industrial Waste Generation Work with Engineered Nanomaterials Power Consumption Historical Contamination (groundwater, soil) Hazardous Waste Generation Atmospheric...

94

Recycling Electronic Waste - Website  

Science Conference Proceedings (OSTI)

Jun 18, 2010 ... Joined: 2/13/2007. Below is a link to a website that has articles on recycling electronic waste. http://www.scientificamerican....ectronic-waste-...

95

International Trade with Waste.  

E-Print Network (OSTI)

?? In this thesis, trade with waste between developed countries and the third world will be presented to analyze whether waste?trading can create a possible (more)

Willn, Jenny

2008-01-01T23:59:59.000Z

96

Recycling Of Cis Photovoltaic Waste  

DOE Patents (OSTI)

A method for extracting and reclaiming metals from scrap CIS photovoltaic cells and associated photovoltaic manufacturing waste by leaching the waste with dilute nitric acid, skimming any plastic material from the top of the leaching solution, separating glass substrate from the leachate, electrolyzing the leachate to plate a copper and selenium metal mixture onto a first cathode, replacing the cathode with a second cathode, re-electrolyzing the leachate to plate cadmium onto the second cathode, separating the copper from selenium, and evaporating the depleted leachate to yield a zinc and indium containing solid.

Drinkard, Jr., William F. (Charlotte, NC); Long, Mark O. (Charlotte, NC); Goozner; Robert E. (Charlotte, NC)

1998-07-14T23:59:59.000Z

97

Waste analysis plan for central waste complex  

SciTech Connect

This waste analysis plan (WAP) has been prepared for the Central Waste Complex which is located in the 200 West Area of the Hanford Facility, Richland, Washington. This WAP documents the methods used to characterize, and obtain and analyze representative samples of waste managed at this unit.

Weston, N.L.

1996-09-20T23:59:59.000Z

98

Tank Waste Corporate Board Meeting 11/06/08 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

11/06/08 11/06/08 Tank Waste Corporate Board Meeting 11/06/08 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 6th, 2008. Note: (Please contact Steven Ross at steven.ross@em.doe.gov for a HLW Glass Waste Loadings version with animations on slide 6). Slurry Retrieval, Pipeline Transport & Plugging and Mixing Workshop The Way Ahead - West Valley Demonstration Project High-Level Liquid Waste Tank Integrity Workshop - 2008 Savannah River Tank Waste Residuals Hanford Tank Waste Residuals HLW Glass Waste Loadings High-Level Waste Corporate Board Performance Assessment Subcommittee More Documents & Publications Tank Waste Corporate Board Meeting 11/18/10 System Planning for Low-Activity Waste at Hanford Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility

99

Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory  

SciTech Connect

This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380{sup 3} corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification.

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01T23:59:59.000Z

100

Radionuclide Retention in Concrete Waste Forms  

Science Conference Proceedings (OSTI)

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how waste form performance is affected by the full range of environmental conditions within the disposal facility; the process of waste form aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of waste form aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the waste forms come in contact with groundwater. The information presented in the report provides data that 1) quantify radionuclide retention within concrete waste form materials similar to those used to encapsulate waste in the Low-Level Waste Burial Grounds (LLBG); 2) measure the effect of concrete waste form properties likely to influence radionuclide migration; and 3) quantify the stability of uranium-bearing solid phases of limited solubility in concrete.

Mattigod, Shas V.; Bovaird, Chase C.; Wellman, Dawn M.; Wood, Marcus I.

2010-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste  

SciTech Connect

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste.

NONE

1994-12-31T23:59:59.000Z

102

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste  

Science Conference Proceedings (OSTI)

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

103

Microbial Transformation of TRU and Mixed Waste: Actinide Speciation and Waste Volume  

Science Conference Proceedings (OSTI)

In order to understand the susceptibility of transuranic and mixed waste to microbial degradation (as well as any mechanism which depends upon either complexation and/or redox of metal ions), it is essential to understand the association of metal ions with organic ligands present in mixed wastes. These ligands have been found in our previous EMSP study to limit electron transfer reactions and strongly affect transport and the eventual fate of radionuclides in the environment. As transuranic waste (and especially mixed waste) will be retained in burial sites and in legacy containment for (potentially) many years while awaiting treatment and removal (or remaining in place under stewardship agreements at government subsurface waste sites), it is also essential to understand the aging of mixed wastes and its implications for remediation and fate of radionuclides. Mixed waste containing actinides and organic materials are especially complex and require extensive study. The EMSP program described in this report is part of a joint program with the Environmental Sciences Department at Brookhaven National Laboratory. The Stony Brook University portion of this award has focused on the association of uranium (U(VI)) and transuranic analogs (Ce(III) and Eu(III)) with cellulosic materials and related compounds, with development of implications for microbial transformation of mixed wastes. The elucidation of the chemical nature of mixed waste is essential for the formulation of remediation and encapsulation technologies, for understanding the fate of contaminant exposed to the environment, and for development of meaningful models for contaminant storage and recovery.

Halada, Gary P

2008-04-10T23:59:59.000Z

104

Infectious waste feed system  

DOE Patents (OSTI)

An infectious waste feed system for comminuting infectious waste and feeding the comminuted waste to a combustor automatically without the need for human intervention. The system includes a receptacle for accepting waste materials. Preferably, the receptacle includes a first and second compartment and a means for sealing the first and second compartments from the atmosphere. A shredder is disposed to comminute waste materials accepted in the receptacle to a predetermined size. A trough is disposed to receive the comminuted waste materials from the shredder. A feeding means is disposed within the trough and is movable in a first and second direction for feeding the comminuted waste materials to a combustor.

Coulthard, E. James (York, PA)

1994-01-01T23:59:59.000Z

105

Understanding radioactive waste  

SciTech Connect

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

Murray, R.L.

1981-12-01T23:59:59.000Z

106

Waste management/waste certification plan for the Oak Ridge National Laboratory Environmental Restoration Program  

Science Conference Proceedings (OSTI)

This Waste Management/Waste Certification (C) Plan, written for the Environmental Restoration (ER) Program at Oak Ridge National Laboratory (ORNL), outlines the criteria and methodologies to be used in the management of waste generated during ORNL ER field activities. Other agreed upon methods may be used in the management of waste with consultation with ER and Waste Management Organization. The intent of this plan is to provide information for the minimization, handling, and disposal of waste generated by ER activities. This plan contains provisions for the safe and effective management of waste consistent with the U.S. Environmental Protection Agency`s (EPA`s) guidance. Components of this plan have been designed to protect the environment and the health and safety of workers and the public. It, therefore, stresses that investigation derived waste (IDW) and other waste be managed to ensure that (1) all efforts be made to minimize the amount of waste generated; (2) costs associated with sampling storage, analysis, transportation, and disposal are minimized; (3) the potential for public and worker exposure is not increased; and (4) additional contaminated areas are not created.

Clark, C. Jr.; Hunt-Davenport, L.D.; Cofer, G.H.

1995-03-01T23:59:59.000Z

107

Nuclear waste solidification  

DOE Patents (OSTI)

High level liquid waste solidification is achieved on a continuous basis by atomizing the liquid waste and introducing the atomized liquid waste into a reaction chamber including a fluidized, heated inert bed to effect calcination of the atomized waste and removal of the calcined waste by overflow removal and by attrition and elutriation from the reaction chamber, and feeding additional inert bed particles to the fluidized bed to maintain the inert bed composition.

Bjorklund, William J. (Richland, WA)

1977-01-01T23:59:59.000Z

108

Robust Solution to Difficult Hydrogen Issues When Shipping Transuranic Waste to the Waste Isolation Pilot Plant  

DOE Green Energy (OSTI)

The Waste Isolation Pilot Plant (WIPP) has been open, receiving, and disposing of transuranic (TRU) waste since March 26, 1999. The majority of the waste has a path forward for shipment to and disposal at the WIPP, but there are about two percent (2%) or approximately 3,020 cubic meters (m{sup 3}) of the volume of TRU waste (high wattage TRU waste) that is not shippable because of gas generation limits set by the U.S. Nuclear Regulatory Commission (NRC). This waste includes plutonium-238 waste, solidified organic waste, and other high plutonium-239 wastes. Flammable gases are potentially generated during transport of TRU waste by the radiolysis of hydrogenous materials and therefore, the concentration at the end of the shipping period must be predicted. Two options are currently available to TRU waste sites for solving this problem: (1) gas generation testing on each drum, and (2) waste form modification by repackaging and/or treatment. Repackaging some of the high wattage waste may require up to 20:1 drum increase to meet the gas generation limits of less than five percent (5%) hydrogen in the inner most layer of confinement (the layer closest to the waste). (This is the limit set by the NRC.) These options increase waste handling and transportation risks and there are high costs and potential worker exposure associated with repackaging this high-wattage TRU waste. The U.S. Department of Energy (DOE)'s Carlsbad Field Office (CBFO) is pursuing a twofold approach to develop a shipping path for these wastes. They are: regulatory change and technology development. For the regulatory change, a more detailed knowledge of the high wattage waste (e.g., void volumes, gas generation potential of specific chemical constituents) may allow refinement of the current assumptions in the gas generation model for Safety Analysis Reports for Packaging for Contact-Handled (CH) TRU waste. For technology development, one of the options being pursued is the use of a robust container, the ARROW-PAK{trademark} System. (1) The ARROW-PAK{trademark} is a macroencapsulation treatment technology, developed by Boh Environmental, LLC, New Orleans, Louisiana. This technology has been designed to withstand any unexpected hydrogen deflagration (i.e. no consequence) and other benefits such as criticality control.

Countiss, S. S.; Basabilvazo, G. T.; Moody, D. C. III; Lott, S. A.; Pickerell, M.; Baca, T.; CH2M Hill; Tujague, S.; Svetlik, H.; Hannah, T.

2003-02-27T23:59:59.000Z

109

Solid Waste Disposal, Hazardous Waste Management Act, Underground...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Eligibility...

110

Business Plan : Residential Solid Waste Collection.  

E-Print Network (OSTI)

??Residential solid waste means all the solid wastes produced in household level, which includes bio-waste, metal, mixed wastes, organic and inorganic waste. The inability of (more)

Mazengo, Dorice

2013-01-01T23:59:59.000Z

111

ECONOMICS OF ON-SITE WASTE GASIFICATION ALFRED C. W. EGGEN  

E-Print Network (OSTI)

procedure for estimating costs for industrial, on-site, waste gasification processes. However, gen eralizingECONOMICS OF ON-SITE WASTE GASIFICATION ALFRED C. W. EGGEN K. T. Lear Associates. Inc. Manchester, Charles R Velzy Associates, Inc., Elmsford, N.Y. On-site waste gasification may well be an at tractive

Columbia University

112

Copyright ASME 20091 Proceedings of the 17th Annual North American Waste-to-Energy Conference  

E-Print Network (OSTI)

procedure for estimating costs for industrial, on-site, waste gasification processes. However, gen eralizingECONOMICS OF ON-SITE WASTE GASIFICATION ALFRED C. W. EGGEN K. T. Lear Associates. Inc. Manchester, Charles R Velzy Associates, Inc., Elmsford, N.Y. On-site waste gasification may well be an at tractive

Columbia University

113

FAQS Qualification Card - Waste Management | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Management Waste Management FAQS Qualification Card - Waste Management A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-WasteManagement.docx Description Waste Management Qualification Card More Documents & Publications FAQS Qualification Card - General Technical Base

114

Characterization of industrial process waste heat and input heat streams  

SciTech Connect

The nature and extent of industrial waste heat associated with the manufacturing sector of the US economy are identified. Industry energy information is reviewed and the energy content in waste heat streams emanating from 108 energy-intensive industrial processes is estimated. Generic types of process equipment are identified and the energy content in gaseous, liquid, and steam waste streams emanating from this equipment is evaluated. Matchups between the energy content of waste heat streams and candidate uses are identified. The resultant matrix identifies 256 source/sink (waste heat/candidate input heat) temperature combinations. (MHR)

Wilfert, G.L.; Huber, H.B.; Dodge, R.E.; Garrett-Price, B.A.; Fassbender, L.L.; Griffin, E.A.; Brown, D.R.; Moore, N.L.

1984-05-01T23:59:59.000Z

115

Enforcement Documents - Waste Isolation Pilot Plant | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Isolation Pilot Plant Waste Isolation Pilot Plant Enforcement Documents - Waste Isolation Pilot Plant September 8, 2006 Enforcement Letter, Washington TRU Solutions - September 8, 2006 Enforcement Letter issued to Washington TRU Solutions, LLC related to Quality Assurance Deficiencies associated with the Super High-Efficiency Neutron Counter Non-Destructive Assay System Refurbishment at the Waste Isolation Pilot Plant October 28, 2004 Enforcement Letter, Diversified Metal Products, Inc - October 28, 2004 Issued to Diversified Metal Products, Inc. related to Transportainer Fabrication Deficiencies for the Waste Isolation Pilot Plant August 30, 2004 Preliminary Notice of Violation, Washington TRU Solutions, LLC - EA-2004-08 Preliminary Notice of Violation issued to Washington TRU Solutions, LLC,

116

Waste Management Quality Assurance Plan  

E-Print Network (OSTI)

Raya James Johnson Rad/Mixed Waste** Steve Bakhtiar Leadhazardous, radioactive, and mixed waste at the Hazardoustraining. Radioactive and mixed waste generators must take

Waste Management Group

2006-01-01T23:59:59.000Z

117

Waste Minimization Plan Prepared by  

E-Print Network (OSTI)

Waste Minimization Plan Prepared by: Environmental Health and Safety Department Revised February 2012 #12;Waste Minimization Plan Table of Contents Policy Statement........................................................... 3 Centralized Waste Management Program

118

Hazardous Waste Act (New Mexico)  

Energy.gov (U.S. Department of Energy (DOE))

"Hazardous waste" means any solid waste or combination of solid wastes that because of their quantity, concentration or physical, chemical or infectious characteristics may: cause or significantly...

119

Tank Waste Corporate Board Meeting 11/18/10 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tank Waste Corporate Board Meeting 11/18/10 Tank Waste Corporate Board Meeting 11/18/10 Tank Waste Corporate Board Meeting 11/18/10 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 18th, 2010. High-Level Waste Corporate Board Meeting Agenda Journey to Excellence Goal 2 and Enhanced Tank Waste Strategy Introduction to Tc/I in Hanford Flowsheet Fate of Tc99 at WTP and Current Work on Capture Technetium Retention During LAW Vitrification Impacts of Feed Composition and Recycle on Hanford Low-Activity Waste Glass Mass Secondary Waste Forms and Technetium Management Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer (FBSR) Na-Al-Si (NAS) Waste Form Qualification Salt Waste Processing Initiatives Recap and Conclusions to Tc/I in Hanford Flowsheet Presentations

120

Encapsulation of hazardous wastes into agglomerates  

SciTech Connect

The objective of this study was to investigate the feasibility of using the cementitious properties and agglomeration characteristics of coal conversion byproducts to encapsulate and immobilize hazardous waste materials. The intention was to establish an economical way of co-utilization and co-disposal of wastes. In addition, it may aid in the eradication of air pollution problems associated with the fine-powdery nature of fly ash. Encapsulation into agglomerates is a novel approach of treating toxic waste. Although encapsulation itself is not a new concept, existing methods employ high-cost resins that render them economically unfeasible. In this investigation, the toxic waste was contained in a concrete-like matrix whereby fly ash and other cementitious waste materials were utilized. The method incorporates the principles of solidification, stabilization and agglomeration. Another aspect of the study is the evaluation of the agglomeration as possible lightweight aggregates. Since fly ash is commercially used as an aggregate, it would be interesting to study the effect of incorporating toxic wastes in the strength development of the granules. In the investigation, the fly ash self-cementation process was applied to electroplating sludges as the toxic waste. The process hoped to provide a basis for delisting of the waste as hazardous and, thereby greatly minimize the cost of its disposal. Owing to the stringent regulatory requirements for hauling and disposal of hazardous waste, the cost of disposal is significant. The current practice for disposal is solidifying the waste with portland cement and dumping the hardened material in the landfill where the cost varies between $700--950/ton. Partially replacing portland cement with fly ash in concrete has proven beneficial, therefore applying the same principles in the treatment of toxic waste looked very promising.

Guloy, A.

1992-01-28T23:59:59.000Z

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

NATURE OF RADIOACTIVE WASTES  

SciTech Connect

The integrated processes of nuclear industry are considered to define the nature of wastes. Processes for recovery and preparation of U and Th fuels produce wastes containing concentrated radioactive materials which present problems of confinement and dispersal. Fundamentals of waste treatment are considered from the standpoint of processes in which radioactive materials become a factor such as naturally occurring feed materials, fission products, and elements produced by parasitic neutron capture. In addition, the origin of concentrated fission product wastes is examined, as well as characteristics of present wastes and the level of fission products in wastes. Also, comments are included on high-level wastes from processes other than solvent extraction, active gaseous wastes, and low- to intermediate-level liquid wastes. (J.R.D.)

Culler, F.L. Jr.

1959-01-26T23:59:59.000Z

122

BLENDING OF LOW-LEVEL RADIOACTIVE WASTE  

E-Print Network (OSTI)

To provide the Commission with the results of the staffs analysis of issues associated with the blending of low-level radioactive waste (LLRW), as directed in Chairman Jaczkos October 8, 2009, memorandum to the staff. The closure of the Barnwell waste disposal facility to most U.S. generators of Class B and C LLRW has caused industry to examine methods for reducing the amount of these wastes, including the blending of some types of Class B and C waste with similar Class A wastes to produce a Class A mixture that can be disposed of at a currently licensed facility. This paper identifies policy, safety, and regulatory issues associated with LLRW blending, provides options for a U. S. Nuclear Regulatory Commission (NRC) blending position, and makes a recommendation for a future blending policy. This paper does not address any new commitments. SUMMARY: In this paper, the staff examines the blending or mixing of LLRW with higher concentrations of radionuclides with LLRW with lower concentrations of radionuclides to form a final homogeneous mixture. While recognizing that some mixing of waste is unavoidable, and may even be necessary and appropriate for efficiency or dose reduction purposes, NRC has historically discouraged mixing LLRW to lower the classification of waste in other circumstances.

R. W. Borchardt; Contacts James; E. Kennedy

2010-01-01T23:59:59.000Z

123

Military Munitions Waste Working Group report  

SciTech Connect

This report presents the findings of the Military Munitions Waste Working Group in its effort to achieve the goals directed under the Federal Advisory Committee to Develop On-Site Innovative Technologies (DOIT Committee) for environmental restoration and waste management. The Military Munitions Waste Working Group identified the following seven areas of concern associated with the ordnance (energetics) waste stream: unexploded ordnance; stockpiled; disposed -- at known locations, i.e., disposal pits; discharged -- impact areas, unknown disposal sites; contaminated media; chemical sureties/weapons; biological weapons; munitions production; depleted uranium; and rocket motor and fuel disposal (open burn/open detonation). Because of time constraints, the Military Munitions Waste Working Group has focused on unexploded ordnance and contaminated media with the understanding that remaining waste streams will be considered as time permits. Contents of this report are as follows: executive summary; introduction; Military Munitions Waste Working Group charter; description of priority waste stream problems; shortcomings of existing approaches, processes and technologies; innovative approaches, processes and technologies, work force planning, training, and education issues relative to technology development and cleanup; criteria used to identify and screen potential demonstration projects; list of potential candidate demonstration projects for the DOIT committee decision/recommendation and appendices.

Not Available

1993-11-30T23:59:59.000Z

124

Waste Isolation Pilot Plant - Enforcement Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Enforcement Documents Enforcement Documents Waste Isolation Pilot Plant Enforcement Letter issued to Washington TRU Solutions, LLC related to Quality Assurance Deficiencies associated with the Super High-Efficiency Neutron Counter Non-Destructive Assay System Refurbishment at the Waste Isolation Pilot Plant, September 8, 2006 Preliminary Notice of Violation issued to Washington TRU Solutions, LLC, related to Radiological Uptakes at the Mobile Visual Examination and Repackaging Facility at Lawrence Livermore National Laboratory, December 22, 2005 (EA-2005-08) - Washington TRU Solutions, LLC - Press Release, December 22, 2005 Enforcement Letter issued to Diversified Metal Products, Inc. related to Transportainer Fabrication Deficiencies for the Waste Isolation Pilot Plant, October 28, 2004

125

CRYSTALLINE CERAMIC WASTE FORMS: REFERENCE FORMULATION REPORT  

Science Conference Proceedings (OSTI)

The research conducted in this work package is aimed at taking advantage of the long term thermodynamic stability of crystalline ceramics to create more durable waste forms (as compared to high level waste glass) in order to reduce the reliance on engineered and natural barrier systems. Durable ceramic waste forms that incorporate a wide range of radionuclides have the potential to broaden the available disposal options and to lower the storage and disposal costs associated with advanced fuel cycles. Assemblages of several titanate phases have been successfully demonstrated to incorporate radioactive waste elements, and the multiphase nature of these materials allows them to accommodate variation in the waste composition. Recent work has shown that they can be successfully produced from a melting and crystallization process. The objective of this report is to explain the design of ceramic host systems culminating in a reference ceramic formulation for use in subsequent studies on process optimization and melt property data assessment in support of FY13 melter demonstration testing. The waste stream used as the basis for the development and testing is a combination of the projected Cs/Sr separated stream, the Trivalent Actinide - Lanthanide Separation by Phosphorous reagent Extraction from Aqueous Komplexes (TALSPEAK) waste stream consisting of lanthanide fission products, the transition metal fission product waste stream resulting from the transuranic extraction (TRUEX) process, and a high molybdenum concentration with relatively low noble metal concentrations. In addition to the combined CS/LN/TM High Mo waste stream, variants without Mo and without Mo and Zr were also evaluated. Based on the results of fabricating and characterizing several simulated ceramic waste forms, two reference ceramic waste form compositions are recommended in this report. The first composition targets the CS/LN/TM combined waste stream with and without Mo. The second composition targets with CS/LN/TM combined waste stream with Mo and Zr removed. Waste streams that contain Mo must be produced in reducing environments to avoid Cs-Mo oxide phase formation. Waste streams without Mo have the ability to be melt processed in air. A path forward for further optimizing the processing steps needed to form the targeted phase assemblages is outlined in this report. Processing modifications including melting in a reducing atmosphere, and controlled heat treatment schedules are anticipated to improve the targeted elemental partitioning.

Brinkman, K.; Fox, K.; Marra, J.

2012-05-15T23:59:59.000Z

126

Development of Cementitious Waste Forms for Nuclear Waste ...  

Science Conference Proceedings (OSTI)

Symposium, Materials Solutions for the Nuclear Renaissance. Presentation Title, Development of Cementitious Waste Forms for Nuclear Waste Immobilization.

127

How to deal with laboratory waste Radioactive waste  

E-Print Network (OSTI)

How to deal with laboratory waste Radioactive waste: Any laboratory waste, whether chemical or biological, containing radioactive material, should be disposed as radioactive waste. Radioactive waste should be removed from the laboratory to the departmental waste area, soon after finishing the experiment

Maoz, Shahar

128

Transuranic (TRU) Waste  

Energy.gov (U.S. Department of Energy (DOE))

Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste with half-lives greater than 20 years, except for (A)...

129

Hanford Waste Vitrification Plant  

SciTech Connect

The Hanford Waste Vitrification Plant (HWVP) is being designed to immobilize pretreated Hanford high-level waste and transuranic waste in borosilicate glass contained in stainless steel canisters. Testing is being conducted in the HWVP Technology Development Project to ensure that adapted technologies are applicable to the candidate Hanford wastes and to generate information for waste form qualification. Empirical modeling is being conducted to define a glass composition range consistent with process and waste form qualification requirements. Laboratory studies are conducted to determine process stream properties, characterize the redox chemistry of the melter feed as a basis for controlling melt foaming and evaluate zeolite sorption materials for process waste treatment. Pilot-scale tests have been performed with simulated melter feed to access filtration for solids removal from process wastes, evaluate vitrification process performance and assess offgas equipment performance. Process equipment construction materials are being selected based on literature review, corrosion testing, and performance in pilot-scale testing. 3 figs., 6 tabs.

Larson, D.E.; Allen, C.R. (Pacific Northwest Lab., Richland, WA (United States)); Kruger, O.L.; Weber, E.T. (Westinghouse Hanford Co., Richland, WA (United States))

1991-10-01T23:59:59.000Z

130

Transuranic Waste Screener  

The TRU waste screener (TRU-WS) is a multifunctional system for the rapid screening of transuranic material for criticality safety or screening for TRU content in open trays or waste containers.

131

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

Department of Energy (DOE) is closing the circle on the generation, management, and disposal of transuranic waste. But the WIPP story is not just about radioactive waste. It is...

132

Immobilization of Nuclear Wastes  

Science Conference Proceedings (OSTI)

Oct 20, 2010 ... Glassy and Glass Composite Nuclear Wasteforms: Michael Ojovan1; Bill Lee2; ... wastes which should be solidified for safe storage and disposal. ... has been vitrifying the Department of Energy's High Level Waste (HLW) at...

133

Pet Waste Management  

E-Print Network (OSTI)

About 1 million pounds of dog waste is deposited daily in North Texas alone. That's why proper disposal of pet waste can make a big difference in the environment. 5 photos, 2 pages

Mechell, Justin; Lesikar, Bruce J.

2008-08-28T23:59:59.000Z

134

The wild wild waste: e-waste  

Science Conference Proceedings (OSTI)

E-Waste is a popular, informal name for discarded electronic products such as computers, VCRs, cameras, which have reached the end of their "useful life". Discarded electronic products contain a stew of toxic metals and chemicals such as lead, mercury, ... Keywords: donate, e-waste, ecology, efficiency, environment, green computing, hazardous material, re-use, recycle, reduce, thin-client, upgrade, virtualization

Scott E. Hanselman; Mahmoud Pegah

2007-10-01T23:59:59.000Z

135

Waste canister for storage of nuclear wastes  

DOE Patents (OSTI)

A waste canister for storage of nuclear wastes in the form of a solidified glass includes fins supported from the center with the tips of the fins spaced away from the wall to conduct heat away from the center without producing unacceptable hot spots in the canister wall.

Duffy, James B. (Fullerton, CA)

1977-01-01T23:59:59.000Z

136

An expert system framework for nondestructive waste assay  

Science Conference Proceedings (OSTI)

Management and disposition of transuranic (RU) waste forms necessitates determining entrained RU and associated radioactive material quantities as per National RU Waste Characterization Program requirements. Technical justification and demonstration of a given NDA method used to determine RU mass and uncertainty in accordance with program quality assurance is difficult for many waste forms. Difficulties are typically founded in waste NDA methods that employ standards compensation and/or employment of simplifying assumptions on waste form configurations. Capability to determine and justify RU mass and mass uncertainty can be enhanced through integration of waste container data/information using expert system and empirical data-driven techniques with conventional data acquisition and analysis. Presented is a preliminary expert system framework that integrates the waste form data base, alogrithmic techniques, statistical analyses, expert domain knowledge bases, and empirical artificial intelligence modules into a cohesive system. The framework design and bases in addition to module development activities are discussed.

Becker, G.K.

1996-10-01T23:59:59.000Z

137

Model development for household waste prevention behaviour  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer We model waste prevention behaviour using structure equation modelling. Black-Right-Pointing-Pointer We merge attitude-behaviour theories with wider models from environmental psychology. Black-Right-Pointing-Pointer Personal norms and perceived behaviour control are the main behaviour predictors. Black-Right-Pointing-Pointer Environmental concern, moral obligation and inconvenience are the main influence on the behaviour. Black-Right-Pointing-Pointer Waste prevention and recycling are different dimensions of waste management behaviour. - Abstract: Understanding waste prevention behaviour (WPB) could enable local governments and decision makers to design more-effective policies for reducing the amount of waste that is generated. By merging well-known attitude-behaviour theories with elements from wider models from environmental psychology, an extensive cognitive framework that provides new and valuable insights is developed for understanding the involvement of individuals in waste prevention. The results confirm the usefulness of the theory of planned behaviour and of Schwartz's altruistic behaviour model as bases for modelling participation in waste prevention. A more elaborate integrated model of prevention was shown to be necessary for the complete analysis of attitudinal aspects associated with waste prevention. A postal survey of 158 respondents provided empirical support for eight of 12 hypotheses. The proposed structural equation indicates that personal norms and perceived behaviour control are the main predictors and that, unlike the case of recycling, subjective norms have a weak influence on WPB. It also suggests that, since social norms have not presented a direct influence, WPB is likely to be influenced by a concern for the environment and the community as well by perceptions of moral obligation and inconvenience. Results also proved that recycling and waste prevention represent different dimensions of waste management behaviour requiring particular approaches to increase individuals' engagement in future policies.

Bortoleto, Ana Paula, E-mail: a.bortoleto@sheffield.ac.uk [Department of Urban Engineering, University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan); Kurisu, Kiyo H.; Hanaki, Keisuke [Department of Urban Engineering, University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan)

2012-12-15T23:59:59.000Z

138

Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste  

SciTech Connect

This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in the Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization.

1995-07-01T23:59:59.000Z

139

Mixed Waste Treatment Study  

Science Conference Proceedings (OSTI)

As part of an ongoing integrated mixed waste program, EPRI has documented nuclear utility industry experience in the on-site treatment of mixed waste. This report reviews all available exclusions/exceptions to EPA permitting requirements for environmentally responsible on-site management of mixed waste. Included is a description of emerging mixed waste treatment technologies along with a detailed evaluation of off-site treatment/disposal facilities.

1996-01-31T23:59:59.000Z

140

Research and Education Campus Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

Science Conference Proceedings (OSTI)

U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory Research and Education Campus facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

L. Harvego; Brion Bennett

2011-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

Science Conference Proceedings (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Not Listed

2011-09-01T23:59:59.000Z

142

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

143

Central Facilities Area Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Central Facilities Area facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facilityspecific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-11-01T23:59:59.000Z

144

Recycle Plastic Waste Recommended Action  

E-Print Network (OSTI)

AR No. 5 Recycle Plastic Waste Recommended Action Separate scrap plastic bag waste from solid waste stream and recycle. This can be accomplished by either arranging for no-cost pick-up of loose waste or by selling baled waste material. Assessment Recommendation Summary Recommended Waste Cost Implementation

Tullos, Desiree

145

Waste Management and WasteWaste Management and Waste--toto--EnergyEnergy Status in SingaporeStatus in Singapore  

E-Print Network (OSTI)

Waste Management and WasteWaste Management and Waste--toto--EnergyEnergy Status in Singapore #12;Singapore's Waste Management · In 2003, 6877 tonnes/day (2.51 M tonnes/year) of MSW collected plants · 8% (non-incinerable waste) and incineration ash goes to the offshore Semakau Landfill · To reach

Columbia University

146

Reducing waste, Photoby stcvcchan  

E-Print Network (OSTI)

I ' I I t Reducing waste, Photoby stcvcchan AMs President Mike Lee (left to right), Point Grey M U recycling given high priority on campus By GAVIN WILSON UBC is taking stepsto reduce waste and encourageGellatly,Vice-President,Administration and Finance,to develop and recommend university policies on waste recycling. Another task force has submitted

Farrell, Anthony P.

147

Hazardous Waste Management Training  

E-Print Network (OSTI)

Hazardous Waste Management Training Persons (including faculty, staff and students) working be thoroughly familiar with waste handling and emergency procedures ap- plicable to their job responsibilities before handling hazardous waste. Departments are re- quired to keep records of training for as long

Dai, Pengcheng

148

Waste disposal package  

DOE Patents (OSTI)

This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

Smith, M.J.

1985-06-19T23:59:59.000Z

149

Waste acceptance criteria for closure generated waste  

Science Conference Proceedings (OSTI)

The PORTS Facility has been operating since 1954. The PORTS Facility is used to enrich uranium for nuclear navy applications and commercial nuclear reactors. The PORTS process uses molecular diffusion techniques to separate the U-235 isotope from the U-238 isotope. The PORTS Facility consists of a complex cascade of compressors and converters through which gaseous uranium hexafluoride feed is processed. The feed contains approximately 0.7 percent U-235 by weight while products contain from 4 to 97 percent U-235 by weight, depending on the final application. In general, the majority of the closure wastes generated at PORTS consists of personal protective equipment (PPE), rags, soils, decontamination solutions, and construction related debris. These hazardous wastes will be predominately characterized on the basis of process knowledge. PORTS assumes its conservative waste characterizations that are based on process knowledge are correct unless and until further investigation and/or analysis proves the constituents are not present or are present at concentrations below characteristic regulatory thresholds. Waste Acceptance Criteria for wastes generated by the closure of active and inactive RCRA facilities at PORTS has been developed. The criteria presented in this document govern the activities that are performed during the closure and subsequent generation of waste and relocation from the closure locations to the storage unit. These criteria are intended to ensure the proper handling, classification, processing, and storage of wastes in order to prevent hazardous waste release that may pose a threat to human health or the environment. Any wastes currently stored at each of the facilities that are to be closed will be transferred to the X-326 or X-7725 Storage Units. The waste transfers will be accomplished in accordance with the Container Transfer Plan.

Not Available

1992-05-01T23:59:59.000Z

150

Safety analysis report for the Waste Storage Facility. Revision 2  

SciTech Connect

This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

Bengston, S.J.

1994-05-01T23:59:59.000Z

151

Waste Disposal Matrix Type of Chemical University-related Waste Personal Waste  

E-Print Network (OSTI)

Waste Disposal Matrix Type of Chemical University-related Waste Personal Waste Batteries, used or unwanted including lithium, alkaline, lead ­ acid or lithium aluminum hydride Chemical Waste Check Disposal of Toxics website for disposal options or Take to Bookstore Biological Waste Biological Waste Residential

Zaferatos, Nicholas C.

152

Accelerator transmutation of waste blanket considerations  

SciTech Connect

Accelerator transmutation of waste (ATW) is one approach for reducing the amount of actinides and long-lived fission products that eventually will be sent to a repository. The ATW accelerator generates high-energy protons, which strike a target and produce spallation neutrons. The spallation neutrons transmute waste in a region that surrounds the spallation target. It is desirable for the waste transmutation region (WTR) to have significant neutron multiplication (a factor of 10 or higher) to keep the required accelerator size reasonable. The WTR is subcritical and is thus not required to generate a self-sustaining fission reaction in the waste. The elimination of this requirement allows the ATW system to be optimized for reducing the hazard from nuclear waste without the concerns associated with safely maintaining criticality. Subcritical operation allows waste compositions with positive prompt reactivity feedback coefficients to be considered, allows waste forms optimized for processing to be considered, and allows additional design flexibility. The WTR will be designed so that criticality cannot be achieved during any credible accident scenario. The primary advantage of the ATW approach is thus the design and operational flexibility gained from subcritical operation. The primary disadvantage of the ATW approach is the expense and complexity of integrating a large proton accelerator with a spallation target and the WTR.

Houts, M.G.; Bjornberg, M.; Poston, D.I.

1997-12-01T23:59:59.000Z

153

Chemical aspects of nuclear waste treatment  

SciTech Connect

The chemical aspects of the treatment of gaseous, liquid, and solid wastes are discussed in overview. The role of chemistry and the chemical reactions in waste treatment are emphasized. Waste treatment methods encompass the chemistry of radioactive elements from every group of the periodic table. In most streams, the radioactive elements are present in relatively low concentrations and are often associated with moderately large amounts of process reagents, or materials. In general, it is desirable that waste treatment methods are based on chemistry that is selective for the concentration of radionuclides and does not require the addition of reagents that contribute significantly to the volume of the treated waste. Solvent extraction, ion exchange, and sorbent chemistry play a major role in waste treatment because of the high selectivity provided for many radionuclides. This paper deals with the chemistry of the onsite treatment methods that is typically used at nuclear installations and is not concerned with the chemistry of the various alternative materials proposed for long-term storage of nuclear wastes. The chemical aspects are discussed from a generic point of view in which the chemistry of important radionuclides is emphasized.

Bond, W.D.

1980-01-01T23:59:59.000Z

154

Radioactive Waste Management Basis  

SciTech Connect

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2009-06-03T23:59:59.000Z

155

Municipal waste processing apparatus  

DOE Patents (OSTI)

This invention relates to apparatus for processing municipal waste, and more particularly to vibrating mesh screen conveyor systems for removing grit, glass, and other noncombustible materials from dry municipal waste. Municipal waste must be properly processed and disposed of so that it does not create health risks to the community. Generally, municipal waste, which may be collected in garbage trucks, dumpsters, or the like, is deposited in processing areas such as landfills. Land and environmental controls imposed on landfill operators by governmental bodies have increased in recent years, however, making landfill disposal of solid waste materials more expensive. 6 figs.

Mayberry, J.L.

1988-04-13T23:59:59.000Z

156

Los Alamos Waste Management Cost Estimation Model; Final report: Documentation of waste management process, development of Cost Estimation Model, and model reference manual  

Science Conference Proceedings (OSTI)

This final report completes the Los Alamos Waste Management Cost Estimation Project, and includes the documentation of the waste management processes at Los Alamos National Laboratory (LANL) for hazardous, mixed, low-level radioactive solid and transuranic waste, development of the cost estimation model and a user reference manual. The ultimate goal of this effort was to develop an estimate of the life cycle costs for the aforementioned waste types. The Cost Estimation Model is a tool that can be used to calculate the costs of waste management at LANL for the aforementioned waste types, under several different scenarios. Each waste category at LANL is managed in a separate fashion, according to Department of Energy requirements and state and federal regulations. The cost of the waste management process for each waste category has not previously been well documented. In particular, the costs associated with the handling, treatment and storage of the waste have not been well understood. It is anticipated that greater knowledge of these costs will encourage waste generators at the Laboratory to apply waste minimization techniques to current operations. Expected benefits of waste minimization are a reduction in waste volume, decrease in liability and lower waste management costs.

Matysiak, L.M.; Burns, M.L.

1994-03-01T23:59:59.000Z

157

ASSEMBLAGES ON WASTE ROCK  

E-Print Network (OSTI)

Abstract: Natural regeneration on waste rock was investigated at the old Wangaloa coal mine, south-east Otago. A 450-m long waste rock stack had been created 4050 years ago, and has had little anthropogenic intervention since. The stack is made up of a gradient of three main waste rock types, defined as silt-rich, mixed, and quartz-rich, which reflect different proportions of loess siltstone and quartz gravel conglomerate. Plant species assemblages were quantified in four 5-m 2 quadrats in each waste rock type. Invertebrates were heat extracted from substrate cores (7 cm diameter; depth 5 cm) collected from quadrats over an eight-week period in spring 2003. Ordination analysis showed statistically distinct plant and invertebrate assemblages had arisen on each waste rock type. Revegetation patterns were dominated by native, woody individuals on all waste rock types, particularly manuka (Leptospermum scoparium) and kanuka (Kunzea ericoides). Plant cover on silt-rich waste rock was four-fold that on quartz-rich waste rock. Total numbers of invertebrates were highest on quartz-rich waste rock, but richness greatest on silt-rich waste rock. Collembola dominated the fauna but their numbers were proportionally greatest in poorly vegetated areas. Further work is required to explain the absence of plants and invertebrates from local areas of waste rock. ___________________________________________________________________________________________________________________________________

C. G. Rufaut; S. Hammit; D. Craw; S. G. Clearwater

2006-01-01T23:59:59.000Z

158

Characteristics of potential repository wastes. Volume 1  

Science Conference Proceedings (OSTI)

This document, and its associated appendices and microcomputer (PC) data bases, constitutes the reference OCRWM data base of physical and radiological characteristics data of radioactive wastes. This Characteristics Data Base (CDB) system includes data on spent nuclear fuel and high-level waste (HLW), which clearly require geologic disposal, and other wastes which may require long-term isolation, such as sealed radioisotope sources. The data base system was developed for OCRWM by the CDB Project at Oak Ridge National Laboratory. Various principal or official sources of these data provided primary information to the CDB Project which then used the ORIGEN2 computer code to calculate radiological properties. The data have been qualified by an OCRWM-sponsored peer review as suitable for quality-affecting work meeting the requirements of OCRWM`s Quality Assurance Program. The wastes characterized in this report include: light-water reactor (LWR) spent fuel and immobilized HLW.

Not Available

1992-07-01T23:59:59.000Z

159

Mixed waste: Proceedings  

SciTech Connect

This volume contains the peer-reviewed and edited versions of papers submitted for presentation a the Second International Mixed Waste Symposium. Following the tradition of the First International Mixed Waste Symposium, these proceedings were prepared in advance of the meeting for distribution to participants. The symposium was organized by the Mixed Waste Committee of the American Society of Mechanical Engineers. The topics discussed at the symposium include: stabilization technologies, alternative treatment technologies, regulatory issues, vitrification technologies, characterization of wastes, thermal technologies, laboratory and analytical issues, waste storage and disposal, organic treatment technologies, waste minimization, packaging and transportation, treatment of mercury contaminated wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base.

Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E. [eds.] [Temple Univ., Philadelphia, PA (United States). Dept. of Environmental Safety and Health

1993-12-31T23:59:59.000Z

160

Enhanced Tank Waste Strategy Update  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reduce the life-cycle costs and accelerate the cleanup of the Cold War environmental legacy www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 cleanup of the Cold War environmental legacy Shirley J. Olinger Associate Principal Deputy for Corporate Operations EMAB Presentation June 23, 2011 EM Priorities: Activities to maintain a safe, secure, and compliant posture in the EM complex Radioactive tank waste stabilization, treatment, and disposal Spent (used) nuclear fuel storage, receipt, and disposition "To-Go Life-Cycle Costs" ($185B - $218B as of the FY 2012 Request) Programmatic support activities* 10% Radioactive tank waste stabilization, treatment and disposal 38% Excess facilities decontamination and decommissioning

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Waste Isolation Pilot Plant Safety Analysis Report  

Science Conference Proceedings (OSTI)

The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

NONE

1995-11-01T23:59:59.000Z

162

Record of Decision for the Solid Waste Program, Hanford Site, Richland, WA: Storage and Treatment of Low-Level Waste and Mixed Low-Level Waste; Disposal of Low-Level Waste and Mixed Low-Level Waste, and Storage, Processing, and Certification of Transuran  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

9 9 Federal Register / Vol. 69, No. 125 / Wednesday, June 30, 2004 / Notices mixed low-level waste, and TRU waste shipments using Year 2000 census data and an updated version of the RADTRAN computer code to calculate potential risks associated with shipping. This analysis included the route- specific impacts of transporting the West Jefferson TRU waste to Hanford and subsequent shipment of this waste to WIPP. Due to the additional TRU waste generated and identified at West Jefferson subsequent to DOE's September 6, 2002, decision, DOE's currently estimated total number of 18 shipments (3 completed RH-TRU waste shipments, 14 remaining RH-TRU waste shipments, and 1 remaining CH-TRU waste shipment) exceeds DOE's prior estimate of total shipments by 3. However, the currently estimated

163

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2010 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2010 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2009-00138, HLW Tank Farm Inspection Plan for 2010, were completed. Ultrasonic measurements (UT) performed in 2010 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 30, 31 and 32 and the findings are documented in SRNL-STI-2010-00533, Tank Inspection NDE Results for Fiscal Year 2010, Waste Tanks 30, 31 and 32. A total of 5824 photographs were made and 1087 visual and video inspections were performed during 2010. Ten new leaksites at Tank 5 were identified in 2010. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.5. Ten leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. None of these new leaksites resulted in a release to the environment. The leaksites were documented during wall cleaning activities and the waste nodules associated with the leaksites were washed away. Previously documented leaksites were reactivated at Tank 12 during waste removal activities.

West, B.; Waltz, R.

2011-06-23T23:59:59.000Z

164

Tank Waste and Waste Processing | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility where the melter is pouring molten glass inside a canister. A Savannah River Remediation employee uses a manipulator located inside a

165

New Waste Calcining Facility (NWCF) Waste Streams  

SciTech Connect

This report addresses the issues of conducting debris treatment in the New Waste Calcine Facility (NWCF) decontamination area and the methods currently being used to decontaminate material at the NWCF.

K. E. Archibald

1999-08-01T23:59:59.000Z

166

Waste Confidence Discussion | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Confidence Discussion Waste Confidence Discussion Long-Term Waste Confidence Update. Waste Confidence Discussion More Documents & Publications Status Update: Extended Storage...

167

TSA waste stream and final waste form composition  

SciTech Connect

A final vitrified waste form composition, based upon the chemical compositions of the input waste streams, is recommended for the transuranic-contaminated waste stored at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The quantities of waste are large with a considerable uncertainty in the distribution of various waste materials. It is therefore impractical to mix the input waste streams into an ``average`` transuranic-contaminated waste. As a result, waste stream input to a melter could vary widely in composition, with the potential of affecting the composition and properties of the final waste form. This work examines the extent of the variation in the input waste streams, as well as the final waste form under conditions of adding different amounts of soil. Five prominent Rocky Flats Plant 740 waste streams are considered, as well as nonspecial metals and the ``average`` transuranic-contaminated waste streams. The metals waste stream is the most extreme variation and results indicate that if an average of approximately 60 wt% of the mixture is soil, the final waste form will be predominantly silica, alumina, alkaline earth oxides, and iron oxide. This composition will have consistent properties in the final waste form, including high leach resistance, irrespective of the variation in waste stream. For other waste streams, much less or no soil could be required to yield a leach resistant waste form but with varying properties.

Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

1993-01-01T23:59:59.000Z

168

Energy from Waste UK Joint Statement on Energy from Waste  

E-Print Network (OSTI)

Energy from Waste UK Joint Statement on Energy from Waste Read more overleaf Introduction Energy from waste provides us with an opportunity for a waste solution and a local source of energy rolled,itcan onlyaddressaportionofthewastestream andisnotsufficientonitsown. Energy obtained from the combustion of residual waste (Energy from

169

WIPP Waste Information System Waste Container Data Report  

E-Print Network (OSTI)

WIPP Waste Information System Waste Container Data Report 06/06/2008 07:50 2.6 % LASB00411 % % Report Date Run by Report Site Id Container Number Waste Stream Data Status Code PEARCYM Version RP0360 Selection Criteria - Total Pages PRD02Instance 5 #12;Waste Isolation Pilot Plant Waste Container Data Report

170

8-Waste treatment and disposal A. Responsibility for waste management  

E-Print Network (OSTI)

8- Waste treatment and disposal A. Responsibility for waste management 1. Each worker is responsible for correctly bagging and labeling his/her own waste. 2. A BSL3 technician will be responsible for transporting and autoclaving the waste. Waste will be autoclaved once or twice per day, depending on use

171

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network (OSTI)

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid scintillation vials must be collected separately. 5. Any "mixed waste" must be cleared with the RSO and labeled

172

WIPP Waste Information System Waste Container Data Report  

E-Print Network (OSTI)

WIPP Waste Information System Waste Container Data Report 06/06/2008 07:49 2.6 % LAS817174 % % Report Date Run by Report Site Id Container Number Waste Stream Data Status Code PEARCYM Version RP0360 Selection Criteria - Total Pages PRD02Instance 5 #12;Waste Isolation Pilot Plant Waste Container Data Report

173

Alpha low-level stored waste systems design study  

SciTech Connect

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex`s Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT&E) requirements for each of the three concepts.

Feizollahi, F.; Teheranian, B. [Morrison Knudson Corp., San Francisco, CA (United States). Environmental Services Div.; Quapp, W.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1992-08-01T23:59:59.000Z

174

Alpha low-level stored waste systems design study  

SciTech Connect

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex's Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT E) requirements for each of the three concepts.

Feizollahi, F.; Teheranian, B. (Morrison Knudson Corp., San Francisco, CA (United States). Environmental Services Div.); Quapp, W.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1992-08-01T23:59:59.000Z

175

Waste Heat Reduction and Recovery for Improving Furnace Efficiency, Productivity and Emissions Performance: A BestPractices Process Heating Technical Brief  

DOE Green Energy (OSTI)

This technical brief is a guide to help plant operators reduce waste heat losses associated with process heating equipment.

Not Available

2004-11-01T23:59:59.000Z

176

Integrated Waste Treatment Facility Fact Sheet | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Management Tank Waste and Waste Processing Integrated Waste Treatment Facility Fact Sheet Integrated Waste Treatment Facility Fact Sheet Waste Management Nuclear...

177

NDAA Section 3116 Waste Determinations with Related Disposal...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste...

178

Life-Cycle Cost Study for a Low-Level Radioactive Waste Disposal Facility in Texas  

SciTech Connect

This report documents the life-cycle cost estimates for a proposed low-level radioactive waste disposal facility near Sierra Blanca, Texas. The work was requested by the Texas Low-Level Radioactive Waste Disposal Authority and performed by the National Low-Level Waste Management Program with the assistance of Rogers and Associates Engineering Corporation.

B. C. Rogers; P. L. Walter (Rogers and Associates Engineering Corporation); R. D. Baird

1999-08-01T23:59:59.000Z

179

Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory  

SciTech Connect

This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification.

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01T23:59:59.000Z

180

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

18 18 19 T he WIPP's first waste receipt, 11 years later than originally planned, was a monumental step forward in the safe management of nuclear waste. Far from ending, however, the WIPP story has really just begun. For the next 35 years, the DOE will face many challenges as it manages a complex shipment schedule from transuranic waste sites across the United States and continues to ensure that the repository complies with all regulatory requirements. The DOE will work to maintain the highest level of safety in waste handling and trans- portation. Coordination with sites Disposal operations require coordination with sites that will ship transuranic waste to the WIPP and include periodic certification of waste characterization and handling practices at those facilities. During the WIPP's

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

SRS - Programs - Waste Solidification  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste Solidification Waste Solidification The two primary facilities operated within the Waste Solidification program are Saltstone and the Defense Waste Processing Facility (DWPF). Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. The largest radioactive waste glassification plant in the world, DWPF converts the high-level liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for immobilizing high-level radioactive liquids into a more stable, manageable form until a federal

182

Underground waste barrier structure  

DOE Patents (OSTI)

Disclosed is an underground waste barrier structure that consists of waste material, a first container formed of activated carbonaceous material enclosing the waste material, a second container formed of zeolite enclosing the first container, and clay covering the second container. The underground waste barrier structure is constructed by forming a recessed area within the earth, lining the recessed area with a layer of clay, lining the clay with a layer of zeolite, lining the zeolite with a layer of activated carbonaceous material, placing the waste material within the lined recessed area, forming a ceiling over the waste material of a layer of activated carbonaceous material, a layer of zeolite, and a layer of clay, the layers in the ceiling cojoining with the respective layers forming the walls of the structure, and finally, covering the ceiling with earth.

Saha, Anuj J. (Hamburg, NY); Grant, David C. (Gibsonia, PA)

1988-01-01T23:59:59.000Z

183

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program  

SciTech Connect

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) is a test program designed to yield data on measurement system capability to characterize drummed transuranic (TRU) waste generated throughout the Department of Energy (DOE) complex. The tests are conducted periodically and provide a mechanism for the independent and objective assessment of NDA system performance and capability relative to the radiological characterization objectives and criteria of the Office of Characterization and Transportation (OCT). The primary documents requiring an NDA PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC), which requires annual characterization facility participation in the PDP, and the Quality Assurance Program Document (QAPD). This NDA PDP implements the general requirements of the QAPD and applicable requirements of the WAC. Measurement facilities must demonstrate acceptable radiological characterization performance through measurement of test samples comprised of pre-specified PDP matrix drum/radioactive source configurations. Measurement facilities are required to analyze the NDA PDP drum samples using the same procedures approved and implemented for routine operational waste characterization activities. The test samples provide an independent means to assess NDA measurement system performance and compliance per criteria delineated in the NDA PDP Plan. General inter-comparison of NDA measurement system performance among DOE measurement facilities and commercial NDA services can also be evaluated using measurement results on similar NDA PDP test samples. A PDP test sample consists of a 55-gallon matrix drum containing a waste matrix type representative of a particular category of the DOE waste inventory and nuclear material standards of known radionuclide and isotopic composition typical of DOE radioactive material. The PDP sample components are made available to participating measurement facilities as designated by the Carlsbad Field Office (CBFO). The nuclear material type, mass and associated alpha activity of the NDA PDP radioactive standard sets have been specified and fabricated to allow assembly of PDP samples that simulate TRU alpha activity concentrations, radionuclidic/isotopic distributions and physical forms typical of the DOE TRU waste inventory. The PDP matrix drum waste matrix types were derived from an evaluation of information contained in the Transuranic Waste Baseline Inventory Report (TWBIR) to ensure representation of prevalent waste types and their associated matrix characteristics in NDA PDP testing. NDA drum analyses required by the Waste Isolation Pilot Plant (WIPP) may only be performed by measurement facilities that comply with the performance criteria as set forth in the NDA PDP Plan. In this document, these analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes.

Carlsbad Field Office

2005-08-03T23:59:59.000Z

184

Guidelines for mixed waste minimization  

SciTech Connect

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.

Owens, C.

1992-02-01T23:59:59.000Z

185

EA-0915: Waste Tank Safety Program Hanford Site, Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE))

This EA evaluates the environmental impacts of the proposal to resolve waste tank safety issues at the Hanford Site near the City of Richland, Washington, and to reduce the risks associated with...

186

Operational Waste Volume Projection  

SciTech Connect

Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000.

STRODE, J.N.

2000-08-28T23:59:59.000Z

187

Solubilities of gases in simulated Tank 241-SY-101 wastes  

DOE Green Energy (OSTI)

Oxygen, nitrogen, hydrogen, methane, and nitrous oxide solubilities were evaluated as a function of temperature in SYl-SIM-93B, a homogeneous simulated waste mixture containing sodium hydroxide, sodium nitrite, sodium nitrate, sodium aluminate, and sodium carbonate, the principal inorganic constituents of the wastes in Tank 241-SY-101. Ammonia solubility data for this simulated waste was obtained as a function of temperature in an earlier study. The choice of a homogeneous waste mixture in this study has the advantage of eliminating complications associated with a changing electrolyte concentration as a function of temperature that would be encountered with a slurry simulant. Dissolution is one of the means by which gases may be retained in Hanford Site wastes. While models are available to estimate gas solubilities in electrolyte solutions, few data are in existence that pertain to highly concentrated, multicomponent electrolytes such as those stored in Hanford Site waste tanks.

Norton, J.D.; Pederson, L.R.

1995-09-01T23:59:59.000Z

188

Norcal Waste Systems, Inc.  

SciTech Connect

Fact sheet describes the LNG long-haul heavy-duty trucks at Norcal Waste Systems Inc.'s Sanitary Fill Company.

Not Available

2002-12-01T23:59:59.000Z

189

Waste Confidence Discussion  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Long-Term Long-Term Waste Confidence Update Christine Pineda Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission National Transportation Stakeholders Forum May 2012 ♦ Knoxville, Tennessee Long-Term Update Draft Report, "Background and Preliminary Assumptions for an Environmental Impact Statement- Long-Term Waste Confidence Update" Elements of the Long-Term Update - Draft environmental impact statement - Draft Waste Confidence Decision - Proposed Waste Confidence Rule based on the EIS and Decision, if applicable 2 Overview of Draft Report Background and assumptions report is first step in process. Basic topics in the report are:

190

Solid Waste Permits (Louisiana)  

Energy.gov (U.S. Department of Energy (DOE))

The Louisiana Department of Environmental Quality administers the rules and regulations governing the storage, collection, processing, recovery, and reuse of solid waste protect the air,...

191

Nuclear Waste Management  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste Management's Yucca Mountain Project and the Office of Nuclear Energy's Advanced Fuel Cycle Initiative (AFCI) and Global Nuclear Energy Partnership (GNEP) programs. Efforts...

192

Vitrification of waste  

DOE Patents (OSTI)

A method is described for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300 C to 800 C to incinerate organic materials, then heated further to a temperature in the range of approximately 1100 C to 1400 C at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

Wicks, G.G.

1999-04-06T23:59:59.000Z

193

The Power of Waste.  

E-Print Network (OSTI)

?? Abstract It is estimated that up to 2 percent of the population in Third World countries survives on waste in one way or another. (more)

Frykman, Carina

2006-01-01T23:59:59.000Z

194

Making waste public.  

E-Print Network (OSTI)

??This thesis questions the boundaries that define waste as a public or private dilemma, investigating these boundaries as productive sites for the imagination of social (more)

Gambetta, Curt

2009-01-01T23:59:59.000Z

195

Vitrification of waste  

DOE Patents (OSTI)

A method for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300.degree. C. to 800.degree. C. to incinerate organic materials, then heated further to a temperature in the range of approximately 1100.degree. C. to 1400.degree. C. at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

Wicks, George G. (Aiken, SC)

1999-01-01T23:59:59.000Z

196

Make love not waste.  

E-Print Network (OSTI)

?? The purpose of this thesis was to investigate a waste management project and its public awareness components, in the Korca region, Albania. We wanted (more)

Carlsson Engstrm, Christina

2008-01-01T23:59:59.000Z

197

Making Waste Public.  

E-Print Network (OSTI)

??This thesis questions the boundaries that define waste as a public or private dilemma, investigating these boundaries as productive sites for the imagination of social (more)

Gambetta, Curt

2009-01-01T23:59:59.000Z

198

WEB RESOURCE: Radioactive Waste  

Science Conference Proceedings (OSTI)

May 8, 2007 ... This resource offers a a very broad explanation of how the Belgian Agency for Management of Radioactive Waste and Enriched Fissile Material...

199

Integrated waste management.  

E-Print Network (OSTI)

??Integrated waste management is considered from a systems approach, with a particular emphasis on advancing sustainability. The focus of the thesis is to examine the (more)

Seadon, Jeffrey Keith

2010-01-01T23:59:59.000Z

200

Waste Clean Up 5  

Science Conference Proceedings (OSTI)

... deployment and clean-up activities of robot arms into a nuclear contaminated pit at the opening of waste storage tank C-106 at Hanford, Washington ...

2011-08-30T23:59:59.000Z

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Tank Waste Corporate Board Meeting 11/18/10 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

18/10 18/10 Tank Waste Corporate Board Meeting 11/18/10 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 18th, 2010. High-Level Waste Corporate Board Meeting Agenda Journey to Excellence Goal 2 and Enhanced Tank Waste Strategy Introduction to Tc/I in Hanford Flowsheet Fate of Tc99 at WTP and Current Work on Capture Technetium Retention During LAW Vitrification Impacts of Feed Composition and Recycle on Hanford Low-Activity Waste Glass Mass Secondary Waste Forms and Technetium Management Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer (FBSR) Na-Al-Si (NAS) Waste Form Qualification Salt Waste Processing Initiatives Recap and Conclusions to Tc/I in Hanford Flowsheet Presentations Tank Closure More Documents & Publications

202

Savannah River Site sample and analysis plan for Clemson Technical Center waste  

Science Conference Proceedings (OSTI)

The purpose of this sampling and analysis plan is to determine the chemical, physical and radiological properties of the SRS radioactive Polychlorinated Biphenyl (PCB) liquid waste stream, to verify that it conforms to Waste Acceptance Criteria of the Department of Energy (DOE) East Tennessee Technology Park (ETTP) Toxic Substance Control Act (TSCA) Incineration Facility. Waste being sent to the ETTP TSCA Incinerator for treatment must be sufficiently characterized to ensure that the waste stream meets the waste acceptance criteria to ensure proper handling, classification, and processing of incoming waste to meet the Waste Storage and Treatment Facility`s Operating Permits. This sampling and analysis plan is limited to WSRC container(s) of homogeneous or multiphasic radioactive PCB contaminated liquids generated in association with a treatability study at Clemson Technical Center (CTC) and currently stored at the WSRC Solid Waste Division Mixed Waste Storage Facility (MWSF).

Hagstrom, T.

1998-04-01T23:59:59.000Z

203

Estimating and understanding DOE waste management costs`  

SciTech Connect

This paper examines costs associated with cleaning up the US Department of Energy`s (DOE`s) nuclear facilities, with particular emphasis on the waste management program. Life-cycle waste management costs have been compiled and reported in the DOE Baseline Environmental Management Report (BEMR). Waste management costs are a critical issue for DOE because of the current budget constraints. The DOE sites are struggling to accomplish their environmental management objectives given funding scenarios that are well below anticipated waste management costs. Through the BEMR process, DOE has compiled complex-wide cleanup cost estimates and has begun analysis of these costs with respect to alternative waste management scenarios and policy strategies. From this analysis, DOE is attempting to identify the major cost drivers and prioritize environmental management activities to achieve maximum utilization of existing funding. This paper provides an overview of the methodology DOE has used to estimate and analyze some waste management costs, including the key data requirements and uncertainties.

Kang, J.S. [USDOE, Washington, DC (United States); Sherick, M.J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-12-01T23:59:59.000Z

204

Secondary Waste Cast Stone Waste Form Qualification Testing Plan  

SciTech Connect

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

Westsik, Joseph H.; Serne, R. Jeffrey

2012-09-26T23:59:59.000Z

205

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6. This Introduction to the WASTE STORAGE FACILITIES TSRs is not part of the TSR limits or conditions and contains no requirements related to WASTE STORAGE FACILITIES operations or to the safety analyses of the DSA.

Larson, H L

2007-09-07T23:59:59.000Z

206

Commercial low-level radioactive waste transportation liability and radiological risk  

SciTech Connect

This report was prepared for States, compact regions, and other interested parties to address two subjects related to transporting low-level radioactive waste to disposal facilities. One is the potential liabilities associated with low-level radioactive waste transportation from the perspective of States as hosts to low-level radioactive waste disposal facilities. The other is the radiological risks of low-level radioactive waste transportation for drivers, the public, and disposal facility workers.

Quinn, G.J.; Brown, O.F. II; Garcia, R.S.

1992-08-01T23:59:59.000Z

207

Design requirements document for project W-465, immobilized low activity waste interim storage  

SciTech Connect

The scope of this design requirements document is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste produced by the privatized Tank Waste Remediation System treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized low-activity waste interim storage facility project and provides traceability from the program level requirements to the project design activity.

Burbank, D.A.

1997-01-27T23:59:59.000Z

208

Waste Isolation Pilot Plant (WIPP) Waste Isolation Pilot Plant...  

National Nuclear Security Administration (NNSA)

dispose of transuranic radioactive waste, or TRU waste, left over from the production of nuclear weapons. After more than 20 years of scientific study, public input, and...

209

Facility accident analysis for low-level waste management alternatives in the US Department of Energy Waste Management Program  

Science Conference Proceedings (OSTI)

The risk to human health of potential radiological releases resulting from facility accidents constitutes an important consideration in the US Department of Energy (DOE) waste management program. The DOE Office of Environmental Management (EM) is currently preparing a Programmatic Environmental Impact Statement (PEIS) that evaluates the risks associated with managing five types of radiological and chemical wastes in the DOE complex. Several alternatives for managing each of the five waste types are defined and compared in the EM PEIS. The alternatives cover a variety of options for storing, treating, and disposing of the wastes. Several treatment methods and operation locations are evaluated as part of the alternatives. The risk induced by potential facility accidents is evaluated for storage operations (current and projected waste storage and post-treatment storage) and for waste treatment facilities. For some of the five waste types considered, facility accidents cover both radiological and chemical releases. This paper summarizes the facility accident analysis that was performed for low-level (radioactive) waste (LLW). As defined in the EM PEIS, LLW includes all radioactive waste not classified as high-level, transuranic, or spent nuclear fuel. LLW that is also contaminated with chemically hazardous components is treated separately as low-level mixed waste (LLMW).

Roglans-Ribas, J.; Mueller, C.; Nabelssi, B.; Folga, S.; Tompkins, M.

1995-06-01T23:59:59.000Z

210

WRPS MEETING THE CHALLENGE OF TANK WASTE  

SciTech Connect

Washington River Protection Solutions (WRPS) is the Hanford tank operations contractor, charged with managing one of the most challenging environmental cleanup projects in the nation. The U.S. Department of Energy hired WRPS to manage 56 million gallons of high-level radioactive waste stored in 177 underground tanks. The waste is the legacy of 45 years of plutonium production for the U. S. nuclear arsenal. WRPS mission is three-fold: safely manage the waste until it can be processed and immobilized; develop the tools and techniques to retrieve the waste from the tanks, and build the infrastructure needed to deliver the waste to the Waste Treatment Plant (WTP) when it begins operating. WTP will 'vitrify' the waste by mixing it with silica and other materials and heating it in an electric melter. Vitrification turns the waste into a sturdy glass that will isolate the radioactivity from the environment. It will take more than 20 years to process all the tank waste. The tank waste is a complex highly radioactive mixture of liquid, sludge and solids. The radioactivity, chemical composition of the waste and the limited access to the underground storage tanks makes retrieval a challenge. Waste is being retrieved from aging single-shell tanks and transferred to newer, safer double-shell tanks. WRPS is using a new technology known as enhanced-reach sluicing to remove waste. A high-pressure stream of liquid is sprayed at 100 gallons per minute through a telescoping arm onto a hard waste layer several inches thick covering the waste. The waste is broken up, moved to a central pump suction and removed from the tank. The innovative Mobile Arm Retrieval System (MARS) is also being used to retrieve waste. MARS is a remotely operated, telescoping arm installed on a mast in the center of the tank. It uses multiple technologies to scrape, scour and rake the waste toward a pump for removal. The American Reinvestment and Recovery Act (ARRA) provided nearly $326 million over two-and-a-half years to modernize the infrastructure in Hanford's tank farms. WRPS issued 850 subcontracts totaling more than $152 million with nearly 76 percent of that total awarded to small businesses. WRPS used the funding to upgrade tank farm infrastructure, develop technologies to retrieve and consolidate tank waste and extend the life of two critical operating facilities needed to feed waste to the WTP. The 222-S Laboratory analyzes waste to support waste retrievals and transfers. The laboratory was upgraded to support future WTP operations with a new computer system, new analytical equipment, a new office building and a new climate-controlled warehouse. The 242-A Evaporator was upgraded with a control-room simulator for operator training and several upgrades to aging equipment. The facility is used to remove liquid from the tank waste, creating additional storage space, necessary for continued waste retrievals and WTP operation. The One System Integrated Project Team is ajoint effort ofWRPS and Bechtel National to identify and resolve common issues associated with commissioning, feeding and operating the Waste Treatment Plant. Two new facilities are being designed to support WTP hot commlsslomng. The Interim Hanford Storage project is planned to store canisters of immobilized high-level radioactive waste glass produced by the vitrification plant. The facility will use open racks to store the 15-foot long, two-foot diameter canisters of waste, which require remote handling. The Secondary Liquid Waste Treatment Project is a major upgrade to the existing Effluent Treatment Facility at Hanford so it can treat about 10 million gallons of liquid radioactive and hazardous effluent a year from the vitrification plant. The One System approach brings the staff of both companies together to identify and resolve WTP safety issues. A questioning attitude is encouraged and an open forum is maintained for employees to raise issues. WRPS is completing its mission safely with record-setting safety performance. Since WRPS took over the Hanford Tank Operations Contract in October 2

BRITTON JC

2012-02-21T23:59:59.000Z

211

Virginia Waste Management Act (Virginia)  

Energy.gov (U.S. Department of Energy (DOE))

Solid waste and hazardous waste are regulated under a number of programs at the Department of Environmental Quality. These programs are designed to encourage the reuse and recycling of solid waste...

212

Solid Waste Act (New Mexico)  

Energy.gov (U.S. Department of Energy (DOE))

The main purpose of the Solid Waste Act is to authorize and direct the establishment of a comprehensive solid waste management program. The act states details about specific waste management...

213

Solid Waste Disposal Act (Texas)  

Energy.gov (U.S. Department of Energy (DOE))

The Texas Commission on Environmental Quality is responsible for the regulation and management of municipal solid waste and hazardous waste. A fee is applied to all solid waste disposed in the...

214

A summary of available information on ferrocyanide tank wastes  

Science Conference Proceedings (OSTI)

Ferrocyanide wastes were generated at the Hanford site during the mid to late 1950s to make more tank space available for the storage of high level nuclear waste. The ferrocyanide process was developed as a method of removing {sup 137}Cs from existing waste solutions and from process solutions that resulted from the recovery of valuable uranium in waste tanks. During the coarse of the research associated with the ferrocyanide process, it was discovered that ferrocyanide materials when mixed with NaNO{sub 3} and/or NaNO{sub 2} exploded. This chemical reactivity became an issue in the 1980s when the safety associated with the storage of ferrocyanide wastes in Hanford tanks became prominent. These safety issues heightened in the late 1980s and led to the current scrutiny of the safety associated with these wastes and the current research and waste management programs. Over the past three years, numerous explosive test have been carried out using milligram quantities of cyanide compounds. These tests provide information on the nature of possible tank reactions. On heating a mixture of ferrocyanide and nitrate or nitrite, an explosive reaction normally begins at about 240{degrees}C, but may occur well below 200{degrees}C in the presence of catalysts or organic compounds that may act as initiators. The energy released is highly dependent on the course of the reaction. Three attempts to model hot spots in local areas of the tanks indicate a very low probability of having a hot spot large enough and hot enough to be of concern. The main purpose of this document is to inform the members of the Tank Waste Science Panel of the background and issues associated with the ferrocyanide wastes. Hopefully, this document fulfills similar needs outside of the framework of the Tank Waste Science Panel. 50 refs., 9 figs., 7 tabs.

Burger, L.L.; Strachan, D.M. (Pacific Northwest Lab., Richland, WA (United States)); Reynolds, D.A. (Westinghouse Hanford Co., Richland, WA (United States)); Schulz, W.W. (Schulz (W.W.), Wilmington, DE (United States))

1991-10-01T23:59:59.000Z

215

SRS - Programs - Solid Waste Management  

NLE Websites -- All DOE Office Websites (Extended Search)

manner possible. SRS's waste is categorized as transuranic, low-level, hazardous, mixed, high-level or sanitary waste. SWM is responsible for managing all of these...

216

Chapter 19 - Nuclear Waste Fund  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Waste Fund 19-1 Nuclear Waste Fund 19-1 CHAPTER 19 NUCLEAR WASTE FUND 1. INTRODUCTION. a. Purpose. This chapter establishes the financial, accounting, and budget policies and procedures for civilian and defense nuclear waste activities, as authorized in Public Law 97-425, the Nuclear Waste Policy Act, as amended, referred to hereafter as the Act. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security Administration, and activities that are funded by the Nuclear Waste Fund (NWF) or the Defense Nuclear Waste Disposal appropriation. c. Background. The Act established the Office of Civilian Radioactive Waste Management (OCRWM) and assigned it responsibility for the management

217

Animal Waste Technology Fund (Maryland)  

Energy.gov (U.S. Department of Energy (DOE))

A bill passed in 2012 transferred responsibility for animal waste management technology projects to the Maryland Department of Agriculture. The Department will maintain the Animal Waste Technology...

218

Drilling Waste Management Technology Descriptions  

NLE Websites -- All DOE Office Websites (Extended Search)

skip navigation Drilling Waste Management Information System: The information resource for better management of drilling wastes DWM Logo Search Search you are in this section...

219

Municipal Waste Combustion (New Mexico)  

Energy.gov (U.S. Department of Energy (DOE))

This rule establishes requirements for emissions from, and design and operation of, municipal waste combustion units. "Municipal waste"means all materials and substances discarded from residential...

220

Hazardous Waste Management (New Mexico)  

Energy.gov (U.S. Department of Energy (DOE))

The New Mexico Environment Department's Hazardous Waste Bureau is responsible for the management of hazardous waste in the state. The Bureau enforces the rules established by the Environmental...

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Solid waste management of Jakarta.  

E-Print Network (OSTI)

?? Solid waste management has been one of the critical issues in Jakarta, Indonesia.With enormous amounts of generated waste per day and limited supportinginfrastructure, the (more)

Trisyanti, Dini

2004-01-01T23:59:59.000Z

222

Treatment of Waste Soils / Solids  

Science Conference Proceedings (OSTI)

About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes: Treatment of Waste Soils / Solids...

223

Mixed Waste Management Guidelines  

Science Conference Proceedings (OSTI)

The management of mixed waste presents serious challenges to nuclear utilities. Regulatory and practical predicaments make compliance with the letter of all applicable regulations extremely difficult. Utility experts developed these guidelines to identify opportunities for improving work practices and regulatory compliance while minimizing any potential adverse impacts of mixed waste management.

1994-12-31T23:59:59.000Z

224

Mixed Waste Characterization Guidelines  

Science Conference Proceedings (OSTI)

This report presents an overview of the process of characterizing potential mixed waste streams from nuclear power plants. Utility experts developed these guidelines to help guide utility personnel through the characterization process and provide a mechanism for properly documenting the characterization of individual waste streams.

1995-12-31T23:59:59.000Z

225

Radioactive waste storage issues  

SciTech Connect

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

226

Nuclear waste solutions  

DOE Patents (OSTI)

High efficiency removal of technetium values from a nuclear waste stream is achieved by addition to the waste stream of a precipitant contributing tetraphenylphosphonium cation, such that a substantial portion of the technetium values are precipitated as an insoluble pertechnetate salt.

Walker, Darrel D. (1684 Partridge Dr., Aiken, SC 29801); Ebra, Martha A. (129 Hasty Rd., Aiken, SC 29801)

1987-01-01T23:59:59.000Z

227

Radioactive waste disposal package  

DOE Patents (OSTI)

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

228

Heterogeneous waste processing  

DOE Patents (OSTI)

A combination of treatment methods are provided for treatment of heterogeneous waste including: (1) treatment for any organic compounds present; (2) removal of metals from the waste; and, (3) bulk volume reduction, with at least two of the three treatment methods employed and all three treatment methods emplyed where suitable.

Vanderberg, Laura A. (Los Alamos, NM); Sauer, Nancy N. (Los Alamos, NM); Brainard, James R. (Los Alamos, NM); Foreman, Trudi M. (Los Alamos, NM); Hanners, John L. (Los Alamos, NM)

2000-01-01T23:59:59.000Z

229

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

T h e W a s t e I s o l a t i o n P i l o t P l a n t DOE 1980. Final Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1981. Waste Isolation Pilot Plant (WIPP): Record of Decision. Federal Register, Vol. 46, No. 18, p. 9162, (46 Federal Register 9162), January 28, 1981. U.S. Department of Energy. DOE 1990. Final Supplement Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026-FS, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1990. Record of Decision: Waste Isolation Pilot Plant. Federal Register, Vol. 55, No. 121, 25689-25692, U.S. Department of Energy. DOE 1994. Comparative Study of Waste Isolation Pilot Plant (WIPP) Transportation Alternatives.

230

Salt Waste Processing Initiatives  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Patricia Suggs Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 Overview * Current SRS Liquid Waste System status * Opportunity to accelerate salt processing - transformational technologies - Rotary Microfiltration (RMF) and Small Column Ion Exchange (SCIX) - Actinide Removal Process/Modular Caustic Side Solvent Extraction (ARP/MCU) extension with next generation extractant - Salt Waste Processing Facility (SWPF) performance enhancement - Saltstone enhancements * Life-cycle impacts and benefits 3 SRS Liquid Waste Total Volume >37 Million Gallons (Mgal) Total Curies 183 MCi (51% ) 175 MCi (49% ) >358 Million Curies (MCi) Sludge 34.3 Mgal (92% ) 3.0 Mgal (8%)

231

HLW Glass Waste Loadings  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HLW HLW Glass Waste Loadings Ian L. Pegg Vitreous State Laboratory The Catholic University of America Washington, DC Overview Overview  Vitrification - general background  Joule heated ceramic melter (JHCM) technology  Factors affecting waste loadings  Waste loading requirements and projections  WTP DWPF  DWPF  Yucca Mountain License Application requirements on waste loading  Summary Vitrification  Immobilization of waste by conversion into a glass  Internationally accepted treatment for HLW  Why glass?  Amorphous material - able to incorporate a wide spectrum of elements over wide ranges of composition; resistant to radiation damage  Long-term durability - natural analogs Relatively simple process - amenable to nuclearization at large  Relatively simple process - amenable to nuclearization at large scale  There

232

AVLIS production plant waste management plan  

Science Conference Proceedings (OSTI)

Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables.

Not Available

1984-11-15T23:59:59.000Z

233

Proposed Use of a Constructed Wetland for the Treatment of Metals in the S-04 Outfall of the Defense Waste Processing Facility at the Savannah River Site  

SciTech Connect

The DWPF is part of an integrated waste treatment system at the SRS to treat wastes containing radioactive contaminants. In the early 1980s the DOE recognized that there would be significant safety and cost advantages associated with immobilizing the radioactive waste in a stable solid form. The Defense Waste Processing Facility was designed and constructed to accomplish this task.

Glover, T.

1999-11-23T23:59:59.000Z

234

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.4.

Laycak, D T

2010-03-05T23:59:59.000Z

235

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6.

Laycak, D T

2008-06-16T23:59:59.000Z

236

L/O/G/OL/O/G/O Waste Waste  

E-Print Network (OSTI)

L/O/G/OL/O/G/O #12;· Waste Waste · Value () · · Flow #12;Genchi GenbutsuGenchi Genbutsu Top management should participate in regular "Ground Zero" walks CQI CQI RCA #12; waste/ value waste/ value · Eliminate · Re-arrange · Re-structure · Simplify · Combine · IT #12

Laksanacharoen, Sathaporn

237

WASTE SEPARATION-DOES IT INFLUENCE MUNICIPAL WASTE COMBUSTOR EMISSIONS?  

E-Print Network (OSTI)

WASTE SEPARATION- DOES IT INFLUENCE MUNICIPAL WASTE COMBUSTOR EMISSIONS? A. John Chandler A a commendable job in proving that trace emissions from a modem waste to energy plant have little to do with the trace compounds in individual components of municipal solid waste. Ogden, the leader in designing

Columbia University

238

FROM WASTE TO WORTH: THE ROLE OF WASTE DIVERSION IN  

E-Print Network (OSTI)

FROM WASTE TO WORTH: THE ROLE OF WASTE DIVERSION IN THE GREEN ECONOMY Submission to the Ministry of the Environment Regarding the Minister's Report on the Waste Diversion Act 2002 Review Submitted by: Submitted to of the Environment 10 Rambert Crescent Integrated Environmental Policy Division Toronto, Ontario M6S 1E6 Waste

Columbia University

239

Accelerator Production of Tritium project process waste assessment  

Science Conference Proceedings (OSTI)

DOE has made a commitment to compliance with all applicable environmental regulatory requirements. In this respect, it is important to consider and design all tritium supply alternatives so that they can comply with these requirements. The management of waste is an integral part of this activity and it is therefore necessary to estimate the quantities and specific wastes that will be generated by all tritium supply alternatives. A thorough assessment of waste streams includes waste characterization, quantification, and the identification of treatment and disposal options. The waste assessment for APT has been covered in two reports. The first report was a process waste assessment (PWA) that identified and quantified waste streams associated with both target designs and fulfilled the requirements of APT Work Breakdown Structure (WBS) Item 5.5.2.1. This second report is an expanded version of the first that includes all of the data of the first report, plus an assessment of treatment and disposal options for each waste stream identified in the initial report. The latter information was initially planned to be issued as a separate Waste Treatment and Disposal Options Assessment Report (WBS Item 5.5.2.2).

Carson, S.D.; Peterson, P.K.

1995-09-01T23:59:59.000Z

240

Quality Services: Solid Wastes, Part 360: Solid Waste Management Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0: Solid Waste Management 0: Solid Waste Management Facilities (New York) Quality Services: Solid Wastes, Part 360: Solid Waste Management Facilities (New York) < Back Eligibility Agricultural Commercial Fuel Distributor Industrial Institutional Investor-Owned Utility Multi-Family Residential Municipal/Public Utility Rural Electric Cooperative Transportation Utility Program Info State New York Program Type Environmental Regulations Provider NY Department of Environmental Conservation These regulations apply to all solid wastes with the exception of hazardous or radioactive waste. Proposed solid waste processing facilities are required to obtain permits prior to construction, and the regulations provide details about permitting, construction, registration, and operation requirements. The regulations contain specific guidance for land

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

TRU Waste Sampling Program: Volume I. Waste characterization  

DOE Green Energy (OSTI)

Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies.

Clements, T.L. Jr.; Kudera, D.E.

1985-09-01T23:59:59.000Z

242

Hanford Tank Waste Residuals  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Hanford Tank Waste Residuals DOE HLW Corporate Board November 6, 2008 Chris Kemp, DOE ORP Bill Hewitt, YAHSGS LLC Hanford Tanks & Tank Waste * Single-Shell Tanks (SSTs) - ~27 million gallons of waste* - 149 SSTs located in 12 SST Farms - Grouped into 7 Waste Management Areas (WMAs) for RCRA closure purposes: 200 West Area S/SX T TX/TY U 200 East Area A/AX B/BX/BY C * Double-Shell Tanks (DSTs) - ~26 million gallons of waste* - 28 DSTs located in 6 DST Farms (1 West/5 East) * 17 Misc Underground Storage Tanks (MUST) * 43 Inactive MUST (IMUST) 200 East Area A/AX B/BX/BY C * Volumes fluctuate as SST retrievals and 242-A Evaporator runs occur. Major Regulatory Drivers * Radioactive Tank Waste Materials - Atomic Energy Act - DOE M 435.1-1, Ch II, HLW - Other DOE Orders * Hazardous/Dangerous Tank Wastes - Hanford Federal Facility Agreement and Consent Order (TPA) - Retrieval/Closure under State's implementation

243

Horizontal Drop of 21- PWR Waste Package  

SciTech Connect

The objective of this calculation is to determine the structural response of the waste package (WP) dropped horizontally from a specified height. The WP used for that purpose is the 21-Pressurized Water Reactor (PWR) WP. The scope of this document is limited to reporting the calculation results in-terms of stress intensities. This calculation is associated with the WP design and was performed by the Waste Package Design group in accordance with the ''Technical Work Plan for: Waste Package Design Description for LA'' (Ref. 16). AP-3.12Q, ''Calculations'' (Ref. 1 1) is used to perform the calculation and develop the document. The sketches attached to this calculation provide the potential dimensions and materials for the 21-PWR WP design.

A.K. Scheider

2007-01-31T23:59:59.000Z

244

Safety Evaluation Report of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis  

Science Conference Proceedings (OSTI)

This Safety Evaluation Report (SER) documents the Department of Energys (DOE's) review of Revision 9 of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis, DOE/WIPP-95-2065 (WIPP CH DSA), and provides the DOE Approval Authority with the basis for approving the document. It concludes that the safety basis documented in the WIPP CH DSA is comprehensive, correct, and commensurate with hazards associated with CH waste disposal operations. The WIPP CH DSA and associated technical safety requirements (TSRs) were developed in accordance with 10 CFR 830, Nuclear Safety Management, and DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports.

Washington TRU Solutions LLC

2005-09-01T23:59:59.000Z

245

Solid waste management challenges for cities in developing countries  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer Stakeholders. Black-Right-Pointing-Pointer Factors affecting performance waste management systems. Black-Right-Pointing-Pointer Questionnaire as Annex for waste management baseline assessment. - Abstract: Solid waste management is a challenge for the cities' authorities in developing countries mainly due to the increasing generation of waste, the burden posed on the municipal budget as a result of the high costs associated to its management, the lack of understanding over a diversity of factors that affect the different stages of waste management and linkages necessary to enable the entire handling system functioning. An analysis of literature on the work done and reported mainly in publications from 2005 to 2011, related to waste management in developing countries, showed that few articles give quantitative information. The analysis was conducted in two of the major scientific journals, Waste Management Journal and Waste Management and Research. The objective of this research was to determine the stakeholders' action/behavior that have a role in the waste management process and to analyze influential factors on the system, in more than thirty urban areas in 22 developing countries in 4 continents. A combination of methods was used in this study in order to assess the stakeholders and the factors influencing the performance of waste management in the cities. Data was collected from scientific literature, existing data bases, observations made during visits to urban areas, structured interviews with relevant professionals, exercises provided to participants in workshops and a questionnaire applied to stakeholders. Descriptive and inferential statistic methods were used to draw conclusions. The outcomes of the research are a comprehensive list of stakeholders that are relevant in the waste management systems and a set of factors that reveal the most important causes for the systems' failure. The information provided is very useful when planning, changing or implementing waste management systems in cities.

Abarca Guerrero, Lilliana, E-mail: l.abarca.guerrero@tue.nl [Built Environment Department, Eindhoven University of Technology, Den Dolech, 25612 AZ Eindhoven (Netherlands); Maas, Ger, E-mail: g.j.maas@tue.nl [Built Environment Department, Eindhoven University of Technology, Den Dolech, 25612 AZ Eindhoven (Netherlands); Hogland, William, E-mail: william.hogland@lnu.se [School of Natural Sciences, Linnaeus University, SE-391 82 Kalmar (Sweden)

2013-01-15T23:59:59.000Z

246

Remedial site evaluation report for the waste area grouping 10 wells associated with the new hydrofracture facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 2: Field activities and well summaries  

Science Conference Proceedings (OSTI)

Four hydrofracture sites at the Oak Ridge National Laboratory (ORNL) were used for development, demonstration, and disposal from 1959 to 1984. More than 10 million gal of waste grout mix was disposed of via hydrofracture. Various types of wells were installed to monitor the hydrofracture operations. The primary goal of this remedial investigation was to gather information about the wells in order to recommend the type and best method of final disposition for the wells. Evaluations were performed to determine the integrity of well castings, confirm construction details for each well, evaluate the extent of contamination, assist in planning for future activities, and determine the suitability of the wells for future temporary site monitoring.

NONE

1996-08-01T23:59:59.000Z

247

L/O/G/OL/O/G/O Waste Waste  

E-Print Network (OSTI)

L/O/G/OL/O/G/O #12;· Waste Waste · Value () · · Flow #12;Genchi GenbutsuGenchi Genbutsu of waste) Zero Inventory #12;Just in Time in HealthcareJust in Time in Healthcare Takt time (pitch), one · · · · · · · · · · · · · · · · · · 5 WHY · · · RCA · · · 5 WHY · · #12; waste/ value waste/ value

Laksanacharoen, Sathaporn

248

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1995-10-24T23:59:59.000Z

249

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

1995-01-01T23:59:59.000Z

250

Method for calcining radioactive wastes  

DOE Patents (OSTI)

This invention relates to a method for the preparation of radioactive wastes in a low leachability form by calcining the radioactive waste on a fluidized bed of glass frit, removing the calcined waste to melter to form a homogeneous melt of the glass and the calcined waste, and then solidifying the melt to encapsulate the radioactive calcine in a glass matrix.

Bjorklund, William J. (Richland, WA); McElroy, Jack L. (Richland, WA); Mendel, John E. (Kennewick, WA)

1979-01-01T23:59:59.000Z

251

Methane generation from waste materials  

DOE Patents (OSTI)

An organic solid waste digester for producing methane from solid waste, the digester comprising a reactor vessel for holding solid waste, a sprinkler system for distributing water, bacteria, and nutrients over and through the solid waste, and a drainage system for capturing leachate that is then recirculated through the sprinkler system.

Samani, Zohrab A. (Las Cruces, NM); Hanson, Adrian T. (Las Cruces, NM); Macias-Corral, Maritza (Las Cruces, NM)

2010-03-23T23:59:59.000Z

252

Copenhagen Waste Management and Incineration  

E-Print Network (OSTI)

Copenhagen Waste Management and Incineration Florence, April 24 2009 Julie B. Svendsen 24 20092 Presentation · General introduction to Copenhagen Waste Management System · National incentives · Waste Management plan 2012 · Incineration plants #12;Florence, April 24 20093 Copenhagen Waste

Columbia University

253

Waste to Energy Time Activities  

E-Print Network (OSTI)

SEMINAR Waste to Energy Time Activities 9:30-9:40 Brief introduction of participants 9:40-10:10 Presentation of Dr. Kalogirou, "Waste to Energy: An Integral Part of Worldwide Sustainable Waste Management" 10. Sofia Bethanis, "Production of synthetic aggregates for use in structural concrete from waste to energy

Columbia University

254

Contained recovery of oily waste  

DOE Patents (OSTI)

A method is provided for recovering oily waste from oily waste accumulations underground comprising sweeping the oily waste accumulation with hot water to recover said oily waste, wherein said area treated is isolated from surrounding groundwater hydraulically. The hot water may be reinjected after the hot-water displacement or may be treated to conform to any discharge requirements.

Johnson, Jr., Lyle A. (Laramie, WY); Sudduth, Bruce C. (Laramie, WY)

1989-01-01T23:59:59.000Z

255

Urban Wood Waste Resource Assessment  

DOE Green Energy (OSTI)

This study collected and analyzed data on urban wood waste resources in 30 randomly selected metropolitan areas in the United States. Three major categories wood wastes disposed with, or recovered from, the municipal solid waste stream; industrial wood wastes such as wood scraps and sawdust from pallet recycling, woodworking shops, and lumberyards; and wood in construction/demolition and land clearing debris.

Wiltsee, G.

1998-11-20T23:59:59.000Z

256

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

Albert, R.

1992-06-30T23:59:59.000Z

257

Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant  

Science Conference Proceedings (OSTI)

The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source documents from the U.S. Nuclear RegulatoryCommission (NRC) and the New Mexico Environment Department (NMED) for acomprehensive and detailed listing of the requirements.This CH-WAC does not address the subject of waste characterization relating to adetermination of whether the waste is hazardous; rather, the sites are referred to theWaste Analysis Plan (WAP) contained in the WIPP Hazardous Waste Facility Permit fordetails of the sampling and analysis protocols to be used in determining compliance withthe required physical and chemical properties of the waste. Requirements andassociated criteria pertaining to a determination of the radiological properties of thewaste, however, are addressed in appendix A of this document. The collectiveinformation obtained from waste characterization records and acceptable knowledge(AK) serves as the basis for sites to certify that their CH-TRU waste satisfies the WIPPwaste acceptance criteria listed herein.

Washington TRU Solutions LLC

2005-12-29T23:59:59.000Z

258

Rethinking the Hanford Tank Waste Program  

Science Conference Proceedings (OSTI)

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

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

2002-02-26T23:59:59.000Z

259

Tank Waste Corporate Board Meeting 07/29/09 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

9/09 9/09 Tank Waste Corporate Board Meeting 07/29/09 The following documents are associated with the Tank Waste Corporate Board Meeting held on July 29th, 2009. Fuel Cycle Research and Development Program Retrieval and Repackaging of RH-TRU Waste - General Presentation Modular Hot Cell Technology Tank Waste System Integrated Project Team Gunite Tanks Waste Retrieval and Closure Operations at Oak Ridge Nattional Laboratory Integrated Facilities Disposition Program Oak Ridge National Laboratory TRU Waste Processing Center Tank Waste Processing Supernate Processing System Chemical Cleaning Program Review Enhanced Chemical Cleaning Hanford Single-Shell Tank Integrity Program Modeling the Performance of Engineered Systems for Closure and Near-Surface Disposal Nuclear Safety R&D in the Waste Processing Technology Development &

260

EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5: Disposal of Greater-than-Class-C Low-Level Radioactive 5: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste Summary This EIS evaluates the reasonably foreseeable environmental impacts associated with the proposed development, operation, and long-term management of a disposal facility or facilities for Greater-Than-Class C (GTCC) low-level radioactive waste and GTCC-like waste. The Environmental Protection Agency is a cooperating agency in the preparation of this EIS. The EIS evaluates potential impacts from the construction and operation of

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261

Tank Waste Strategy Update  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tank Waste Subcommittee www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 Tank Waste Subcommittee Ken Picha Office of Environmental Management December 5, 2011 Background Tank Waste Subcommittee (TWS)originally chartered, in response to Secretary's request to perform a technical review of Waste Treatment and Immobilization Plant (WTP) in May 2010. Three tasks: o Verification of closure of WTP External Flowsheet Review Team (EFRT) issues. o WTP Technical Design Review o WTP potential improvements Report completed and briefed to DOE in September 2010 www.em.doe.gov safety performance cleanup closure E M Environmental Management 2 Report completed and briefed to DOE in September 2010 Follow-on scope for TWS identified immediately after briefing to DOE and

262

Waste Treatment Plant Overview  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Site, located in southeastern Washington state, Hanford Site, located in southeastern Washington state, was the largest of three defense production sites in the U.S. Over the span of 40 years, it was used to produce 64 metric tons of plutonium, helping end World War II and playing a major role in military defense efforts during the Cold War. As a result, 56 million gallons of radioactive and chemical wastes are now stored in 177 underground tanks on the Hanford Site. To address this challenge, the U.S. Department of Energy contracted Bechtel National, Inc., to design and build the world's largest radioactive waste treatment plant. The Waste Treatment and Immobilization Plant (WTP), also known as the "Vit Plant," will use vitrification to immobilize most of Hanford's dangerous tank waste.

263

ORNL radioactive waste operations  

SciTech Connect

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards.

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01T23:59:59.000Z

264

Handford Waste Division  

NLE Websites -- All DOE Office Websites (Extended Search)

1 Hanford Waste Diversion SAN Teleconference June 21, 2012 Tom Ferns, DOE-RL 2 Hanford Site Mission The Hanford Site is engaged in one of the largest and most complex environmental...

265

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

request for further delays After the EPA certified that the WIPP met the standards for disposal of transuranic waste in May 1998, then-New Mexico Attorney General Tom Udall...

266

Vitrification of waste  

DOE Patents (OSTI)

A method for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300{degrees}C to 800{degrees}C to incinerate organic materials, then heated further to a temperature in the range of approximately 1100{degrees}C to 1400{degrees}C at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

Wicks, G.G.

1992-12-31T23:59:59.000Z

267

Treatment of organic waste  

DOE Patents (OSTI)

An organic waste containing at least one element selected from the group consisting of strontium, cesium, iodine and ruthenium is treated to achieve a substantial reduction in the volume of the waste and provide for fixation of the selected element in an inert salt. The method of treatment comprises introducing the organic waste and a source of oxygen into a molten salt bath maintained at an elevated temperature to produce solid and gaseous reaction products. The gaseous reaction products comprise carbon dioxide and water vapor, and the solid reaction products comprise the inorganic ash constituents of the organic waste and the selected element which is retained in the molten salt. The molten salt bath comprises one or more alkali metal carbonates, and may optionally include from 1 to about 25 wt.% of an alkali metal sulfate.

Grantham, LeRoy F. (Calabasas, CA)

1979-01-01T23:59:59.000Z

268

Independent Oversight Review, Savannah River Site Salt Waste Processing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Savannah River Site Salt Waste Savannah River Site Salt Waste Processing Facility - August 2013 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - August 2013 August 2013 Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development. This report documents the results of an independent oversight review of the safety basis and design development for the Salt Waste Processing Facility (SWPF) at the U.S. Department of Energy (DOE) Savannah River Site. The review was performed February 12-14, 2013 by DOE's Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The purpose of the review was to evaluate the safety basis, design, and the associated technical documents developed for

269

Independent Oversight Review, Savannah River Site Salt Waste Processing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Savannah River Site Salt Waste Savannah River Site Salt Waste Processing Facility - August 2013 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - August 2013 August 2013 Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development. This report documents the results of an independent oversight review of the safety basis and design development for the Salt Waste Processing Facility (SWPF) at the U.S. Department of Energy (DOE) Savannah River Site. The review was performed February 12-14, 2013 by DOE's Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The purpose of the review was to evaluate the safety basis, design, and the associated technical documents developed for

270

3116 WASTE DETERMINATIONS PUBLIC MEETINGS AND GENERIC TECHNICAL ISSUES  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3116 WASTE DETERMINATIONS PUBLIC MEETINGS AND GENERIC TECHNICAL 3116 WASTE DETERMINATIONS PUBLIC MEETINGS AND GENERIC TECHNICAL ISSUES SUMMARIES 3116 WASTE DETERMINATIONS PUBLIC MEETINGS AND GENERIC TECHNICAL ISSUES SUMMARIES Below are public meeting summaries and general technical issue summaries relating to 3116 waste determinations. The 3116 Public Meeting Summaries cover public meetings that the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) periodically host to provide the status of activities associated with waste determinations under Section 3116 (a) of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005. 3116 Public Meeting Summaries - July 2007 3116 Public Meeting Summaries - November 2006 The Generic Technical Issues Summaries cover the informal technical discussions between representatives of the Department of Energy (DOE),

271

Independent Oversight Review, Oak Ridge Transuranic Waste Processing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oak Ridge Transuranic Waste Oak Ridge Transuranic Waste Processing Center, September 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Center, September 2013 September 2013 Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes. This report documents the results of an independent oversight review of the management of safety significant structures, systems, and components at the Oak Ridge Transuranic Waste Processing Center (TWPC). The review was performed April 2-5, April 15-19, and May 19-23, 2013, by the Department of Energy's (DOE) Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The review was carried out within the broader context of an ongoing program of

272

Citrus Waste Biomass Program  

DOE Green Energy (OSTI)

Renewable Spirits is developing an innovative pilot plant bio-refinery to establish the commercial viability of ehtanol production utilizing a processing waste from citrus juice production. A novel process based on enzymatic hydrolysis of citrus processing waste and fermentation of resulting sugars to ethanol by yeasts was successfully developed in collaboration with a CRADA partner, USDA/ARS Citrus and Subtropical Products Laboratory. The process was also successfully scaled up from laboratory scale to 10,000 gal fermentor level.

Karel Grohman; Scott Stevenson

2007-01-30T23:59:59.000Z

273

Medical and Biohazardous Waste Generator's Guide (Revision 2)  

E-Print Network (OSTI)

Biohazardous Waste Training Medical/Biohazardous WasteInspections 7. Forms and Supplies Medical Waste AccumulationLog Ordering Medical Waste Supplies 8. Solid Medical Waste

Waste Management Group

2006-01-01T23:59:59.000Z

274

Framework for managing wastes from oil and gas exploration and production (E&P) sites.  

Science Conference Proceedings (OSTI)

Oil and gas companies operate in many countries around the world. Their exploration and production (E&P) operations generate many kinds of waste that must be carefully and appropriately managed. Some of these wastes are inherently part of the E&P process; examples are drilling wastes and produced water. Other wastes are generic industrial wastes that are not unique to E&P activities, such as painting wastes and scrap metal. Still other wastes are associated with the presence of workers at the site; these include trash, food waste, and laundry wash water. In some host countries, mature environmental regulatory programs are in place that provide for various waste management options on the basis of the characteristics of the wastes and the environmental settings of the sites. In other countries, the waste management requirements and authorized options are stringent, even though the infrastructure to meet the requirements may not be available yet. In some cases, regulations and/or waste management infrastructure do not exist at all. Companies operating in these countries can be confronted with limited and expensive waste management options.

Veil, J. A.; Puder, M. G.; Environmental Science Division

2007-09-15T23:59:59.000Z

275

Final Environmental Impact Statement for Treating Transuranic (TRU)/Alpha Low-level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee  

SciTech Connect

The DOE proposes to construct, operate, and decontaminate/decommission a TRU Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste. This document analyzes the potential environmental impacts associated with five alternatives--No Action, the Low-Temperature Drying Alternative (Preferred Alternative), the Vitrification Alternative, the Cementation Alternative, and the Treatment and Waste Storage at Oak Ridge National Laboratory (ORNL) Alternative.

N /A

2000-06-30T23:59:59.000Z

276

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification.

Albert, R.

1992-06-30T23:59:59.000Z

277

Project report for the commercial disposal of mixed low-level waste debris  

SciTech Connect

This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project.

Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.

1994-05-01T23:59:59.000Z

278

Mediated electrochemical hazardous waste destruction  

SciTech Connect

There are few permitted processes for mixed waste (radioactive plus chemically hazardous) treatment. We are developing electrochemical processes that convert the toxic organic components of mixed waste to water, carbon dioxide, an innocuous anions such as chloride. Aggressive oxidizer ions such as Ag{sup 2+} or Ce{sup +4} are produced at an anode. These can attack the organic molecules directly. They can also attack water which yields hydroxyl free radicals that in turn attack the organic molecules. The condensed (i.e., solid and/or liquid) effluent streams contain the inorganic radionuclide forms. These may be treated with existing technology and prepared for final disposal. Kinetics and the extent of destruction of some toxic organics have been measured. Depending on how the process is operated, coulombic efficiency can be nearly 100%. In addition, hazardous organic materials are becoming very expensive to dispose of and when they are combined with transuranic radioactive elements no processes are presently permitted. Mediated electrochemical oxidation is an ambient-temperature aqueous-phase process that can be used to oxidize organic components of mixed wastes. Problems associated with incineration, such as high-temperature volatilization of radionuclides, are avoided. Historically, Ag (2) has been used as a mediator in this process. Fe(6) and Co(3) are attractive alternatives to Ag(2) since they form soluble chlorides during the destruction of chlorinated solvents. Furthermore, silver itself is a toxic heavy metal. Quantitative data has been obtained for the complete oxidation of ethylene glycol by Fe(6) and Co(3). Though ethylene glycol is a nonhalogenated organic, this data has enabled us to make direct comparisons of activities of Fe(6) and Co(3) with Ag(2). Very good quantitative data for the oxidation of ethylene glycol by Ag(2) had already been collected. 4 refs., 6 figs.

Hickman, R.G.; Farmer, J.C.; Wang, F.T.

1991-08-01T23:59:59.000Z

279

Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility  

SciTech Connect

This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energys Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

Bonnema, Bruce Edward

2001-09-01T23:59:59.000Z

280

Transporting & Shipping Hazardous Materials at LBNL: Waste -...  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste: Hazardous, Biohazardous, Medical or Radioactive Do not transport or ship hazardous material wastes off-site. Only Waste Management, Radiation Protection or approved...

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Nonhazardous Solid Waste Management Regulations & Criteria (Mississippi)  

Energy.gov (U.S. Department of Energy (DOE))

The purpose of the Nonhazardous Solid Waste Management Regulations & Criteria is to establish a minimum State Criteria under the Mississippi Solid Waste Law for all solid waste management...

282

Hazardous Waste Management (Oklahoma) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

treatment and storage of such waste. It also mentions the availability of tax credits for waste facilities. Energy recovery from the destruction of a hazardous waste may be...

283

Annual Transuranic Waste Inventory Report - 2013  

NLE Websites -- All DOE Office Websites (Extended Search)

contain both combustible and noncombustible waste items. Combustible waste may include wood, plastics, paper, and rags. Noncombustible waste items may include metals, glass,...

284

Bioenergy development from agricultural waste on Northern ...  

Science Conference Proceedings (OSTI)

... Summary This project will convert agricultural waste, including food waste, rice straw, and other organic farm waste to bioethanol through bacterial ...

2011-08-02T23:59:59.000Z

285

Site Programs & Cooperative Agreements: Waste Isolation Pilot...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Isolation Pilot Plant Site Programs & Cooperative Agreements: Waste Isolation Pilot Plant Waste Isolation Pilot Plant (WIPP) The DOE Carlsbad Field Office funds a number of...

286

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Municipal Waste Planning, Recycling and Waste Reduction Act Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Pennsylvania Program Type Environmental Regulations

287

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

Open Energy Info (EERE)

Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) No revision has been approved for this page. It is currently under review by our subject matter experts. Jump to: navigation, search Last modified on February 13, 2013. EZFeed Policy Place Pennsylvania Name Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Policy Category Other Policy Policy Type Environmental Regulations Affected Technologies Biomass/Biogas, Coal with CCS, Concentrating Solar Power, Energy Storage, Fuel Cells, Geothermal Electric, Hydroelectric, Hydroelectric (Small), Natural Gas, Nuclear, Solar Photovoltaics, Wind energy Active Policy Yes Implementing Sector State/Province Program Administrator Pennsylvania Department of Environmental Protection

288

Certification plan transuranic waste: Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of transuranic (TRU) waste handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). The plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Quality Assurance Implementing Management Plan (QAIMP) for the HWBF; and a list of the current and planned implementing procedures used in waste certification.

1992-06-01T23:59:59.000Z

289

Solid Waste and Infectious Waste Regulations (Ohio) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and Infectious Waste Regulations (Ohio) and Infectious Waste Regulations (Ohio) Solid Waste and Infectious Waste Regulations (Ohio) < Back Eligibility Utility Agricultural Investor-Owned Utility Industrial Municipal/Public Utility Local Government Rural Electric Cooperative Program Info State Ohio Program Type Environmental Regulations Provider Ohio Environmental Protection Agency This chapter of the law that establishes the Ohio Environmental Protection Agency establishes the rules and regulations regarding solid waste. The chapter establishes specific regulations for biomass facilities, which includes permitting, siting, operation, safety guidelines, and closing requirements. Siting regulations include setbacks from waste handling areas for state facilities (1000 feet from jails, schools), requirements for not siting

290

Focus Sheet | Hazardous Waste Checklist How to be ready for state hazardous waste  

E-Print Network (OSTI)

Focus Sheet | Hazardous Waste Checklist How to be ready for state hazardous waste inspectors. See a hazardous waste inspection. ons, rrosive. n hemicals? ical waste. Waste-like chemicals have als Are you. Are your waste containers properly labeled? us Waste label as soon t Do you accumulate waste in a safe

Wilcock, William

291

LANL reaches waste shipment milestone  

NLE Websites -- All DOE Office Websites (Extended Search)

LANL reaches waste shipment milestone LANL reaches waste shipment milestone LANL reaches waste shipment milestone The Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. May 31, 2011 A shipment of transuranic waste on its way to the WIPP repository A shipment of transuranic waste on its way to the WIPP repository. Contact Fred deSousa Communicatons Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total.

292

Mixed waste characterization reference document  

SciTech Connect

Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization.

1997-09-01T23:59:59.000Z

293

Process to separate transuranic elements from nuclear waste  

DOE Patents (OSTI)

A process is described for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1989-03-21T23:59:59.000Z

294

Process to separate transuranic elements from nuclear waste  

DOE Patents (OSTI)

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1988-07-12T23:59:59.000Z

295

Waste form product characteristics  

SciTech Connect

The Department of Energy has operated nuclear facilities at the Idaho National Engineering Laboratory (INEL) to support national interests for several decades. Since 1953, it has supported the development of technologies for the storage and reprocessing of spent nuclear fuels (SNF) and the resultant wastes. However, the 1992 decision to discontinue reprocessing of SNF has left nearly 768 MT of SNF in storage at the INEL with unspecified plans for future dispositioning. Past reprocessing of these fuels for uranium and other resource recovery has resulted in the production of 3800 M{sup 3} calcine and a total inventory of 7600 M{sup 3} of radioactive liquids (1900 M{sup 3} destined for immediate calcination and the remaining sodium-bearing waste requiring further treatment before calcination). These issues, along with increased environmental compliance within DOE and its contractors, mandate operation of current and future facilities in an environmentally responsible manner. This will require satisfactory resolution of spent fuel and waste disposal issues resulting from the past activities. A national policy which identifies requirements for the disposal of SNF and high level wastes (HLW) has been established by the Nuclear Waste Policy Act (NWPA) Sec.8,(b) para(3)) [1982]. The materials have to be conditioned or treated, then packaged for disposal while meeting US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. The spent fuel and HLW located at the INEL will have to be put into a form and package that meets these regulatory criteria. The emphasis of Idaho Chemical Processing Plant (ICPP) future operations has shifted toward investigating, testing, and selecting technologies to prepare current and future spent fuels and waste for final disposal. This preparation for disposal may include mechanical, physical and/or chemical processes, and may differ for each of the various fuels and wastes.

Taylor, L.L.; Shikashio, R.

1995-01-01T23:59:59.000Z

296

RETRIEVAL & TREATMENT OF HANFORD TANK WASTE  

SciTech Connect

The Hanford Tank Farms contain 53 million gal of radioactive waste accumulated during over 50 years of operations. The waste is stored in 177 single-shell and double-shell tanks in the Hanford 200 Areas. The single-shell tanks were put into operation from the early 1940s through the 1960s with wastes received from several generations of processing facilities for the recovery of plutonium and uranium, and from laboratories and other ancillary facilities. The overall hanford Tank Farm system represents one of the largest nuclear legacies in the world driving towards completion of retrieval and treatment in 2028 and the associated closure activity completion by 2035. Remote operations, significant radiation/contamination levels, limited access, and old facilities are just some of the challenges faced by retrieval and treatment systems. These systems also need to be able to successfully remove 99% or more of the waste, and support waste treatment, and tank closure. The Tank Farm retrieval program has ramped up dramatically in the past three years with design, fabrication, installation, testing, and operations ongoing on over 20 of the 149 single-shell tanks. A variety of technologies are currently being pursued to retrieve different waste types, applications, and to help establish a baseline for recovery/operational efficiencies. The paper/presentation describes the current status of retrieval system design, fabrication, installation, testing, readiness, and operations, including: (1) Saltcake removal progress in Tanks S-102, S-109, and S-112 using saltcake dissolution, modified sluicing, and high pressure water lancing techniques; (2) Sludge vacuum retrieval experience from Tanks C-201, C-202, C-203, and C-204; (3) Modified sluicing experience in Tank C-103; (4) Progress on design and installation of the mobile retrieval system for sludge in potentially leaking single-shell tanks, particularly Tank C-101; and (5) Ongoing installation of various systems in the next generation of tanks to be retrieved.

EACKER, J.A.; SPEARS, J.A.; STURGES, M.H.; MAUSS, B.M.

2006-01-20T23:59:59.000Z

297

Mixed Waste Focus Area Working Group: An Integrated Approach to Mercury Waste Treatment and Disposal. Revision 1  

SciTech Connect

May 1996, the U.S. Department of Energy (DOE) Mixed Waste Focus Area (MWFA) initiated the Mercury Work Group (HgWG). The HgWG was established to address and resolve the issues associated with Mercury- contaminated mixed wastes (MWs). During the initial technical baseline development process of the MWFA, three of the top four technology deficiencies identified were related to (1) amalgamation, (2) stabilization, and (3) separation and removal for the treatment of mercury and mercury-contaminated mixed waste (MW). The HgWG is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these needs.

Morris, M.I.; Conley, T.B.; Osborne-Lee, I.W.

1997-09-08T23:59:59.000Z

298

Inconsistent pathways of household waste  

Science Conference Proceedings (OSTI)

The aim of this study was to provide policy-makers and waste management planners with information about how recycling programs affect the quantities of specific materials recycled and disposed of. Two questions were addressed: which factors influence household waste generation and pathways? and how reliable are official waste data? Household waste flows were studied in 35 Swedish municipalities, and a wide variation in the amount of waste per capita was observed. When evaluating the effect of different waste collection policies, it was found to be important to identify site-specific factors influencing waste generation. Eleven municipal variables were investigated in an attempt to explain the variation. The amount of household waste per resident was higher in populous municipalities and when net commuting was positive. Property-close collection of dry recyclables led to increased delivery of sorted metal, plastic and paper packaging. No difference was seen in the amount of separated recyclables per capita when weight-based billing for the collection of residual waste was applied, but the amount of residual waste was lower. Sixteen sources of error in official waste statistics were identified and the results of the study emphasize the importance of reliable waste generation and composition data to underpin waste management policies.

Dahlen, Lisa [Division of Waste Science and Technology, Lulea University of Technology, SE, 971 87 Lulea (Sweden)], E-mail: lisa.dahlen@ltu.se; Aberg, Helena [Department of Food, Health and Environment, University of Gothenburg, P.O. Box 12204, SE, 402 42 Gothenburg (Sweden); Lagerkvist, Anders [Division of Waste Science and Technology, Lulea University of Technology, SE, 971 87 Lulea (Sweden); Berg, Per E.O. [HB Anttilator, Stagnellsgatan 3, SE, 652 23, Karlstad (Sweden)

2009-06-15T23:59:59.000Z

299

DOE Waste Treatability Group Guidance  

Science Conference Proceedings (OSTI)

This guidance presents a method and definitions for aggregating U.S. Department of Energy (DOE) waste into streams and treatability groups based on characteristic parameters that influence waste management technology needs. Adaptable to all DOE waste types (i.e., radioactive waste, hazardous waste, mixed waste, sanitary waste), the guidance establishes categories and definitions that reflect variations within the radiological, matrix (e.g., bulk physical/chemical form), and regulated contaminant characteristics of DOE waste. Beginning at the waste container level, the guidance presents a logical approach to implementing the characteristic parameter categories as part of the basis for defining waste streams and as the sole basis for assigning streams to treatability groups. Implementation of this guidance at each DOE site will facilitate the development of technically defined, site-specific waste stream data sets to support waste management planning and reporting activities. Consistent implementation at all of the sites will enable aggregation of the site-specific waste stream data sets into comparable national data sets to support these activities at a DOE complex-wide level.

Kirkpatrick, T.D.

1995-01-01T23:59:59.000Z

300

Waste Form Performance Modeling [Nuclear Waste Management using...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Transuranic Waste Tabletop  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Transuranic (TRU) Waste Transuranic (TRU) Waste (Hazard Class 7 Radioactive) Moderator's Version of Tabletop Prepared for the Department of Energy Office of Transportation and Emergency Management 02B00215-07D.p65 This page intentionally left blank table of contents Transportation Emergency Preparedness Program (TEPP) planning tools planning tools planning tools planning tools T T T T Tr r r r ransur ansur ansur ansur ansuranic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) Waste aste aste aste aste (Hazar (Hazar (Hazar (Hazar (Hazard Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radioactiv activ activ activ active) e) e) e) e) Moder Moder Moder Moder Moderat at at at ator' or' or' or' or's V s V s V s V s Version of T ersion of T ersion of T ersion of T ersion of Tablet ablet ablet ablet abletop

302

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

2 2 3 T he journey to the WIPP began nearly 60 years before the first barrels of transuranic waste arrived at the repository. The United States produced the world's first sig- nificant quantities of transuranic material during the Manhattan Project of World War II in the early 1940s. The government idled its plutonium- producing reactors and warhead manu- facturing plants at the end of the Cold War and scheduled most of them for dismantlement. However, the DOE will generate more transuranic waste as it cleans up these former nuclear weapons facilities. The WIPP is a cor- nerstone of the effort to clean up these facilities by providing a safe repository to isolate transuranic waste in disposal rooms mined out of ancient salt beds, located 2,150 feet below ground. The need for the WIPP

303

EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste  

Energy.gov (U.S. Department of Energy (DOE))

This EIS evaluates the reasonably foreseeable environmental impacts associated with the proposed development, operation, and long-term management of a disposal facility or facilities for Greater-Than-Class C (GTCC) low-level radioactive waste and GTCC-like waste. The Environmental Protection Agency is a cooperating agency in the preparation of this EIS.

304

Radioactive Waste Management Complex low-level waste radiological performance assessment  

Science Conference Proceedings (OSTI)

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01T23:59:59.000Z

305

Weigh your waste: a sustainable way to reduce waste  

Science Conference Proceedings (OSTI)

An increased concern for the environment has brought about an arena to develop and experiment with new devices to support sustainable design. The 'Weigh Your Waste' (WYW) device will allow the user to monitor their waste charges and provide a platform ... Keywords: bin tax, pay by weight, proenvironmental behavior, recycling, rubbish, sustainable design, trash, waste

Alex A. Gartland; Paulina Piasek

2009-04-01T23:59:59.000Z

306

Swedish nuclear waste efforts  

SciTech Connect

After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981.

Rydberg, J.

1981-09-01T23:59:59.000Z

307

Associate Admin.  

National Nuclear Security Administration (NNSA)

Associate Admin. for Management & Budget Associate Admin. for Acquisition & Proj. Management Under Secretary for Nuclear Security & Administrator Principal Deputy Administrator...

308

Comprehensive Municipal Solid Waste Management, Resource Recovery...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Municipal Solid Waste Management, Resource Recovery, and Conservation Act (Texas) Comprehensive Municipal Solid Waste Management, Resource Recovery, and Conservation...

309

Transuranic Waste Transportation Working Group Agenda | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda More Documents & Publications...

310

UK Radioactive Waste: Classification, Sources and Management ...  

Science Conference Proceedings (OSTI)

Paper contents outlook: Introduction; Radioactive waste classification; Sources of waste (Nuclear power plant operation/decommissioning, Reprocessing and...

311

Radioactive waste systems and radioactive effluents  

SciTech Connect

Radioactive waste systems for handling gaseous, liquid, and solid wastes generated at light and pressurized water reactors are described. (TFD)

Row, T.H.

1973-01-01T23:59:59.000Z

312

Waste Disposal (Illinois) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Disposal (Illinois) Waste Disposal (Illinois) Eligibility Commercial Construction Industrial Utility Program Information Illinois Program Type Environmental Regulations This...

313

Solid Waste Management Program (Missouri)  

Energy.gov (U.S. Department of Energy (DOE))

The Solid Waste Management Program in the Department of Natural Resources regulates the management of solid waste in the state of Missouri. A permit is required prior to the construction or...

314

Waste Management Assistance Act (Iowa)  

Energy.gov (U.S. Department of Energy (DOE))

This section promotes the proper and safe storage, treatment, and disposal of solid, hazardous, and low-level radioactive wastes in Iowa, and calls on Iowans to assume responsibility for waste...

315

Delaware Solid Waste Authority (Delaware)  

Energy.gov (U.S. Department of Energy (DOE))

The Delaware Solid Waste Authority (DSWA) runs three landfills, all of which recover methane and generate electricity with a total capacity of 24 MWs. The DSWA Solid Waste Plan includes goals,...

316

Waste Isolation Pilot Plant  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste Isolation Pilot Plant Waste Isolation Pilot Plant AFFIDAVIT FOR SURVIVING RELATIVE STATE _______________ ) ) ss: __________________ COUNTY OF _____________ ) That I, ________________________, am the _________________________ (Indicate relationship) of ___________________________, who is deceased and make the attached request pursuant to 10 CFR, Section 1008. That the information contained on the attached request is true and correct to the best of my knowledge and belief, and I am signing this authorization subject to the penalties provided in 18 U.S.C. 1001. ____________________________ SIGNATURE NOTARIZATION: SUBSCRIBED and SWORN to before me this ______day of __________, 20_____

317

Explosive Waste Treatment Facility  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

106 106 Environment a 1 Assessment for th.e Explosive Waste Treatment Facility at Site 300 Lawrence Livermore National Laboratory MASTER November 1995 U.S. Department of Energy Office of Environmental Restoration and Waste Management Washington, DOC. 20585 Portions of this document maly be illegible in electronic image products. Images are produced from the best available original document. Table of Contents 1 . 0 2.0 3 . 0 4.0 5 . 0 6.0 7 . 0 8 . 0 Document Summary .............................................................. 1 Purpose and Need for Agency Action ............................................. 3 Description of the Proposed Action and Alternatives ............................ 4 3.1.1 Location ............................................................. 4

318

SOLID WASTE MANAGEMENT PLAN  

E-Print Network (OSTI)

ACKNOWLEDGMENTS The Chelan County Public Works Department would like to thank the following organizations and individuals for their assistance in the development of this plan: ? Chelan Countys Solid Waste Council members, past and present, and the municipalities they represent. ? Chelan Countys Solid Waste Advisory Committee members, past and present, and the agencies and businesses they represented. ? the ChelanDouglas Health District staff. ? Washington Department of Ecology staff. Chelan County residents and businesses also contributed to this document through comments provided during public meetings and through various other channels. The Board of County Commissioners and the Public Works Department gratefully acknowledge this input by the

unknown authors

2007-01-01T23:59:59.000Z

319

Tank Waste Corporate Board Meeting 03/05/09 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tank Waste Corporate Board Meeting 03/05/09 Tank Waste Corporate Board Meeting 03/05/09 Tank Waste Corporate Board Meeting 03/05/09 The following documents are associated with the Tank Waste Corporate Board Meeting held on March 5th, 2009. Overview of Integrated Waste Treatment Unit Desired PU Loading During Vitrification HLW System Integrated Project Team Waste Determination and Section 3116 of the 2005 National Defense Authorization Act - HQ Perspective Status of Art & Practice of Performance Assessment within the DOE Complex Experience from the Short Course on Introduction to Nuclear Chemistry and Fuel Cycle Separations and Future Educational Opportunities Role of Liquid Waste Pretreatment Technologies in Solving the DOE Clean-up Mission Performance Assessment Community of Practice Action Item Review and Status

320

Characterization, Leaching, and Filtrations Testing of Ferrocyanide Tank sludge (Group 8) Actual Waste Composite  

SciTech Connect

This is the final report in a series of eight reports defining characterization, leach, and filtration testing of a wide variety of Hanford tank waste sludges. The information generated from this series is intended to supplement the Waste Treatment and Immobilization Plant (WTP) project understanding of actual waste behaviors associated with tank waste sludge processing through the pretreatment portion of the WTP. The work described in this report presents information on a high-iron waste form, specifically the ferrocyanide tank waste sludge. Iron hydroxide has been shown to pose technical challenges during filtration processing; the ferrocyanide tank waste sludge represented a good source of the high-iron matrix to test the filtration processing.

Fiskum, Sandra K.; Billing, Justin M.; Crum, J. V.; Daniel, Richard C.; Edwards, Matthew K.; Shimskey, Rick W.; Peterson, Reid A.; MacFarlan, Paul J.; Buck, Edgar C.; Draper, Kathryn E.; Kozelisky, Anne E.

2009-02-28T23:59:59.000Z

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Waste Minimization/Pollution Prevention Crosscut Plan, 1994  

SciTech Connect

This plan establishes a Department-wide goal to reduce total releases of toxic chemicals to the environment and off-site transfers of such toxic chemicals by 50 percent by December 31, 1999, in compliance with Executive Order 12856. Each site that meets the threshold quantities of toxic chemicals established in the Emergency Planning and Community Right-to-Know Act (EPCRA) will participate in this goal. In addition, each DOE site will establish site-specific goals to reduce generation of hazardous, radioactive, radioactive mixed, and sanitary wastes and pollutants, as applicable. Implementation of this plan will represent a major step toward the environmental risks and costs associated with DOE operations and increasing the Department`s use of preventive environmental management practices. Investing in Waste Minimization Pollution Prevention (WMin/PP) steadily reduce hazardous and radioactive waste generation and will reduce the need for waste management and unnecessary expenditures for waste treatment, storage, and disposal. A preventive approach to waste management will help solve current environmental and regulatory issues and reduce the need for costly future corrective actions. The purpose of this plan is to establish the strategic framework for integrating WMin/PP into all DOE internal activities. This program includes setting DOE policy and goals for reducing the generation of wastes and pollutants, increasing recycling activities, and establishing an infrastructure to achieve and measure the goals throughout the DOE complex. Waste Minimization and Pollution Prevention Awareness Plans, submitted to Headquarters by DOE field sites, will incorporate the WMin/PP activities and goals outlined in this plan. Success of the DOE WMin/PP program is dependent upon each field operation becoming accountable for resources used, wastes and pollutants generated, and wastes recycled.

1994-02-28T23:59:59.000Z

322

Process for treating fission waste  

DOE Patents (OSTI)

A method is described for the treatment of fission waste. A glass forming agent, a metal oxide, and a reducing agent are mixed with the fission waste and the mixture is heated. After melting, the mixture separates into a glass phase and a metal phase. The glass phase may be used to safely store the fission waste, while the metal phase contains noble metals recovered from the fission waste.

Rohrmann, Charles A. (Kennewick, WA); Wick, Oswald J. (Richland, WA)

1983-01-01T23:59:59.000Z

323

Seal welded cast iron nuclear waste container  

SciTech Connect

This invention identifies methods and articles designed to circumvent metallurgical problems associated with hermetically closing an all cast iron nuclear waste package by welding. It involves welding nickel-carbon alloy inserts which are bonded to the mating plug and main body components of the package. The welding inserts might be bonded in place during casting of the package components. When the waste package closure weld is made, the most severe thermal effects of the process are restricted to the nickel-carbon insert material which is far better able to accommodate them than is cast iron. Use of nickel-carbon weld inserts should eliminate any need for pre-weld and post-weld heat treatments which are a problem to apply to nuclear waste packages. Although the waste package closure weld approach described results in a dissimilar metal combination, the relative surface area of nickel-to-iron, their electrochemical relationship, and the presence of graphite in both materials will act to prevent any galvanic corrosion problem.

Filippi, Arthur M. (Pittsburgh, PA); Sprecace, Richard P. (Murrysville, PA)

1987-01-01T23:59:59.000Z

324

Low level tank waste disposal study  

SciTech Connect

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

Mullally, J.A.

1994-09-29T23:59:59.000Z

325

EIS-0303: Savannah River Site High-Level Waste Tank Closure | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

03: Savannah River Site High-Level Waste Tank Closure 03: Savannah River Site High-Level Waste Tank Closure EIS-0303: Savannah River Site High-Level Waste Tank Closure SUMMARY This EIS evaluates alternatives for closing 49 high-level radioactive waste tanks and associated equipment such as evaporator systems, transfer pipelines, diversion boxes, and pump pits. DOE selected the preferred alternative identified in the Final EIS, Stabilize Tanks-Fill with Grout, to guide development and implementation of closure of the high-level waste tanks and associated equipment at the Savannah River Site. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD March 5, 2012 EIS-0303: Supplement Analysis Savannah River Site High-Level Waste Tank Closure, SC July 8, 2011 EIS-0303: Notice of Intent to Prepare an Environmental Impact Statement

326

Mixed Waste Focus Area Mercury Working Group: An integrated approach to mercury waste treatment and disposal  

SciTech Connect

In May 1996, the US Department of Energy (DOE) Mixed Waste Focus Area (MWFA) initiated the Mercury Working Group (HgWG). The HgWG was established to address and resolve the issues associated with mercury contaminated mixed wastes. During the MWFA`s initial technical baseline development process, three of the top four technology deficiencies identified were related to the need for amalgamation, stabilization, and separation removal technologies for the treatment of mercury and mercury contaminated mixed waste. The HgWG is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these areas. The focus of the HgWG is to better establish the mercury related treatment technologies at the DOE sites, refine the MWFA technical baseline as it relates to mercury treatment, and make recommendations to the MWFA on how to most effectively address these needs. Based on the scope and magnitude of the mercury mixed waste problem, as defined by HgWG, solicitations and contract awards have been made to the private sector to demonstrate both the amalgamation and stabilization processes using actual mixed wastes. Development efforts are currently being funded that will address DOE`s needs for separation removal processes. This paper discusses the technology selection process, development activities, and the accomplishments of the HgWG to date through these various activities.

Conley, T.B.; Morris, M.I.; Osborne-Lee, I.W.

1998-01-01T23:59:59.000Z

327

FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2  

Science Conference Proceedings (OSTI)

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company`s Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division`s treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on ranges provided by the waste generators, this baseline volume could fluctuate between a minimum of about 59,720 cubic meters and a maximum of about 152,170 cubic meters. The range is primarily due to uncertainties associated with the Tank Waste Remediation System (TWRS) program, including uncertainties regarding retrieval of long-length equipment, scheduling, and tank retrieval technologies.

Templeton, K.J.

1996-05-23T23:59:59.000Z

328

RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE BY FLUIDIZED BED STEAM REFORMING USING THE BENCH SCALE REFORMER PLATFORM  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of {sup 125/129}I and {sup 99}Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

2012-02-02T23:59:59.000Z

329

WASTE DISPOSAL SECTION CORNELL UNIVERSITY  

E-Print Network (OSTI)

2/07 WASTE DISPOSAL SECTION CORNELL UNIVERSITY PROCEDURE for DISPOSAL of RADIOACTIVE MATERIALS This procedure has been developed to ensure the safety of those individuals who handle radioactive waste identified hazardous waste, or other unusual issues require special consideration. Contact the Department

Manning, Sturt

330

Hazardous Waste Management Keith Williams  

E-Print Network (OSTI)

Hazardous Waste Management Keith Williams DES ­ Environmental Affairs Extension 53163 #12,100 Locally · 1998 Univ of Va $33,990 · 1998 Univ. of MD $0 !!!!! #12;Hazardous Waste Disposal Procedures Hazardous (Chemical) Waste Management in University of Maryland Laboratories o All laboratories and work

Appelbaum, Ian

331

Laboratory Waste Disposal HAZARDOUS GLASS  

E-Print Network (OSTI)

Laboratory Waste Disposal HAZARDOUS GLASS Items that could cut or puncture skin or trash- can liners. This waste stream must be boxed to protect custodial staff. It goes directly to the landfill lined cardboard box. Tape seams with heavy duty tape to contain waste. Limit weight to 20 lbs. Or

Sheridan, Jennifer

332

Waste Pickup Form User's Guide  

E-Print Network (OSTI)

Waste Pickup Form User's Guide Updated: 3/13/12 #12;Introduction: Welcome to the Cal State University Fullerton Online Waste Pickup Form User's Guide. In this guide you will learn what you can use phosphorus-32) 3. To request a pickup of universal waste including light bulbs, aerosol cans, batteries

de Lijser, Peter

333

Waste incineration and the community -  

E-Print Network (OSTI)

Waste incineration and the community - The Amsterdam experience The successful community relations strategy followed by the operator of Amsterdam's waste-to- energy plant has convinced the public and other stakeholders of the benefits of incineration for treating the city's waste Thomas McCarthy Article by Thomas Mc

Columbia University

334

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING  

E-Print Network (OSTI)

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING EFFICIENCY.EFFICIENCY. A l GA leaner Green #12 t R li Management Recycling Staff The Office of Waste Reduction & Recycling started in The Office of Waste Reduction & Recycling started in 1990, we have 14 full time staff positions. ·We collect over 40

Kelly, Scott David

335

Waste Form Features, Events, and Processes  

Science Conference Proceedings (OSTI)

The purpose of this report is to evaluate and document the inclusion or exclusion of the waste form features, events and processes (FEPs) with respect to modeling used to support the Total System Performance Assessment for License Application (TSPA-LA). A screening decision, either Included or Excluded, is given for each FEP along with the technical bases for screening decisions. This information is required by the Nuclear Regulatory Commission (NRC) in 10 CFR 63.114 (d, e, and f) [DIRS 156605]. The FEPs addressed in this report deal with the issues related to the degradation and potential failure of the waste form and the migration of the waste form colloids. For included FEPs, this analysis summarizes the implementation of the FEP in TSPA-LA, (i.e., how the FEP is included). For excluded FEPs, this analysis provides the technical bases for exclusion from TSPA-LA (i.e., why the FEP is excluded). This revision addresses the TSPA-LA FEP list (DTN: MO0407SEPFEPLA.000 [DIRS 170760]). The primary purpose of this report is to identify and document the analyses and resolution of the features, events, and processes (FEPs) associated with the waste form performance in the repository. Forty FEPs were identified that are associated with the waste form performance. This report has been prepared to document the screening methodology used in the process of FEP inclusion and exclusion. The analyses documented in this report are for the license application (LA) base case design (BSC 2004 [DIRS 168489]). In this design, a drip shield is placed over the waste package and no backfill is placed over the drip shield (BSC 2004 [DIRS 168489]). Each FEP may include one or more specific issues that are collectively described by a FEP name and a FEP description. The FEP description may encompass a single feature, process or event, or a few closely related or coupled processes if the entire FEP can be addressed by a single specific screening argument or TSPA-LA disposition. The FEPs are addressed in associated analysis or model reports. The assignments were based on the nature of the FEPs so that the analysis and resolution of screening decisions reside with the subject-matter experts in the relevant disciplines.

R. Schreiner

2004-10-27T23:59:59.000Z

336

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

PIONEERING NUCLEAR WASTE DISPOSAL U.S. Department of Energy Carlsbad Area Office February 2000 DOECAO-00-3124 T h e W a s t e I s o l a t i o n P i l o t P l a n t ii Table of...

337

Proceedings: Vitrification of Low-Level Waste--the Process and Potential  

Science Conference Proceedings (OSTI)

Vitrification technology, or the consolidation of waste in a glass matrix, represents a proven method for achieving volume reduction for high-level industrial waste. Application of this technology is emerging as a viable treatment of low-level waste. This workshop focused on the range of vitrification technologies now available and highlighted issues associated with application of the vitrification process in the nuclear power industry.

1996-05-21T23:59:59.000Z

338

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

10 CFR Ch. X (1-1-12 Edition) Pt. 1022 D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE Siting, construction or expansion, and op- eration of disposal facilities for transuranic (TRU) waste and TRU mixed waste (TRU waste also containing hazardous waste as designated in 40 CFR part 261). D12 INCINERATORS Siting, construction, and operation of in- cinerators, other than research and develop- ment incinerators or incinerators for non- hazardous solid waste (as designated in 40 CFR 261.4(b)). PART 1022-COMPLIANCE WITH FLOODPLAIN AND WETLAND EN- VIRONMENTAL REVIEW REQUIRE- MENTS Subpart A-General Sec. 1022.1 Background. 1022.2 Purpose and scope. 1022.3 Policy. 1022.4 Definitions. 1022.5 Applicability. 1022.6 Public inquiries. Subpart B-Procedures for Floodplain and

339

Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Regulation No. 8 - Solid Waste Composting Facilities Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) < Back Eligibility Commercial Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Rhode Island Program Type Environmental Regulations Provider Department of Environmental Management Facilities which compost putrescible waste and/or leaf and yard waste are subject to these regulations. The regulations establish permitting, registration, and operational requirements for composting facilities. Operational requirements for putrescible waste facilities include siting, distance, and buffer requirements, as well as standards for avoiding harm to endangered species and contamination of air and water sources. Specific

340

WIPP TRANSURANIC WASTE How has the WIPP TRU Waste Inventory Changed  

E-Print Network (OSTI)

of tank waste from the Hanford site that is currently managed as high-level waste. None of this waste has that these Hanford tank wastes will be treated and will eventually be able to meet the WIPP waste acceptance criteria on the Hanford Tank Waste and K-Basin Sludges that were included in the waste inventory for recertifica- tion

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Hanford Tank Waste - Near Source Treatment of Low Activity Waste  

SciTech Connect

Treatment and disposition of Hanford Site waste as currently planned consists of I 00+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory ofthis waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most ofthe leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper describes the potential near source treatment and waste disposition options as well as the impact these options could have on reducing infrastructure requirements, project cost and mission schedule.

Ramsey, William Gene

2013-08-15T23:59:59.000Z

342

Low-level radioactive waste disposal facility closure  

Science Conference Proceedings (OSTI)

Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-11-01T23:59:59.000Z

343

Hanford Waste Physical and Rheological Properties: Data and Gaps  

SciTech Connect

The retrieval, transport, treatment and disposal operations associated with Hanford Tank Wastes involve the handling of a wide range of slurries. Knowledge of the physical and rheological properties of the waste is a key component to the success of the design and implementation of the waste processing facilities. Previous efforts to compile and analyze the physical and rheological properties were updated with new results including information on solids composition and density, particle size distributions, slurry rheology, and particle settling behavior. The primary source of additional data is from a recent series of tests sponsored by the Hanford Waste Treatment and Immobilization Plant. These tests involved an extensive suite of characterization and bench-scale process testing of 8 waste groups representing approximately 75% of the high-level waste mass expected to be processed through the WTP. Additional information on the morphology of the waste solids was also included. Based on the updated results, a gap analysis to identify gaps in characterization data, analytical methods and data interpretation was completed.

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

2012-03-01T23:59:59.000Z

344

Accumulated waste characterization work plan  

Science Conference Proceedings (OSTI)

The Portsmouth Gaseous Diffusion Plant (PORTS) as part of the uranium enrichment complex produces enriched uranium for power generation and defense purposes. Since the beginning of diffusion plant operations in 1953, a variety of waste materials and excess equipment has been generated through both normal operations and as part of major system upgrade programs. However, as a result of the closure of former onsite radioactive management facilities and limited onsite and offsite disposal facilities for mixed (hazardous and radioactive) wastes, PORTS has accumulated large quantities of waste awaiting final disposition. These accumulated wastes were estimated in the Accumulated Waste Plan (AWP) to consist of some 21,700 containers of the radioactive, RCRA hazardous, PCB, mixed and asbestos wastes in various storage areas and process buildings with PORTS. In order to proper manage these wastes onsite and prepare for them for ultimate treatment or disposal, a detailed understanding of the waste contents and characteristics must be developed. The strategy for managing and disposing of these wastes was outlined in the AWP. The purpose of this Accumulated Waste Characterization Work Plan (AWCWP) is to provide a detailed plan for characterizing waste containers from the existing PORTS inventory. The AWCWP documents the process and analytical information currently available and describes statistically-based sampling and analyses required to support proper regulatory classification.

Not Available

1992-01-01T23:59:59.000Z

345

High-Level Waste Corporate Board Performance Assessment Subcommittee  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Level Level Waste Corporate Board Performance Assessment Subcommittee John E. Marra, Ph.D. Associate Laboratory Director November 6, 2008 Richland, WA DOE-EM HLW Corporate Board Meeting Background - Performance Assessment Process Performance assessments are the fundamental risk assessment tool used by the DOE to evaluate and communicate the effectiveness and long-term impact of waste management and cleanup decisions. This includes demonstrations of compliance, NEPA analyses, and decisions about technologies and 2 analyses, and decisions about technologies and waste forms. Background - Process Perception EM-2 'Precepts' for Improved High-Level Waste Management (HLW Corporate Board Meeting - April 2008) Improved Performance Assessments (PA) The PA process is not consistently applied amongst the 3 The PA process is not consistently applied amongst the major HLW sites PA

346

Federal Court Dismisses Waste Fee Challenges | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Federal Court Dismisses Waste Fee Challenges Federal Court Dismisses Waste Fee Challenges Federal Court Dismisses Waste Fee Challenges December 13, 2010 - 2:31pm Addthis The D.C. Circuit today dismissed petitions filed by the National Association of Regulatory Utility Commissioners (NARUC) and other entities seeking (1) to force the Department to issue an assessment of the adequacy of the nuclear waste fund fee and (2) compelling suspension of the fee. These petitions were filed before the Department's recent issuance of a new fee assessment, and, in that context, the court determined that the petitions were moot and unripe. The court's order can be found here. Addthis Related Articles NARUC Releases Cybersecurity Primer for Utility Regulators (June 2012) DOE Does Not Oppose Petitions to Intervene in Yucca Mountain NRC Proceeding

347

High level waste facilities -- Continuing operation or orderly shutdown  

SciTech Connect

Two options for Environmental Impact Statement No action alternatives describe operation of the radioactive liquid waste facilities at the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory. The first alternative describes continued operation of all facilities as planned and budgeted through 2020. Institutional control for 100 years would follow shutdown of operational facilities. Alternatively, the facilities would be shut down in an orderly fashion without completing planned activities. The facilities and associated operations are described. Remaining sodium bearing liquid waste will be converted to solid calcine in the New Waste Calcining Facility (NWCF) or will be left in the waste tanks. The calcine solids will be stored in the existing Calcine Solids Storage Facilities (CSSF). Regulatory and cost impacts are discussed.

Decker, L.A.

1998-04-01T23:59:59.000Z

348

Technical resource document for assured thermal processing of wastes  

Science Conference Proceedings (OSTI)

This document is a concise compendium of resource material covering assured thermal processing of wastes (ATPW), an area in which Sandia aims to develop a large program. The ATPW program at Sandia is examining a wide variety of waste streams and thermal processes. Waste streams under consideration include municipal, chemical, medical, and mixed wastes. Thermal processes under consideration range from various incineration technologies to non-incineration processes such as supercritical water oxidation or molten metal technologies. Each of the chapters describes the element covered, discusses issues associated with its further development and/or utilization, presents Sandia capabilities that address these issues, and indicates important connections to other ATPW elements. The division of the field into elements was driven by the team`s desire to emphasize areas where Sandia`s capabilities can lead to major advances and is therefore somewhat unconventional. The report will be valuable to Sandians involved in further ATPW program development.

Farrow, R.L.; Fisk, G.A.; Hartwig, C.M.; Hurt, R.H.; Ringland, J.T.; Swansiger, W.A.

1994-06-01T23:59:59.000Z

349

Environment Canada research on land treatment of petroleum wastes  

Science Conference Proceedings (OSTI)

The purpose of the studies presented in this book is to identify wastes which can be applied to land in an environmentally acceptable manner and to provide information on which to base guidelines for the proper application of such wastes to land. The information which has been collected to date has focused on the persistence and fate of oil and toxic constituents of petroleum wastes when applied to soil, potential environmental impacts and risk to human health associated with application to land, and site managements techniques which enhance treatment of organic constituents of wastes while protecting environmental quality. The potential for contamination of groundwater, the accumulation of hazardous substances in soil and effects on plant growth have undergone the most intensive investigation to date. Impingement on air quality has received limited study.

Bulman, T.L.; Scroggins, R.P. (Wastewater Technolgy Centre, Burlington, Ontario (CA))

1988-01-01T23:59:59.000Z

350

Waste Isolation Pilot Plant - Reports  

NLE Websites -- All DOE Office Websites (Extended Search)

Reports Reports Waste Isolation Pilot Plant Review Report 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013 Review Report 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012 Activity Reports 2011 Orientation Visit to the Waste Isolation Pilot Plant, September 2011 Review Reports 2007 Independent Oversight Inspection of Emergency Management at the Carlsbad Field Office and Waste Isolation Pilot Plant, December 2007 Review Reports 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Waste Isolation Pilot Plant - Summary Report, August 2002 Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002

351

Waste Management | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Management Management Waste Management Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Read more Tank Waste and Waste Processing The Department has approximately 88 million gallons of liquid waste stored in underground tanks and approximately 4,000 cubic meters of solid waste derived from the liquids stored in bins. The current DOE estimated cost for retrieval, treatment and disposal of this waste exceeds $50 billion to be spent over several decades.

352

Environmental waste disposal contracts awarded  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental contracts awarded locally Environmental contracts awarded locally Environmental waste disposal contracts awarded locally Three small businesses with offices in Northern New Mexico awarded nuclear waste clean-up contracts. April 3, 2012 Worker moves drums of transuranic (TRU) waste at a staging area A worker stages drums of transuranic waste at Los Alamos National Laboratory's Technical Area 54. the Lap ships such drums to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) in Southern New Mexico. The Lab annually averages about 120 shipments of TRU waste to WIPP. Contact Small Business Office (505) 667-4419 Email "They will be valuable partners in the Lab's ability to dispose of the waste safely and efficiently." Small businesses selected for environmental work at LANL

353

Waste minimization handbook, Volume 1  

Science Conference Proceedings (OSTI)

This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility`s life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996.

Boing, L.E.; Coffey, M.J.

1995-12-01T23:59:59.000Z

354

Waste Management | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Cleanup » Waste Management Cleanup » Waste Management Waste Management November 12, 2013 U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal On Tuesday, November 12, 2013, the U.S. Department of Energy (DOE) will host a press call to discuss Consolidated Edison Uranium Solidification Project (CEUSP) shipment and disposal plans in Nevada. September 24, 2013 Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and

355

Waste Logic(TM): Decommissioning Waste Manager, Version 2.1 and Solid Waste Manager, Version 2.1  

Science Conference Proceedings (OSTI)

Waste Logic(TM) Decommissioning Waste Manager, Version 2.1: Rising program costs and a more competitive business environment have made solid waste management a major cost concern. Effective management of solid waste can reduce long range operating costs for a large nuclear plant by millions of dollars. To assist waste managers in maximizing potential cost savings, EPRI developed the Waste Logic Decommissioning Waste Manager(TM) computer code. It provides a comprehensive methodology for capturing and quan...

2003-03-03T23:59:59.000Z

356

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 3. Revision 1  

Science Conference Proceedings (OSTI)

This report consists of information related to the waste forms at the WIPP facility from the waste originators. Data for retrievably stored, projected and total wastes are given.

NONE

1995-02-01T23:59:59.000Z

357

Public involvement in radioactive waste management decisions  

SciTech Connect

Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE`s Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government`s decision to study Yucca Mountain. The state`s opposition reflects public opinion in Nevada, and has considerably slowed DOE`s progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada`s opposition -- its ability to thwart if not outright derail DOE`s activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE`s radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE`s low level of credibility among the general public as the product, in part, of the department`s past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials.

NONE

1994-04-01T23:59:59.000Z

358

Waste Management Quality Assurance Plan  

SciTech Connect

Lawrence Berkeley Laboratory`s Environment Department addresses its responsibilities through activities in a variety of areas. The need for a comprehensive management control system for these activities has been identified by the Department of Energy (DOE). The WM QA (Waste Management Quality Assurance) Plan is an integral part of a management system that provides controls necessary to ensure that the department`s activities are planned, performed, documented, and verified. This WM QA Plan defines the requirements of the WM QA program. These requirements are derived from DOE Order 5700.6C, Quality Assurance, the LBL Operating and Assurance Program Plan (OAP, LBL PUB-3111), and other environmental compliance documents applicable to WM activities. The requirements presented herein, as well as the procedures and methodologies that direct the implementation of these requirements, will undergo review and revisions as necessary. The provisions of this QA Plan and its implementing documents apply to quality-affecting activities performed by and for WM. It is also applicable to WM contractors, vendors, and other LBL organizations associated with WM activities, except where such contractors, vendors, or organizations are governed by their own WM-approved QA programs. References used in the preparation of this document are (1) ASME NQA-1-1989, (2) ANSI/ASQC E4 (Draft), (3) Waste Management Quality Assurance Implementing Management Plan (LBL PUB-5352, Rev. 1), (4) LBL Operating and Assurance Program Plan (OAP), LBL PUB-3111, 2/3/93. A list of terms and definitions used throughout this document is included as Appendix A.

Not Available

1993-11-30T23:59:59.000Z

359

Treatment of halogen-containing waste and other waste materials  

DOE Patents (OSTI)

A process is described for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes. 3 figs.

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1997-03-18T23:59:59.000Z

360

Treatment of halogen-containing waste and other waste materials  

DOE Patents (OSTI)

A process for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes.

Forsberg, Charles W. (Oak Ridge, TN); Beahm, Edward C. (Oak Ridge, TN); Parker, George W. (Concord, TN)

1997-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site  

Science Conference Proceedings (OSTI)

This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D&D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D&D a facility to process low-activity job-control and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS.

NONE

1998-01-01T23:59:59.000Z

362

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

363

Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Advanced Test Reactor Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. U.S. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-11-01T23:59:59.000Z

364

Standard guide for sampling radioactive tank waste  

E-Print Network (OSTI)

1.1 This guide addresses techniques used to obtain grab samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing. 1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2011-01-01T23:59:59.000Z

365

Hydraulic waste energy recovery, Phase 2  

SciTech Connect

The energy required for booster station operation is supplied by the electrical utility company and has an associated cost. Energy removed by pressure reducing valves in the system is lost or wasted. The objective of this project is to capture the wasted hydraulic energy with in-line turbines. In this application, the in-line turbines act as pressure reducing valves while removing energy from the water distribution system and converting it to electrical energy. The North Service Center pumping station was selected for the pilot program due to the availability of a wide range in pressure drop and flow, which are necessary for hydraulic energy recovery. The research performed during this project resulted in documentation of technical, economic, installation, and operational information necessary for local government officials to make an informed judgement as it relates to in-line turbine generation.

1992-02-01T23:59:59.000Z

366

Analytical and experimental evaluation of solid waste drum fire performance volumes I and II  

Science Conference Proceedings (OSTI)

Fire hazards associated with drum storage of radioactively contaminated wastes are a major concern in DOE facilities design for long term storage of solid wastes in drums. These facilities include drums stored in pallet arrays and in rack storage systems. This report details testing in this area

Hecker, C.F., [Los Alamos Technical Associates, Inc., Kennewick, WA (United States); Rhodes, B.T.; Beitel, J.J.; Gottuk, D.T.; Beyler, C.L.; Rosenbaum, E.R., [Hughes Associates, Inc., Columbia, MD (United States)

1995-04-28T23:59:59.000Z

367

Process chemistry for the pretreatment of Hanford tank wastes  

SciTech Connect

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

Lumetta, G.J.; Swanson, J.L. [Pacific Northwest Lab., Richland, WA (United States); Barker, S.A. [Westinghouse Hanford Co., Richland, WA (United States)

1992-08-01T23:59:59.000Z

368

WRAP Module 1 waste analysis plan  

Science Conference Proceedings (OSTI)

The purpose of this waste analysis plan is to document the necessary characterization, sampling, screening, analysis, and waste acceptance criteria for waste received at the WRAP Module 1. Waste expected to be received at WRAP Module 1 includes newly generated and retrieved waste. The newly generated waste will undergo verification prior to treatment, storage, or disposal. Retrieved waste from the burial grounds or above ground storage will undergo further characterization (as needed), treatment, supercompaction, and repackaging

Mayancsik, B.A.

1995-09-22T23:59:59.000Z

369

I-NERI-2007-004-K, DEVELOPMENT AND CHARACTERIZATION OF NEW HIGH-LEVEL WASTE FORMS FOR ACHIEVING WASTE MINIMIZATION FROM PYROPROCESSING  

SciTech Connect

Work describe in this report represents the final year activities for the 3-year International Nuclear Energy Research Initiative (I-NERI) project: Development and Characterization of New High-Level Waste Forms for Achieving Waste Minimization from Pyroprocessing. Used electrorefiner salt that contained actinide chlorides and was highly loaded with surrogate fission products was processed into three candidate waste forms. The first waste form, a high-loaded ceramic waste form is a variant to the CWF produced during the treatment of Experimental Breeder Reactor-II used fuel at the Idaho National Laboratory (INL). The two other waste forms were developed by researchers at the Korean Atomic Energy Research Institute (KAERI). These materials are based on a silica-alumina-phosphate matrix and a zinc/titanium oxide matrix. The proposed waste forms, and the processes to fabricate them, were designed to immobilize spent electrorefiner chloride salts containing alkali, alkaline earth, lanthanide, and halide fission products that accumulate in the salt during the processing of used nuclear fuel. This aspect of the I-NERI project was to demonstrate 'hot cell' fabrication and characterization of the proposed waste forms. The outline of the report includes the processing of the spent electrorefiner salt and the fabrication of each of the three waste forms. Also described is the characterization of the waste forms, and chemical durability testing of the material. While waste form fabrication and sample preparation for characterization must be accomplished in a radiological hot cell facility due to hazardous radioactivity levels, smaller quantities of each waste form were removed from the hot cell to perform various analyses. Characterization included density measurement, elemental analysis, x-ray diffraction, scanning electron microscopy and the Product Consistency Test, which is a leaching method to measure chemical durability. Favorable results from this demonstration project will provide additional options for fission product immobilization and waste management associated the electrochemical/pyrometallurgical processing of used nuclear fuel.

S.M. Frank

2011-09-01T23:59:59.000Z

370

Municipal Solid Waste:  

U.S. Energy Information Administration (EIA) Indexed Site

Methodology for Allocating Municipal Solid Waste Methodology for Allocating Municipal Solid Waste to Biogenic and Non-Biogenic Energy May 2007 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the U.S. Department of Energy. The information contained herein should be attributed to the Energy Information Administration and should not be construed as advocating or reflecting any policy of the Department of Energy or any other organization. Contact This report was prepared by staff of the Renewable Information Team, Coal, Nuclear, and Renewables Division, Office of Coal, Nuclear, Electric and Alternate Fuels.

371

Tritium waste package  

DOE Patents (OSTI)

A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

Rossmassler, Rich (Cranbury, NJ); Ciebiera, Lloyd (Titusville, NJ); Tulipano, Francis J. (Teaneck, NJ); Vinson, Sylvester (Ewing, NJ); Walters, R. Thomas (Lawrenceville, NJ)

1995-01-01T23:59:59.000Z

372

Tritium waste package  

DOE Patents (OSTI)

A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB adsorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1994-12-31T23:59:59.000Z

373

Tritium waste package  

DOE Patents (OSTI)

A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within the outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB. 1 fig.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1995-11-07T23:59:59.000Z

374

Waste | OpenEI  

Open Energy Info (EERE)

Waste Waste Dataset Summary Description The Planning Database Project provides the UK Department of Energy and Climate Change (DECC) with regular data to track progress towards achieving EU targets for electricity generation from renewable energy (RE) sources. Extracts from the database are available each month. Information collected in the database includes: name, location and installed capacity of RE projects over 0.1MW; environmental designations; planning status; and construction status. Included here is the October 2010 Progress Datasheet, and an extract from December, 15, 2010 (i.e. Source UK Department of Energy and Climate Change (DECC) Date Released December 15th, 2010 (3 years ago) Date Updated Unknown Keywords biomass co-firing installed capacity

375

The First Recovery Act Funded Waste Shipment depart from the...  

NLE Websites -- All DOE Office Websites (Extended Search)

The First Recovery Act Funded Waste Shipment departs from the Advanced Mixed Waste Treatment Facility A shipment of mixed low-level waste left DOEs Advanced Mixed Waste...

376

Nuclear Waste Policy Act Signed | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

> Nuclear Waste Policy Act Signed Nuclear Waste Policy Act Signed January 07, 1983 Washington, DC Nuclear Waste Policy Act Signed President Reagan signs the Nuclear Waste...

377

Mixed Waste Recycling Exemption  

Science Conference Proceedings (OSTI)

As part of an ongoing integrated mixed waste program, EPRI has documented the process for obtaining state approval to apply the Resource Conservation and Recovery Act (RCRA) recycling exemption. This report examines the regulatory basis for the recycling exemption and the strategy for designing and operating a recycling facility to meet that exemption. Specifically addressed is the process of submitting an actual recycling exemption request to an RCRA authorized state and potential roadblocks utilities m...

1998-11-30T23:59:59.000Z

378

Cooling tower waste reduction  

SciTech Connect

At Lawrence Livermore National Laboratory (LLNL), the two main cooling tower systems (central and northwest) were upgraded during the summer of 1997 to reduce the generation of hazardous waste. In 1996, these two tower systems generated approximately 135,400 lbs (61,400 kg) of hazardous sludge, which is more than 90 percent of the hazardous waste for the site annually. At both, wet decks (cascade reservoirs) were covered to block sunlight. Covering the cascade reservoirs reduced the amount of chemical conditioners (e.g. algaecide and biocide), required and in turn the amount of waste generated was reduced. Additionally, at the northwest cooling tower system, a sand filtration system was installed to allow cyclical filtering and backflushing, and new pumps, piping, and spray nozzles were installed to increase agitation. the appurtenance upgrade increased the efficiency of the cooling towers. The sand filtration system at the northwest cooling tower system enables operators to continuously maintain the cooling tower water quality without taking the towers out of service. Operational costs (including waste handling and disposal) and maintenance activities are compared for the cooling towers before and after upgrades. Additionally, the effectiveness of the sand filter system in conjunction with the wet deck covers (northwest cooling tower system), versus the cascade reservoir covers alone (south cooling tower south) is discussed. the overall expected return on investment is calculated to be in excess of 250 percent. this upgrade has been incorporated into the 1998 DOE complex-wide water conservation project being led by Sandia National Laboratory/Albuquerque.

Coleman, S.J.; Celeste, J.; Chine, R.; Scott, C.

1998-05-01T23:59:59.000Z

379

PROCESSING OF RADIOACTIVE WASTE  

DOE Patents (OSTI)

A process for treating radioactive waste solutions prior to disposal is described. A water-soluble phosphate, borate, and/or silicate is added. The solution is sprayed with steam into a space heated from 325 to 400 deg C whereby a powder is formed. The powder is melted and calcined at from 800 to 1000 deg C. Water vapor and gaseous products are separated from the glass formed. (AEC)

Johnson, B.M. Jr.; Barton, G.B.

1961-11-14T23:59:59.000Z

380

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal, Hazardous Waste Management Act, Underground Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Tribal Government Utility Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Solid Waste Disposal Laws and Regulations are found in Tenn. Code 68-211. These rules are enforced and subject to change by the Public Waste Board (PWB), which is established by the Division of Solid and Hazardous

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

SRS - Programs - Liquid Waste Disposition  

NLE Websites -- All DOE Office Websites (Extended Search)

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

382

Method for processing aqueous wastes  

DOE Patents (OSTI)

This invention is comprised of a method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

Pickett, J.B.; Martin, H.L.; Langton, C.A.; Harley, W.W.

1992-12-31T23:59:59.000Z

383

Method for processing aqueous wastes  

DOE Patents (OSTI)

A method is presented for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply. 4 figures.

Pickett, J.B.; Martin, H.L.; Langton, C.A.; Harley, W.W.

1993-12-28T23:59:59.000Z

384

Method for processing aqueous wastes  

DOE Patents (OSTI)

A method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

Pickett, John B. (3922 Wood Valley Dr., Aiken, SC 29803); Martin, Hollis L. (Rt. 1, Box 188KB, McCormick, SC 29835); Langton, Christine A. (455 Sumter St. SE., Aiken, SC 29801); Harley, Willie W. (110 Fairchild St., Batesburg, SC 29006)

1993-01-01T23:59:59.000Z

385

Radioactive waste processing apparatus  

DOE Patents (OSTI)

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container.

Nelson, Robert E. (Lombard, IL); Ziegler, Anton A. (Darien, IL); Serino, David F. (Maplewood, MN); Basnar, Paul J. (Western Springs, IL)

1987-01-01T23:59:59.000Z

386

Design requirements document for project W-520, immobilized low-activity waste disposal  

SciTech Connect

This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

Ashworth, S.C.

1998-08-06T23:59:59.000Z

387

Feasibility Study Using a Solar Evaporator to Reduce the Metalworking Fluid (MWF) Waste Stream  

DOE Green Energy (OSTI)

A solar evaporator was designed, built, and operated to reduce the water-based metalworking fluid waste stream. The evaporator was setup in Waste Managements barrel lot inside one of the confinement areas. The unit processed three batches of waste fluid during the prototype testing. Initial tests removed 13% of the fluid waste stream. Subsequent modifications to the collector improved the rate to almost 20% per week. Evaluation of the risk during operation showed that even a small spill when associated with precipitation, and the unit placement within a confinement area, gave it the potential to contaminate more fluid that what it could save.

Lazarus, Lloyd

2008-12-03T23:59:59.000Z

388

Assessment of pre-competitive research and development needs for industrial waste minimization  

Science Conference Proceedings (OSTI)

This report summarizes the findings of the first phase of a study undertaken to define a role for the Advanced Industrial Concepts (AIC) Division of the Office of Industrial Technologies (OIT) in developing waste minimization technologies for the industrial sector. The report describes the results of an industrial waste characterization based mainly on the US Environmental Protection Agency`s (EPA`s) 1989 Toxics Release Inventory (TRI) database. IN addition, it contains the results of interviews with personnel from trade associations, environmental advocacy groups, federal agencies, and industrial firms regarding pre-competitive research and development needs for industrial waste minimization. Recommendations for future AIC waste minimization activities are provided.

Young, J.K.; Fassbender, L.L. [Pacific Northwest Lab., Richland, WA (United States); Sen, R.K. [Sen (R.K.) and Associates, Washington, DC (United States)

1992-02-01T23:59:59.000Z

389

Assessment of pre-competitive research and development needs for industrial waste minimization  

Science Conference Proceedings (OSTI)

This report summarizes the findings of the first phase of a study undertaken to define a role for the Advanced Industrial Concepts (AIC) Division of the Office of Industrial Technologies (OIT) in developing waste minimization technologies for the industrial sector. The report describes the results of an industrial waste characterization based mainly on the US Environmental Protection Agency's (EPA's) 1989 Toxics Release Inventory (TRI) database. IN addition, it contains the results of interviews with personnel from trade associations, environmental advocacy groups, federal agencies, and industrial firms regarding pre-competitive research and development needs for industrial waste minimization. Recommendations for future AIC waste minimization activities are provided.

Young, J.K.; Fassbender, L.L. (Pacific Northwest Lab., Richland, WA (United States)); Sen, R.K. (Sen (R.K.) and Associates, Washington, DC (United States))

1992-02-01T23:59:59.000Z

390

Approach for enhancing nuclear materials tracking and reporting in waste  

SciTech Connect

Recent policy from the Department of Energy/Office of Safeguards and Security (DOE/OSS) has identified the need to report nuclear materials in waste in a manner that is consistent with the Department of Energy's Nuclear Materials Information System (NMIS), which uses Form 471 as its official record. NMIS is used to track nuclear material inventories while they are subject to safeguards. This requirement necessitates the reevaluation of existing business practices that are used to track and report these nuclear materials. This paper provides a methodology for applying a systems approach to the evaluation of the flow of nuclear waste materials from a generating facility through to permanent disposal. This methodology can be used to integrate existing systems and leverage data already gathered that support both the waste reporting requirements and the NMIS requirements. In order to consider an active waste reporting system that covers waste management through to final disposal, the requirements for characterization, certification, and transportation for disposal at the Waste Isolation Pilot Plant (WIPP) are used as an example. These requirements are found in the WIPP Waste Acceptance Criteria (WIPP/WAC) and associated requirement documents. This approach will prevent inconsistencies in reported data and address current and future needs. For example, spent fuel (which the U.S. intends to dispose of as high-level waste) has not been viewed as particularly attractive in terms of proliferation in comparison to materials associated with other parts of the nuclear fuel cycle. However, collecting high-level waste (or some types of defense waste) in one location where it will be left for hundreds or thousands of years presents proliferation and safeguards issues that need to be considered as part of a systems evaluation. This paper brings together information on domestic and international safeguards practices and considers the current system of documentation used by the U.S. Department of Energy for radioactive waste disposal. The information presented represents current practices, and we recognize that the practices were designed to address different goals. After providing an overview of these areas, some steps that may help develop safeguards systems for geologic repositories in the U.S. context are discussed.

Longmire, V. L. (Victoria L.); Seitz, S. L. (Sharon L.); Sinkule, B. J. (Barbara J.)

2001-06-01T23:59:59.000Z

391

Control of incidental asbestos exposure at hazardous waste sites  

Science Conference Proceedings (OSTI)

This paper discusses asbestos regulations that are not part of Superfund and examines how these regulations can help to identify, evaluate and manage the risk associated with Asbestos Containing Material (ACM) at hazardous waste cleanup sites. Unless one knows where to look for ACM at hazardous waste sites, it may go undetected even after all the traditional sampling is done. Although EPA is currently developing a policy for evaluating risk from asbestos exposure at certain Superfund sites, information from existing regulations can be used to manage hazards associated with asbestos exposure at hazardous waste sites. This paper also identifies where to find governmental agency personnel and consultants who may be retained for site-specific help.

Kaustas, R.N. (Environmental Protection Agency, Edison, NJ (United States))

1991-08-01T23:59:59.000Z

392

Cementation and solidification of miscellaneous mixed wastes at the Rocky Flats Environmental Technology Site  

Science Conference Proceedings (OSTI)

The Rocky Flats Environmental Technology Site produces a variety of wastes which are amenable to micro-encapsulation in cement Portland cement is an inexpensive and readily available material for this application. The Waste Projects (WP) group at Rocky Flats evaluated cementation to determine its effectiveness in encapsulating several wastes. These included waste analytical laboratory solutions, incinerator ash, hydroxide precipitation sludge, and an acidic solution from the Delphi process (a chemical oxidation technology being evaluated as an alternative to incineration). WP prepared surrogate wastes and conducted designed experiments to optimize the cement formulation for the waste streams. These experiments used a Taguchi or factorial experimental design, interactions between the variables were also considered in the testing. Surrogate waste samples were spiked with various levels of each of six Resource Conservation and Recovery Act (RCRA) listed metals (Cd, Cr, Ba, Pb, Ni, and Ag), cemented using the optimized formulation, and analyzed for leach resistance using the Toxicity Characteristic Leaching Procedure (TCLP). The metal spike levels chosen were based on characterization data, and also based on an estimate of the highest levels of contaminants suspected in the waste. This paper includes laboratory test results for each waste studied. These include qualitative observations as well as quantitative data from TCLP analyses and environmental cycling studies. The results from these experiments show that cement stabilization of the different wastes can produce final waste forms which meet the current RCRA Land Disposal Restriction (LDR) requirements. Formulations that resulted in LDR compliant waste forms are provided. The volume increases associated with cementation are also lower than anticipated. Future work will include verification studies with actual mixed radioactive waste as well as additional formulation development studies on other waste streams.

Phillips, J.A.; Semones, G.B.

1995-02-01T23:59:59.000Z

393

Summary of INEL research on the iron-enriched basalt waste form  

SciTech Connect

This report summarizes the knowledge base on the iron-enriched basalt (IEB) waste form developed at the Idaho National Engineering Laboratory (INEL) during 1979--1982. The results presented discuss the applicability of IEB in converting retrieved transuranic (TRU) waste from INEL`s Radioactive Waste Management Complex (RWMC) into a vitreous/ceramic (glassy/rock) stable waste form suitable for permanent disposal in an appropriate repository, such as the Waste Isolation Pilot Plant (WIPP) in New Mexico. Borosilicate glass (BSG), the approved high-level waste form, appears unsuited for this application. Melting the average waste-soil mix from the RWMC produces the IEB composition and attempting to convert IEB to the BSG composition would require additions of substantial B{sub 2}0{sub 3}, Na, and SiO{sub 2} (glass frit). IEB requires processing temperatures of 1400 to 1600{degrees}C, depending upon the waste composition. Production of the IEB waste form, using Joule heated melters, has proved difficult in the past because of electrode and refractory corrosion problems associated with the high temperature melts. Higher temperature electric melters (arc and plasma) are available to produce this final waste form. Past research focused on extensive slag property measurements, waste form leachability tests, mechanical, composition, and microstructure evaluations, as well as a host of experiments to improve production of the waste form. Past INEL studies indicated that the IEB glass-ceramic is a material that will accommodate and stabilize a wide range of heterogeneous waste materials, including long lived radionuclides and scrap metals, while maintaining a superior level of chemical and physical performance characteristics. Controlled cooling of the molten IEB and subsequent heat treatment will produce a glass-ceramic waste form with superior leach resistance.

Reimann, G.A.; Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

1992-01-01T23:59:59.000Z

394

Summary of INEL research on the iron-enriched basalt waste form  

Science Conference Proceedings (OSTI)

This report summarizes the knowledge base on the iron-enriched basalt (IEB) waste form developed at the Idaho National Engineering Laboratory (INEL) during 1979--1982. The results presented discuss the applicability of IEB in converting retrieved transuranic (TRU) waste from INEL's Radioactive Waste Management Complex (RWMC) into a vitreous/ceramic (glassy/rock) stable waste form suitable for permanent disposal in an appropriate repository, such as the Waste Isolation Pilot Plant (WIPP) in New Mexico. Borosilicate glass (BSG), the approved high-level waste form, appears unsuited for this application. Melting the average waste-soil mix from the RWMC produces the IEB composition and attempting to convert IEB to the BSG composition would require additions of substantial B{sub 2}0{sub 3}, Na, and SiO{sub 2} (glass frit). IEB requires processing temperatures of 1400 to 1600{degrees}C, depending upon the waste composition. Production of the IEB waste form, using Joule heated melters, has proved difficult in the past because of electrode and refractory corrosion problems associated with the high temperature melts. Higher temperature electric melters (arc and plasma) are available to produce this final waste form. Past research focused on extensive slag property measurements, waste form leachability tests, mechanical, composition, and microstructure evaluations, as well as a host of experiments to improve production of the waste form. Past INEL studies indicated that the IEB glass-ceramic is a material that will accommodate and stabilize a wide range of heterogeneous waste materials, including long lived radionuclides and scrap metals, while maintaining a superior level of chemical and physical performance characteristics. Controlled cooling of the molten IEB and subsequent heat treatment will produce a glass-ceramic waste form with superior leach resistance.

Reimann, G.A.; Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

1992-01-01T23:59:59.000Z

395

Waste Treatment and Immobilation Plant HLW Waste Vitrification...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

compounds VSL Vitreous State Laboratory of the Catholic University of America WESP Wet Electrostatic Precipitator WGI Washington Group International WTP Waste Treatment and...

396

Tank waste chemistry: A new understanding of waste aging  

SciTech Connect

There is concern about the risk of uncontrolled exothermic reaction(s) in Hanford Site waste tanks containing NO{sub 3}{sup {minus}}/NO{sub 2} based salts and/or metal hydroxide sludges in combination with organics or ferrocyanides. However, gradual oxidation of the waste in the tanks to less reactive species appears to have reduced the risk. In addition, wastes sampled to date contain sufficiently large quantities of water so that propagation reactions are highly unlikely. This paper investigates various aspects of the aging of Hanford tank wastes.

Babad, H. [Westinghouse Hanford Co., Richland, WA (United States); Camaioni, D.M.; Lilga, M.A.; Samuels, W.D.; Strachan, D.M. [Pacific Northwest Lab., Richland, WA (United States)

1993-02-01T23:59:59.000Z

397

Exploratory Study of Waste Generation and Waste Minimization in Sweden.  

E-Print Network (OSTI)

?? The current thesis presents an exploratory study on municipal solid waste generation and minimization in Sweden, with a focus on their connection to basic (more)

Kuslyaykina, Dina

2013-01-01T23:59:59.000Z

398

Steel-Based Alloy Waste Forms for Reprocessing Wastes  

Science Conference Proceedings (OSTI)

... although the release of some radionuclides is limited by the solubilities of the ... Hot Isostatic Pressing of Chlorine-Containing Plutonium Residues and Wastes.

399

PERIODIC WASTE DISPOSAL SYSTEM MATERIAL BALANCE TEST. CORE I, SEED I. Test Results T-641317. Section 1. First issue, June 14, 1961  

SciTech Connect

Tests were performed to determine the adequacy of storage facilities and operating procedures of the Shippingport PWR waste disposal system during a reactor refueling operation. Problems associated with the liquid waste evaporator and the various storage tanks were outlined. The activities of the wastes expelled to the reactor effluent channel and the Ohio River were compared with the design activities. (T.F.H.)

1961-10-31T23:59:59.000Z

400

Hanford A and AX-Farm Leak Assessments Report: 241-A-103, 241-A-104, 241-A-105, 241-AX-102, 241-AX-104 and Unplanned Waste Releases  

SciTech Connect

This report summarizes information on historical waste loss events associated with tanks and piplines in the 241-A and 241-AX tank farms.

Johnson, Michael E.; Field, Jim G.

2008-08-26T23:59:59.000Z

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

PROJECT STRATEGY FOR THE REMEDIATION AND DISPOSITION OF LEGACY TRANSURANIC WASTE AT THE SAVANNAH RIVER SITE, South Carolina, USA  

Science Conference Proceedings (OSTI)

This paper discusses the Savannah River Site Accelerated Transuranic (TRU) Waste Project that was initiated in April of 2009 to accelerate the disposition of remaining legacy transuranic waste at the site. An overview of the project execution strategy that was implemented is discussed along with the lessons learned, challenges and improvements to date associated with waste characterization, facility modifications, startup planning, and remediation activities. The legacy waste was generated from approximately 1970 through 1990 and originated both on site as well as at multiple US Department of Energy sites. Approximately two thirds of the waste was previously dispositioned from 2006 to 2008, with the remaining one third being the more hazardous waste due to its activity (curie content) and the plutonium isotope Pu-238 quantities in the waste. The project strategy is a phased approach beginning with the lower activity waste in existing facilities while upgrades are made to support remediation of the higher activity waste. Five waste remediation process lines will be used to support the full remediation efforts which involve receipt of the legacy waste container, removal of prohibited items, venting of containers, and resizing of contents to fit into current approved waste shipping containers. Modifications have been minimized to the extent possible to meet the accelerated goals and involve limited upgrades to address life safety requirements, radiological containment needs, and handling equipment for the larger waste containers. Upgrades are also in progress for implementation of the TRUPACT III for the shipment of Standard Large Boxes to the Waste Isolation Pilot Plant, the US TRU waste repository. The use of this larger shipping container is necessary for approximately 20% of the waste by volume due to limited size reduction capability. To date, approximately 25% of the waste has been dispositioned, and several improvements have been made to the overall processing plan as well as facility processing rates. These lessons learned, challenges, and improvements will be discussed to aid other sites in their efforts to conduct similar activities.

Rodriguez, M.

2010-12-17T23:59:59.000Z

402

WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION  

NLE Websites -- All DOE Office Websites (Extended Search)

Carlsbad, New Mexico 8822 Carlsbad, New Mexico 8822 1 NOV 2 3 2011 Mr. John Kieling , Acting Bureau Chief Hazardous Waste Bureau New Mexico Environme nt Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transmittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report Dear Mr. Kieling: This letter provides the submittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report. This report is required by and has bee n prepared in accordance with the WIPP Hazardous Waste Facility Perm it Part 2, Permit Condition 2.4. We certify under penalty of law that this document and all enclosures were prepared under our direction or supervision according to a system designed to assure that qualified personnel properly gather and evaluate the information submitted

403

Waste Management | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

July 27, 2011 July 27, 2011 End of Year 2010 SNF & HLW Inventories Map of the United States of America that shows the location of approximately 64,000 MTHM of Spent Nuclear Fuel (SNF) & 275 High-Level Radioactive Waste (HLW) Canisters. July 27, 2011 FY 2007 Total System Life Cycle Cost, Pub 2008 The Analysis of the Total System Life Cycle Cost (TSLCC) of the Civilian Radioactive Waste Management Program presents the Office of Civilian Radioactive Waste Management's (OCRWM) May 2007 total system cost estimate for the disposal of the Nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The TSLCC analysis provides a basis for assessing the adequacy of the Nuclear Waste Fund (NWF) Fee as required by Section 302 of the Nuclear Waste Policy Act of 1982 (NWPA), as amended.

404

Waste Management Process Improvement Project  

SciTech Connect

The Bechtel Hanford-led Environmental Restoration Contractor team's Waste Management Process Improvement Project is working diligently with the U.S. Department of Energy's (DOE) Richland Operations Office to improve the waste management process to meet DOE's need for an efficient, cost-effective program for the management of dangerous, low-level and mixed-low-level waste. Additionally the program must meet all applicable regulatory requirements. The need for improvement was highlighted when a change in the Groundwater/Vadose Zone Integration Project's waste management practices resulted in a larger amount of waste being generated than the waste management organization had been set up to handle.

Atwood, J.; Borden, G.; Rangel, G. R.

2002-02-25T23:59:59.000Z

405

Optimizing Organic Waste to Energy Operations  

Science Conference Proceedings (OSTI)

A waste-to-energy firm that recycles organic waste with energy recovery performs two environmentally beneficial functions: it diverts waste from landfills and it produces renewable energy. At the same time, the waste-to-energy firm serves and collects ... Keywords: environment, operating strategy, organic waste to energy, regulation, sustainability

Bar?? Ata; Deishin Lee; Mustafa H. Tongarlak

2012-04-01T23:59:59.000Z

406

What is Hazardous Hazardous waste is  

E-Print Network (OSTI)

What is Hazardous Waste? Hazardous waste is any product charac- terized or labeled as toxic, reactive, cor- rosive, flammable, combustible that is unwanted, dis- carded or no longer useful. This waste may be harmful to human health and/ or the environment. Hazardous Waste Disposal EH&S x7233 E-Waste

de Lijser, Peter

407

Feed Materials Production Center Waste Management Plan  

SciTech Connect

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the waste generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF/sub 2/, slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program.

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-12-31T23:59:59.000Z

408

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

SciTech Connect

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

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

1993-06-01T23:59:59.000Z

409

Vitrification of high sulfate wastes  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) through the Mixed Waste Integrated Program (MWIP) is investigating the application of vitrification technology to mixed wastes within the DOE system This work involves identifying waste streams, laboratory testing to identify glass formulations and characterize the vitrified product, and demonstration testing with the actual waste in a pilot-scale system. Part of this program is investigating process limits for various waste components, specifically those components that typically create problems for the application of vitrification, such as sulfate, chloride, and phosphate. This work describes results from vitrification testing for a high-sulfate waste, the 183-H Solar Evaporation Basin waste at Hanford. A low melting phosphate glass formulation has been developed for a waste stream high in sodium and sulfate. At melt temperatures in the range of 1,000 C to 1,200 C, sulfate in the waste is decomposed to gaseous oxides and driven off during melting, while the remainder of the oxides stay in the melt. Decomposition of the sulfates eliminates the processing problems typically encountered in vitrification of sulfate-containing wastes, resulting in separation of the sulfate from the remainder of the waste and allowing the sulfate to be collected in the off-gas system and treated as a secondary waste stream. Both the vitreous product and intentionally devitrified samples are durable when compared to reference glasses by TCLP and DI water leach tests. Simple, short tests to evaluate the compatibility of the glasses with potential melter materials found minimal corrosion with most materials.

Merrill, R.A.; Whittington, K.F.; Peters, R.D.

1994-09-01T23:59:59.000Z

410

Recovery Act Workers Remediate and Restore Former Waste Sites, Help Reduce  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Remediate and Restore Former Waste Sites, Help Remediate and Restore Former Waste Sites, Help Reduce Cold War Footprint Recovery Act Workers Remediate and Restore Former Waste Sites, Help Reduce Cold War Footprint The Hanford Site is looking greener these days after American Recovery and Reinvestment Act workers revegetated 166 acres across 12 waste sites, planting over 1,100 pounds of seeds and about 280,000 pounds of mulch. The largest of the sites, known as the BC Control Area, is an approximately 13-square-mile area associated with a waste disposal system used during Hanford operations. Recovery Act Workers Remediate and Restore Former Waste Sites, Help Reduce Cold War Footprint More Documents & Publications 2011 ARRA Newsletters Workers at Hanford Site Achieve Recovery Act Legacy Cleanup Goals Ahead of

411

DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5 November 2013 www.energy.gov/EM 2 * Waste Management Accomplishments and Priorities * National TRU Program Update * LLW/MLLW Disposal Update * Other Programmatic Updates * Disposition Maps - Current Tools Discussion Outline www.energy.gov/EM 3 FY13 Waste Management Accomplishments * WIPP: Emplaced 5,065 cubic meters of TRU with 89 percent of shipments departed from TRU waste sites as planned * Los Alamos: Met Framework Agreement goal for FY 13 ahead of schedule, disposing of over 1,800 cubic meters of legacy managed TRU waste * Oak Ridge: Partnered with regulators to develop strategy for

412

Glass Property Data and Models for Estimating High-Level Waste Glass Volume  

SciTech Connect

This report describes recent efforts to develop glass property models that can be used to help estimate the volume of high-level waste (HLW) glass that will result from vitrification of Hanford tank waste. The compositions of acceptable and processable HLW glasses need to be optimized to minimize the waste-form volume and, hence, to save cost. A database of properties and associated compositions for simulated waste glasses was collected for developing property-composition models. This database, although not comprehensive, represents a large fraction of data on waste-glass compositions and properties that were available at the time of this report. Glass property-composition models were fit to subsets of the database for several key glass properties. These models apply to a significantly broader composition space than those previously publised. These models should be considered for interim use in calculating properties of Hanford waste glasses.

Vienna, John D.; Fluegel, Alexander; Kim, Dong-Sang; Hrma, Pavel R.

2009-10-05T23:59:59.000Z

413

TSD capacity model interface with waste reduction planning in the Environmental Restoration Program  

Science Conference Proceedings (OSTI)

This report provides a picture of how the integration of waste generation forecasting with treatment, storage, and disposal (TSD) capacity modeling interfaces with waste reduction planning in the Environmental Restoration Program. Background information is given for the major activities at the seven Martin Marietta Energy Systems, Inc., sites: (1) Oak Ridge National Laboratory; (2) Oak Ridge Y-12 Plant; (3) Oak Ridge K-25 Site; (4) Paducah Gaseous Diffusion Plant; (5) Portsmouth Gaseous Diffusion Plant; (6) Oak Ridge Associated Universities; and (7) the off-site contaminated areas near DOE facilities. A perspective is provided for strategies to achieve waste reduction, how waste generation forecasts rates were developed, and how those forecasted waste generation rates will be used in TSD capacity modeling. The generation forecasting in combination with TSD modeling allows development of quantifiable goals and subsequent waste reduction. 2 figs.

Phifer, B.E. Jr.; Grumski, J.T.

1991-01-01T23:59:59.000Z

414

Waste management aspects of decontamination and decommissioning (D&D) projects  

Science Conference Proceedings (OSTI)

History shows that waste management concepts have generally been overlooked during the planning stages of most projects and experiments. This is resulting,in the generation of vast amounts of waste during the clean up or D&D of these facilities. Managers are not only being frustrated in their waste minimization efforts (a relatively new concept) but are also facing the prospect of not being able to dispose of the waste materials at all. At the least, managers are having to budget extraordinary amounts of time, money, and effort in defending their positions that the waste materials are not only humanly and environmentally safe, but that the waste materials are in fact what management says they are. The following discussion will attempt to provide some guidance to D&D managers to help them avoid many of the common pitfalls associated with the ultimate disposal of the materials generated during these projects.

Becker, B.D.

1993-07-01T23:59:59.000Z

415

OSS 19.5 Hazardous Waste Operations and Emergency Response 3/21/95 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5 Hazardous Waste Operations and Emergency Response 3/21/95 5 Hazardous Waste Operations and Emergency Response 3/21/95 OSS 19.5 Hazardous Waste Operations and Emergency Response 3/21/95 The objective of this surveillance is to ensure that workers who are performing activities associated with characterizing, handling, processing, storing or transporting hazardous wastes are adequately protected. The surveillance also evaluates the effectiveness of programs implemented to protect the health and safety of emergency response personnel who may be called upon to mitigate upset conditions at a facility where hazardous waste operations are conducted. Finally, the surveillance includes evaluations of the contractor's compliance with specific requirements regarding hazardous waste operations and emergency response. OSS19-05.doc

416

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 2. Revision 1  

SciTech Connect

This document is the Baseline Inventory Report for the transuranic (alpha-bearing) wastes stored at the Waste Isolation Pilot Plant (WIPP) in New Mexico. Waste stream profiles including origin, applicable EPA codes, typical isotopic composition, typical waste densities, and typical rates of waste generation for each facility are presented for wastes stored at the WIPP.

1995-02-01T23:59:59.000Z

417

WEB RESOURCE: Nuclear Waste Disposal  

Science Conference Proceedings (OSTI)

May 10, 2007 ... The complete "Yucca Mountain Resource Book" is also available for download at this site. Citation: Nuclear Waste Disposal. 2007. Nuclear...

418

Solid Waste Management Act (Pennsylvania)  

Energy.gov (U.S. Department of Energy (DOE))

This Act provides for the planning and regulation of solid waste storage, collection, transportation, processing, treatment, and disposal. It requires that municipalities submit plans for municipal...

419

Chernobyls waste site  

Science Conference Proceedings (OSTI)

An analysis of the prospects for using the Chernobyl exclusion zone for development of a spent fuel store, waste disposal site and other nuclear facilities.

Schmieman, Eric A.; Paskevych, Sergiy; Sizov, Andrey; Batiy, Valeriy

2007-02-15T23:59:59.000Z

420

Next Generation Waste Glass Melters  

activities as described in EM Tank Waste R&D Plan. Melter project in support of this activity. Facets of WTP processing being investigated/enhanced include:

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Waste disposal and renewable resources.  

E-Print Network (OSTI)

?? Purpose/aim: The purpose of this dissertation is to find out the effect of waste disposal on environment and to explore the effect of renewable (more)

Hai, Qu; PiaoYi, Sun

2013-01-01T23:59:59.000Z

422

Nuclear waste incineration technology status  

Science Conference Proceedings (OSTI)

The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance.

Ziegler, D.L.; Lehmkuhl, G.D.; Meile, L.J.

1981-07-15T23:59:59.000Z

423

Drilling Waste Management Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

The Drilling Waste Management Information System is an online resource for technical and regulatory information on practices for managing drilling muds and cuttings, including...

424

Waste Bakery on diet Sheep.  

E-Print Network (OSTI)

??This work aimed to evaluate the effects of inclusion of bakery waste (BW) in sheep diets on intake, apparent digestibility, balance of nitrogen compounds and (more)

Almira Biazon Frana

2010-01-01T23:59:59.000Z

425

Treatment of mercury containing waste  

DOE Patents (OSTI)

A process is provided for the treatment of mercury containing waste in a single reaction vessel which includes a) stabilizing the waste with sulfur polymer cement under an inert atmosphere to form a resulting mixture and b) encapsulating the resulting mixture by heating the mixture to form a molten product and casting the molten product as a monolithic final waste form. Additional sulfur polymer cement can be added in the encapsulation step if needed, and a stabilizing additive can be added in the process to improve the leaching properties of the waste form.

Kalb, Paul D. (Wading River, NY); Melamed, Dan (Gaithersburg, MD); Patel, Bhavesh R (Elmhurst, NY); Fuhrmann, Mark (Babylon, NY)

2002-01-01T23:59:59.000Z

426

FAQS Reference Guide Waste Management  

Energy.gov (U.S. Department of Energy (DOE))

This reference guide addresses the competency statements in the January 2003 edition of DOE-STD-1159-2003, Waste Management Functional Area Qualification Standard.

427

Waste Clean-up 1  

Science Conference Proceedings (OSTI)

... These figures are concepts of the Waste Retrieval System and Deployment for the Hanford, Washington tank farm, specifically focused on tank C ...

2011-09-30T23:59:59.000Z

428

Challenges of Nuclear Waste Vitrification  

Science Conference Proceedings (OSTI)

The US DOE has developed glass property-composition models to control glass compositions for HLW vitrification at Hanford Waste Treatment & Immobilization...

429

Tank waste remediation system fiscal year 1997 multi-year workplan WBS 1.1  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) established the Tank Waste Remediation System (TWRS) Program to manage and immobilize for disposal the waste contained in underground storage tanks at the Hanford Site. The TWRS program was established as a DOE major system acquisition under an approved Justification of Mission Need (JMN) dated January 19, 1993. The JMN states that the purpose of the TWRS Program is to: Resolve the tank waste safety issues; Integrate the waste disposal mission with the ongoing waste management mission; Assess the technical bases for tank waste management and disposal; Determine the technology available and develop any needed technologies; and Establish a dedicated organization and provide the resources to meet the technical challenge. The principal objectives of management of existing and future tank wastes is to cost-effectively minimize the environmental, safety, and health risks associated with stored wastes, with reduction of safety risks given the highest priority. The potentials must be minimized for release of tank wastes to the air and to the ground (and subsequently to the groundwater) and for exposure of the operating personnel to tank wastes.

Wilson, C.E.

1996-09-23T23:59:59.000Z

430

Progress in resolving Savannah River Site high-level waste tank safety issues  

SciTech Connect

At the Savannah River Site (SRS), near Aiken, South Carolina, approximately 35 million gallons of high-level radioactive waste are stored in 51 underground, carbon steel waste tanks. These tanks and associated facilities are distributed between the F and H areas, two processing areas at SRS, and are called the F- and H-area high-level waste tank farms. Within the last few years, issues have been raised about the safety of high-level waste tank farms throughout the DOE complex, including those at SRS. Plans for resolution of these issues were reported at the Waste Management 192 conference. This paper addresses progress made at SRS since 1992. Most of the efforts for resolving the six safety issues identified at SRS have concentrated on (1) preparing the tanks for waste removal and (2) completing construction, testing, and starting up three key facilities. These facilities will transform the waste into forms suitable for final disposal, specifically borosilicate glass and saltstone (grout). Removing the waste from the tanks and processing it is needed to resolve three of the safety issues. Two facilities -- In-Tank Precipitation and the Defense Waste Processing Facility -- are undergoing non-radioactive simulant testing (``cold runs``) at this time. The third facility -- Sludge Processing -- began testing with actual waste in October 1993. In Tank Precipitation is scheduled to be operating by the end of 1994.

d`Entremont, P.D.

1993-12-31T23:59:59.000Z

431

AIR POLLUTION CONTROL TECHNOLOGY DEVELOPMENT WASTE-AS-FUEL PROCESSES  

E-Print Network (OSTI)

stream char acterization for co-firing RDF and coal as perti nent to the progress of the study to date TECHNOLOGIES There are three primary thermal waste-as-fuel technologies described below: (1) co-firing of an RDF suit able for co-firing. In most instances there is little or no preprocessing associated

Columbia University

432

Test Plan: WIPP bin-scale CH TRU waste tests  

SciTech Connect

This WIPP Bin-Scale CH TRU Waste Test program described herein will provide relevant composition and kinetic rate data on gas generation and consumption resulting from TRU waste degradation, as impacted by synergistic interactions due to multiple degradation modes, waste form preparation, long-term repository environmental effects, engineered barrier materials, and, possibly, engineered modifications to be developed. Similar data on waste-brine leachate compositions and potentially hazardous volatile organic compounds released by the wastes will also be provided. The quantitative data output from these tests and associated technical expertise are required by the WIPP Performance Assessment (PA) program studies, and for the scientific benefit of the overall WIPP project. This Test Plan describes the necessary scientific and technical aspects, justifications, and rational for successfully initiating and conducting the WIPP Bin-Scale CH TRU Waste Test program. This Test Plan is the controlling scientific design definition and overall requirements document for this WIPP in situ test, as defined by Sandia National Laboratories (SNL), scientific advisor to the US Department of Energy, WIPP Project Office (DOE/WPO). 55 refs., 16 figs., 19 tabs.

Molecke, M.A.

1990-08-01T23:59:59.000Z

433

Effect of Concrete Waste Form Properties on Radionuclide Migration  

Science Conference Proceedings (OSTI)

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation) the mechanism of contaminant release, the significance of contaminant release pathways, how waste form performance is affected by the full range of environmental conditions within the disposal facility, the process of waste form aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility, the effect of waste form aging on chemical, physical, and radiological properties and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the waste forms come in contact with groundwater. Numerous sets of tests were initiated in fiscal years (FY) 2006-2009 to evaluate (1) diffusion of iodine (I) and technetium (Tc) from concrete into uncontaminated soil after 1 and 2 years, (2) I and rhenium (Re) diffusion from contaminated soil into fractured concrete, (3) I and Re (set 1) and Tc (set 2) diffusion from fractured concrete into uncontaminated soil, (4) evaluate the moisture distribution profile within the sediment half-cell, (5) the reactivity and speciation of uranium (VI) (U(VI)) compounds in concrete porewaters, (6) the rate of dissolution of concrete monoliths, and (7) the diffusion of simulated tank waste into concrete.

Mattigod, Shas V.; Bovaird, Chase C.; Wellman, Dawn M.; Skinner, De'Chauna J.; Cordova, Elsa A.; Wood, Marcus I.

2009-09-30T23:59:59.000Z

434

International low level waste disposal practices and facilities  

SciTech Connect

The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of options for the management of radioactive waste. There is a variety of alternatives for processing waste and for short term or long term storage prior to disposal. Likewise, there are various alternatives currently in use across the globe for the safe disposal of waste, ranging from near surface to geological disposal, depending on the specific classification of the waste. At present, there appears to be a clear and unequivocal understanding that each country is ethically and legally responsible for its own wastes, in accordance with the provisions of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Therefore the default position is that all nuclear wastes will be disposed of in each of the 40 or so countries concerned with nuclear power generation or part of the fuel cycle. To illustrate the global distribution of radioactive waste now and in the near future, Table 1 provides the regional breakdown, based on the UN classification of the world in regions illustrated in Figure 1, of nuclear power reactors in operation and under construction worldwide. In summary, 31 countries operate 433 plants, with a total capacity of more than 365 gigawatts of electrical energy (GW[e]). A further 65 units, totaling nearly 63 GW(e), are under construction across 15 of these nations. In addition, 65 countries are expressing new interest in, considering, or actively planning for nuclear power to help address growing energy demands to fuel economic growth and development, climate change concerns, and volatile fossil fuel prices. Of these 65 new countries, 21 are in Asia and the Pacific region, 21 are from the Africa region, 12 are in Europe (mostly Eastern Europe), and 11 in Central and South America. However, 31 of these 65 are not currently planning to build reactors, and 17 of those 31 have grids of less than 5 GW, which is said to be too small to accommodate most of the reactor designs available. For the remaining 34 countries actively planning reactors, as of September 2010: 14 indicate a strong intention to precede w

Nutt, W.M. (Nuclear Engineering Division)

2011-12-19T23:59:59.000Z

435

Integration of the informal sector into municipal solid waste management in the Philippines - What does it need?  

SciTech Connect

The integration of the informal sector into municipal solid waste management is a challenge many developing countries face. In Iloilo City, Philippines around 220 tons of municipal solid waste are collected every day and disposed at a 10 ha large dumpsite. In order to improve the local waste management system the Local Government decided to develop a new Waste Management Center with integrated landfill. However, the proposed area is adjacent to the presently used dumpsite where more than 300 waste pickers dwell and depend on waste picking as their source of livelihood. The Local Government recognized the hidden threat imposed by the waste picker's presence for this development project and proposed various measures to integrate the informal sector into the municipal solid waste management (MSWM) program. As a key intervention a Waste Workers Association, called USWAG Calahunan Livelihood Association Inc. (UCLA) was initiated and registered as a formal business enterprise in May 2009. Up to date, UCLA counts 240 members who commit to follow certain rules and to work within a team that jointly recovers wasted materials. As a cooperative they are empowered to explore new livelihood options such as the recovery of Alternative Fuels for commercial (cement industry) and household use, production of compost and making of handicrafts out of used packages. These activities do not only provide alternative livelihood for them but also lessen the generation of leachate and Greenhouse Gases (GHG) emissions from waste disposal, whereby the life time of the proposed new sanitary landfill can be extended likewise.

Paul, Johannes G., E-mail: jp.aht.p3@gmail.com [GIZ-AHT Project Office SWM4LGUs, c/o DENR, Iloilo City (Philippines); Arce-Jaque, Joan [GIZ-AHT Project Office SWM4LGUs, c/o DENR, Iloilo City (Philippines); Ravena, Neil; Villamor, Salome P. [General Service Office, City Government, Iloilo City (Philippines)

2012-11-15T23:59:59.000Z

436

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

437

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

438

Waste management plan for inactive LLLW tanks 3001-B, 3004-B, 3013, and T-30 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

Science Conference Proceedings (OSTI)

This Project Waste Management Plan identifies the waste that is expected to be generated in connection with the removal and disposition of inactive liquid low-level radioactive waste tanks 3001-B, 3004-B, and T-30, and grouting of tank 3013 at the Oak Ridge National Laboratory and the isolation of these tanks` associated piping systems. The plan also identifies the organization, responsibilities, and administrative controls that will be followed to ensure proper handling of the waste.

NONE

1995-07-01T23:59:59.000Z

439

Tank Waste Remediation System decisions and risk assessment  

SciTech Connect

The Tank Waste Remediation System (TWRS) mission is to store, treat, and immobilize the highly radioactive Hanford Site tank wastes and encapsulated cesium and strontium materials in an environmentally sound, safe, and cost effective manner. Additionally, the TWRS conducts, as part of this mission, resolution of safety issues associated with the wastes within the 177 underground radioactive waste tanks. Systems engineering principles are being applied to determine the functions and establish requirements necessary for accomplishing the TWRS mission (DOE 1994 draft). This systematic evaluation of the TWRS program has identified key decisions that must be executed to establish mission scope, determine requirements, or select a technical solution for accomplishing identified functions and requirements. Key decisions identified through the systematic evaluation of the TWRS mission are presented in this document. Potential alternative solutions to each decision are discussed. After-discussion and evaluation of each decision with effected stakeholder groups, the US Department of Energy (DOE) will select a solution from the identified alternatives for implementation. In order to proceed with the development and execution of the tank waste remediation program, the DOE has adopted a planning basis for several of these decisions, until a formal basis is established. The planning bases adopted by the DOE is continuing to be discussed with stakeholder groups to establish consensus for proceeding with proposed actions. Technical and programmatic risks associated with the planning basis adopted by the DOE are discussed.

Johnson, M.E.

1994-09-01T23:59:59.000Z

440

Waste IncIneratIon and Waste PreventIon  

E-Print Network (OSTI)

disposing of waste, it also makes consider- able amounts of energy available in the form of electricity) of electricity and 17 TWh of heat, equivalent to the supply required by a major city like Berlin. This energy can . This is equivalent to the annual CO2 emissions of some 1.6 million passenger cars. This means that waste incineration

Note: This page contains sample records for the topic "waste association iswa" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Radioactive waste processing apparatus  

DOE Patents (OSTI)

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

1985-08-30T23:59:59.000Z

442

Nevada Test Site 2008 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites  

Science Conference Proceedings (OSTI)

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2008 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities.

NSTec Environmental Management

2009-06-23T23:59:59.000Z

443

EM-21 Retrieval Knowledge Center: Waste Retrieval Challenges  

Science Conference Proceedings (OSTI)

EM-21 is the Waste Processing Division of the Office of Engineering and Technology, within the U.S. Department of Energys (DOE) Office of Environmental Management (EM). In August of 2008, EM-21 began an initiative to develop a Retrieval Knowledge Center (RKC) to provide the DOE, high level waste retrieval operators, and technology developers with centralized and focused location to share knowledge and expertise that will be used to address retrieval challenges across the DOE complex. The RKC is also designed to facilitate information sharing across the DOE Waste Site Complex through workshops, and a searchable database of waste retrieval technology information. The database may be used to research effective technology approaches for specific retrieval tasks and to take advantage of the lessons learned from previous operations. It is also expected to be effective for remaining current with state-of-the-art of retrieval technologies and ongoing development within the DOE Complex. To encourage collaboration of DOE sites with waste retrieval issues, the RKC team is co-led by the Savannah River National Laboratory (SRNL) and the Pacific Northwest National Laboratory (PNNL). Two RKC workshops were held in the Fall of 2008. The purpose of these workshops was to define top level waste retrieval functional areas, exchange lessons learned, and develop a path forward to support a strategic business plan focused on technology needs for retrieval. The primary participants involved in these workshops included retrieval personnel and laboratory staff that are associated with Hanford and Savannah River Sites since the majority of remaining DOE waste tanks are located at these sites. This report summarizes and documents the results of the initial RKC workshops. Technology challenges identified from these workshops and presented here are expected to be a key component to defining future RKC-directed tasks designed to facilitate tank waste retrieval solutions.

Fellinger, Andrew P.; Rinker, Michael W.; Berglin, Eric J.; Minichan, Richard L.; Poirier, Micheal R.; Gauglitz, Phillip A.; Martin, Bruce A.; Hatchell, Brian K.; Saldivar, Eloy; Mullen, O Dennis; Chapman, Noel F.; Wells, Beric E.; Gibbons, Peter W.

2009-04-10T23:59:59.000Z

444

WIPP Documents - Hazardous Waste Facility Permit (RCRA)  

NLE Websites -- All DOE Office Websites (Extended Search)

of Energy to manage, store, and dispose of contact-handled and remote-handled transuranic mixed waste at the Waste Isolation Pilot Plant. Mixed waste contains radioactive and...

445

Nuclear Waste Policy Act | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Waste Policy Act Nuclear Waste Policy Act Document on the Nuclear Waste Policy Act of 1982 An Act to provide for the development of repositories for the disposal of...

446

Waste Minimization Plan Colorado School of Mines  

E-Print Network (OSTI)

Waste Minimization Plan Colorado School of Mines Prepared by: Environmental Health and Safety Department Revised February 2008 #12;Waste Minimization Plan Table of Contents Policy Statement Based Chemical Inventory and Database................................................4 Centralized Waste

447

Hazardous Waste Management Standards and Regulations (Kansas)  

Energy.gov (U.S. Department of Energy (DOE))

This act states the standards and regulations for the management of hazardous waste. No person shall construct, modify or operate a hazardous waste facility or otherwise dispose of hazardous waste...

448

Municipal waste processing apparatus  

DOE Patents (OSTI)

Municipal waste materials are processed by crushing the materials so that pieces of noncombustible material are smaller than a selected size and pieces of combustible material are larger than the selected size. The crushed materials are placed on a vibrating mesh screen conveyor belt having openings which pass the smaller, noncombustible pieces of material, but do not pass the larger, combustible pieces of material. Pieces of material which become lodged in the openings of the conveyor belt may be removed by cylindrical deraggers or pressurized air. The crushed materials may be fed onto the conveyor belt by a vibrating feed plate which shakes the materials so that they tend to lie flat.

Mayberry, J.L.

1987-01-15T23:59:59.000Z

449

Municipal waste processing apparatus  

DOE Patents (OSTI)

Municipal waste materials are processed by crushing the materials so that pieces of noncombustible material are smaller than a selected size and pieces of combustible material are larger than the selected size. The crushed materials are placed on a vibrating mesh screen conveyor belt having openings which pass the smaller, noncombustible pieces of material, but do not pass the larger, combustible pieces of material. Pieces of material which become lodged in the openings of the conveyor belt may be removed by cylindrical deraggers or pressurized air. The crushed materials may be fed onto the conveyor belt by a vibrating feed plate which shakes the materials so that they tend to lie flat.

Mayberry, John L. (Idaho Falls, ID)

1988-01-01T23:59:59.000Z

450

Municipal waste processing apparatus  

DOE Patents (OSTI)

Municipal waste materials are processed by crushing the materials so that pieces of noncombustible material are smaller than a selected size and pieces of combustible material are larger than the selected size. The crushed materials are placed on a vibrating mesh screen conveyor belt having openings which pass the smaller, noncombustible pieces of material, but do not pass the larger, combustible pieces of material. Consecutive conveyors may be connected by an intermediate vibratory plate. An air knife can be used to further separate materials based on weight.

Mayberry, John L. (Idaho Falls, ID)

1989-01-01T23:59:59.000Z

451

NUCLEAR WASTE CONSULTANTS, INC.  

E-Print Network (OSTI)

Attached please find the Subtask 1.2 Management, prepared by Water, Waste bibliographical information relevant on NNWSI, now comprising 356 titles. scheduled, semi-annual update report contract. Update Report: Data Inventory and and Land (WWL). The report presents the to the all documents in the WWL library Please note that this is the last for Subtask 1.2 under the current The WWL report has received a managerial review by M. Logsdon (NWC), and the report was prepared under WWL's QA procedures, consistent with the NWC QA-manual. 009-1.2-- NNWSI DATABASE- Aucust IS- 19M-2 Auou~~~~ ~ _ _ _ 5._,1_88

Technical Review Branch

1988-01-01T23:59:59.000Z

452

Association Exchange  

Science Conference Proceedings (OSTI)

The AOCS Association Exchange program goal is to create collaborative partnerships and long term business relations with related organizations. Association Exchange Membership Information achievement application award Awards distinguished division

453

Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6 6 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August 2007 Prepared by the U.S. Department of Energy Office of River Protection Richland, Washington, 99352 07-DESIGN-046 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August 2007 Prepared by the U.S. Department of Energy Office of River Protection under Contract DE-AC05-76RL01830 07-DESIGN-046 iii Summary The U.S. Department of Energy (DOE), Office of River Protection (ORP) and the DOE Office of Environmental and Radioactive Waste Management (EM), Office of Project Recovery have completed a

454

Vitrification of hazardous and radioactive wastes  

SciTech Connect

Vitrification offers many attractive waste stabilization options. Versatility of waste compositions, as well as the inherent durability of a glass waste form, have made vitrification the treatment of choice for high-level radioactive wastes. Adapting the technology to other hazardous and radioactive waste streams will provide an environmentally acceptable solution to many of the waste challenges that face the public today. This document reviews various types and technologies involved in vitrification.

Bickford, D.F.; Schumacher, R.

1995-12-31T23:59:59.000Z

455

Waste minimization plan, T plant facilities  

SciTech Connect

This document contains the waste minimization plan for the T Plant facilities, located in the 200 West Area of the Hanford Site in south central Washington State. A waste minimization plan is one part of a multi-faceted waste management program; this waste minimization plan documents the goals and techniques of the waste minimization program, identifies methods for evaluating the progra